Sample records for underground nuclear test

  1. Contaminant Boundary at the Faultless Underground Nuclear Test

    SciTech Connect (OSTI)

    Greg Pohll; Karl Pohlmann; Jeff Daniels; Ahmed Hassan; Jenny Chapman

    2003-04-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP) have reached agreement on a corrective action strategy applicable to address the extent and potential impact of radionuclide contamination of groundwater at underground nuclear test locations. This strategy is described in detail in the Federal Facility Agreement and Consent Order (FFACO, 2000). As part of the corrective action strategy, the nuclear detonations that occurred underground were identified as geographically distinct corrective action units (CAUs). The strategic objective for each CAU is to estimate over a 1,000-yr time period, with uncertainty quantified, the three-dimensional extent of groundwater contamination that would be considered unsafe for domestic and municipal use. Two types of boundaries (contaminant and compliance) are discussed in the FFACO that will map the three-dimensional extent of radionuclide contamination. The contaminant boundary will identify the region wi th 95 percent certainty that contaminants do not exist above a threshold value. It will be prepared by the DOE and presented to NDEP. The compliance boundary will be produced as a result of negotiation between the DOE and NDEP, and can be coincident with, or differ from, the contaminant boundary. Two different thresholds are considered for the contaminant boundary. One is based on the enforceable National Primary Drinking Water Regulations for radionuclides, which were developed as a requirement of the Safe Drinking Water Act. The other is a risk-based threshold considering applicable lifetime excess cancer-risk-based criteria The contaminant boundary for the Faultless underground nuclear test at the Central Nevada Test Area (CNTA) is calculated using a newly developed groundwater flow and radionuclide transport model that incorporates aspects of both the original three-dimensional model (Pohlmann et al., 1999) and the two-dimensional model developed for the Faultless data decision analysis (DDA) (Pohll and Mihevc, 2000). This new model includes the uncertainty in the three-dimensional spatial distribution of lithology and hydraulic conductivity from the 1999 model as well as the uncertainty in the other flow and transport parameters from the 2000 DDA model. Additionally, the new model focuses on a much smaller region than was included in the earlier models, that is, the subsurface within the UC-1 land withdrawal area where the 1999 model predicted radionuclide transport will occur over the next 1,000 years. The purpose of this unclassified document is to present the modifications to the CNTA groundwater flow and transport model, to present the methodology used to calculate contaminant boundaries, and to present the Safe Drinking Water Act and risk-derived contaminant boundaries for the Faultless underground nuclear test CAU.

  2. Radionuclide Partitioning in an Underground Nuclear Test Cavity

    SciTech Connect (OSTI)

    Rose, T P; Hu, Q; Zhao, P; Conrado, C L; Dickerson, R; Eaton, G F; Kersting, A B; Moran, J E; Nimz, G; Powell, B A; Ramon, E C; Ryerson, F J; Williams, R W; Wooddy, P T; Zavarin, M

    2009-01-09T23:59:59.000Z

    In 2004, a borehole was drilled into the 1983 Chancellor underground nuclear test cavity to investigate the distribution of radionuclides within the cavity. Sidewall core samples were collected from a range of depths within the re-entry hole and two sidetrack holes. Upon completion of drilling, casing was installed and a submersible pump was used to collect groundwater samples. Test debris and groundwater samples were analyzed for a variety of radionuclides including the fission products {sup 99}Tc, {sup 125}Sb, {sup 129}I, {sup 137}Cs, and {sup 155}Eu, the activation products {sup 60}Co, {sup 152}Eu, and {sup 154}Eu, and the actinides U, Pu, and Am. In addition, the physical and bulk chemical properties of the test debris were characterized using Scanning Electron Microscopy (SEM) and Electron Microprobe measurements. Analytical results were used to evaluate the partitioning of radionuclides between the melt glass, rubble, and groundwater phases in the Chancellor test cavity. Three comparative approaches were used to calculate partitioning values, though each method could not be applied to every nuclide. These approaches are based on: (1) the average Area 19 inventory from Bowen et al. (2001); (2) melt glass, rubble, and groundwater mass estimates from Zhao et al. (2008); and (3) fission product mass yield data from England and Rider (1994). The U and Pu analyses of the test debris are classified and partitioning estimates for these elements were calculated directly from the classified Miller et al. (2002) inventory for the Chancellor test. The partitioning results from this study were compared to partitioning data that were previously published by the IAEA (1998). Predictions of radionuclide distributions from the two studies are in agreement for a majority of the nuclides under consideration. Substantial differences were noted in the partitioning values for {sup 99}Tc, {sup 125}Sb, {sup 129}I, and uranium. These differences are attributable to two factors: chemical volatility effects that occur during the initial plasma condensation, and groundwater remobilization that occurs over a much longer time frame. Fission product partitioning is very sensitive to the early cooling history of the test cavity because the decay of short-lived (t{sub 1/2} < 1 hour) fission-chain precursors occurs on the same time scale as melt glass condensation. Fission product chains that include both volatile and refractory elements, like the mass 99, 125, and 129 chains, can show large variations in partitioning behavior depending on the cooling history of the cavity. Uranium exhibits similar behavior, though the chemical processes are poorly understood. The water temperature within the Chancellor cavity remains elevated (75 C) more than two decades after the test. Under hydrothermal conditions, high solubility chemical species such as {sup 125}Sb and {sup 129}I are readily dissolved and transported in solution. SEM analyses of melt glass samples show clear evidence of glass dissolution and secondary hydrothermal mineral deposition. Remobilization of {sup 99}Tc is also expected during hydrothermal activity, but moderately reducing conditions within the Chancellor cavity appear to limit the transport of {sup 99}Tc. It is recommended that the results from this study should be used together with the IAEA data to update the range in partitioning values for contaminant transport models at the Nevada National Security Site (formerly known as the Nevada Test Site).

  3. Calculated concentrations of any radionuclide deposited on the ground by release from underground nuclear detonations, tests of nuclear rockets, and tests of nuclear ramjet engines

    SciTech Connect (OSTI)

    Hicks, H.G.

    1981-11-01T23:59:59.000Z

    This report presents calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from three types of event that deposited detectable radioactivity outside the Nevada Test Site complex, namely, underground nuclear detonations, tests of nuclear rocket engines and tests of nuclear ramjet engines.

  4. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect (OSTI)

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01T23:59:59.000Z

    The purpose of this work is to characterize groundwater flow and contaminant transport at the Shoal underground nuclear test through numerical modeling using site-specific hydrologic data. The ultimate objective is the development of a contaminant boundary, a model-predicted perimeter defining the extent of radionuclide-contaminated groundwater from the underground test throughout 1,000 years at a prescribed level of confidence. This boundary will be developed using the numerical models described here, after they are approved for that purpose by DOE and NDEP.

  5. Modeling to Support Groundwater Contaminant Boundaries for the Shoal Underground Nuclear Test

    SciTech Connect (OSTI)

    K. Pohlmann; G. Pohll; J. Chapman; A. Hassan; R. Carroll; C. Shirley

    2004-03-01T23:59:59.000Z

    Groundwater flow and radionuclide transport at the Shoal underground nuclear test are characterized using three-dimensional numerical models, based on site-specific hydrologic data. The objective of this modeling is to provide the flow and transport models needed to develop a contaminant boundary defining the extent of radionuclide-contaminated groundwater at the site throughout 1,000 years at a prescribed level of confidence. This boundary will then be used to manage the Project Shoal Area for the protection of the public and the environment.

  6. Multinational underground nuclear parks

    SciTech Connect (OSTI)

    Myers, C.W. [Nuclear Engineering and Nonproliferation Division, Los Alamos National Laboratory, MS F650, Los Alamos, NM 87544 (United States); Giraud, K.M. [Wolf Creek Nuclear Operating Corporation, 1550 Oxen Lane NE, P.O. Box 411, Burlington, KS 66839-0411 (United States)

    2013-07-01T23:59:59.000Z

    Newcomer countries expected to develop new nuclear power programs by 2030 are being encouraged by the International Atomic Energy Agency to explore the use of shared facilities for spent fuel storage and geologic disposal. Multinational underground nuclear parks (M-UNPs) are an option for sharing such facilities. Newcomer countries with suitable bedrock conditions could volunteer to host M-UNPs. M-UNPs would include back-end fuel cycle facilities, in open or closed fuel cycle configurations, with sufficient capacity to enable M-UNP host countries to provide for-fee waste management services to partner countries, and to manage waste from the M-UNP power reactors. M-UNP potential advantages include: the option for decades of spent fuel storage; fuel-cycle policy flexibility; increased proliferation resistance; high margin of physical security against attack; and high margin of containment capability in the event of beyond-design-basis accidents, thereby reducing the risk of Fukushima-like radiological contamination of surface lands. A hypothetical M-UNP in crystalline rock with facilities for small modular reactors, spent fuel storage, reprocessing, and geologic disposal is described using a room-and-pillar reference-design cavern. Underground construction cost is judged tractable through use of modern excavation technology and careful site selection. (authors)

  7. TYBO/BENHAM: Model Analysis of Groundwater Flow and Radionuclide Migration from Underground Nuclear Tests in Southwestern Pahute Mesa, Nevada

    SciTech Connect (OSTI)

    Andrew Wolfsberg; Lee Glascoe; Guoping Lu; Alyssa; Olson; Peter Lichtner; Maureen McGraw; Terry Cherry; ,; Guy Roemer

    2002-09-01T23:59:59.000Z

    Recent field studies have led to the discovery of trace quantities of plutonium originating from the BENHAM underground nuclear test in two groundwater observation wells on Pahute Mesa at the Nevada Test Site. These observation wells are located 1.3 km from the BENHAM underground nuclear test and approximately 300 m from the TYBO underground nuclear test. In addition to plutonium, several other conservative (e.g. tritium) and reactive (e.g. cesium) radionuclides were found in both observation wells. The highest radionuclide concentrations were found in a well sampling a welded tuff aquifer more than 500m above the BENHAM emplacement depth. These measurements have prompted additional investigations to ascertain the mechanisms, processes, and conditions affecting subsurface radionuclide transport in Pahute Mesa groundwater. This report describes an integrated modeling approach used to simulate groundwater flow, radionuclide source release, and radionuclide transport near the BENHAM and TYBO underground nuclear tests on Pahute Mesa. The components of the model include a flow model at a scale large enough to encompass many wells for calibration, a source-term model capable of predicting radionuclide releases to aquifers following complex processes associated with nonisothermal flow and glass dissolution, and site-scale transport models that consider migration of solutes and colloids in fractured volcanic rock. Although multiple modeling components contribute to the methodology presented in this report, they are coupled and yield results consistent with laboratory and field observations. Additionally, sensitivity analyses are conducted to provide insight into the relative importance of uncertainty ranges in the transport parameters.

  8. Challenges in defining a radiologic and hydrologic source term for underground nuclear test centers, Nevada Test Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Smith, D.K.

    1995-06-01T23:59:59.000Z

    The compilation of a radionuclide inventory for long-lived radioactive contaminants residual from nuclear testing provides a partial measure of the radiologic source term at the Nevada Test Site. The radiologic source term also includes potentially mobile short-lived radionuclides excluded from the inventory. The radiologic source term for tritium is known with accuracy and is equivalent to the hydrologic source term within the saturated zone. Definition of the total hydrologic source term for fission and activation products that have high activities for decades following underground testing involves knowledge and assumptions which are presently unavailable. Systematic investigation of the behavior of fission products, activation products and actinides under saturated or Partially saturated conditions is imperative to define a representative total hydrologic source term. This is particularly important given the heterogeneous distribution of radionuclides within testing centers. Data quality objectives which emphasize a combination of measurements and credible estimates of the hydrologic source term are a priority for near-field investigations at the Nevada Test Site.

  9. Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2011, Part 2

    SciTech Connect (OSTI)

    Pawloski, G A

    2012-01-30T23:59:59.000Z

    This report evaluates collapse evolution for selected Lawrence Livermore National Laboratory (LLNL) underground nuclear tests at the Nevada National Security Site (NNSS, formerly called the Nevada Test Site). The work is being done to support several different programs that desire access to the ground surface above expended underground nuclear tests. The programs include: the Borehole Management Program, the Environmental Restoration Program, and the National Center for Nuclear Security Gas-Migration Experiment. Safety decisions must be made before a crater area, or potential crater area, can be reentered for any work. Evaluation of cavity collapse and crater formation is input into the safety decisions. Subject matter experts from the LLNL Containment Program who participated in weapons testing activities perform these evaluations. Information used included drilling and hole construction, emplacement and stemming, timing and sequence of the selected test and nearby tests, geology, yield, depth of burial, collapse times, surface crater sizes, cavity and crater volume estimations, ground motion, and radiological release information. Both classified and unclassified data were reviewed. The evaluations do not include the effects of erosion that may modify the collapse craters over time. They also do not address possible radiation dangers that may be present. Various amounts of information are available for these tests, depending on their age and other associated activities. Lack of data can hamper evaluations and introduce uncertainty. We make no attempt to quantify this uncertainty. Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2011 was published on March 2, 2011. This report, considered Part 2 of work undertaken in calendar year 2011, compiles evaluations requested after the March report. The following unclassified summary statements describe collapse evolution and crater stability in response to a recent request to review 6 LLNL test locations in Yucca Flat, Rainier Mesa, and Pahute Mesa. They include: Baneberry in U8d; Clearwater in U12q; Wineskin in U12r, Buteo in U20a and Duryea in nearby U20a1; and Barnwell in U20az.

  10. Neptunium Transport Behavior in the Vicinity of Underground Nuclear Tests at the Nevada Test Site

    SciTech Connect (OSTI)

    Zhao, P; Tinnacher, R M; Zavarin, M; Williams, R W; Kersting, A B

    2010-12-03T23:59:59.000Z

    We used short lived {sup 239}Np as a yield tracer and state of the art magnetic sector ICP-MS to measure ultra low levels of {sup 237}Np in a number of 'hot wells' at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site (NTS). The results indicate that {sup 237}Np concentrations at the Almendro, Cambric, Dalhart, Cheshire and Chancellor sites, are in the range of 3 x 10{sup -5} to 7 x 10{sup -2} pCi/L and well below the MCL for alpha emitting radionuclides (15 pCi/L) (EPA, 2009). Thus, while Np transport is believed to occur at the NNSS, activities are expected to be well below the regulatory limits for alpha-emitting radionuclides. We also compared {sup 237}Np concentration data to other radionuclides, including tritium, {sup 14}C, {sup 36}Cl, {sup 99}Tc, {sup 129}I, and plutonium, to evaluate the relative {sup 237}Np transport behavior. Based on isotope ratios relative to published unclassified Radiologic Source Terms (Bowen et al., 1999) and taking into consideration radionuclide distribution between melt glass, rubble and groundwater (IAEA, 1998), {sup 237}Np appears to be substantially less mobile than tritium and other non-sorbing radionuclides, as expected. However, this analysis also suggests that {sup 237}Np mobility is surprisingly similar to that of plutonium. The similar transport behavior of Np and Pu can be explained by one of two possibilities: (1) Np(IV) and Pu(IV) oxidation states dominate under mildly reducing NNSS groundwater conditions resulting in similar transport behavior or (2) apparent Np transport is the result of transport of its parent {sup 241}Pu and {sup 241}Am isotopes and subsequent decay to {sup 237}Np. Finally, measured {sup 237}Np concentrations were compared to recent Hydrologic Source Term (HST) models. The 237Np data collected from three wells in Frenchman Flat (RNM-1, RNM-2S, and UE-5n) are in good agreement with recent HST transport model predictions (Carle et al., 2005). The agreement provides confidence in the results of the predictive model. The comparison to Cheshire HST model predictions (Pawloski et al, 2001) is somewhat ambiguous due to the low concentration resolution of the particle transport model.

  11. Evaluation of Cavity Collapse and Surface Crater Formation for Selected Lawrence Livermore National Laboratory Underground Nuclear Tests - 2010

    SciTech Connect (OSTI)

    Pawloski, G A

    2011-01-03T23:59:59.000Z

    This report evaluates collapse evolution for selected Lawrence Livermore National Laboratory (LLNL) underground nuclear tests at the Nevada National Security Site (NNSS, formerly called the Nevada Test Site). The work is being done at the request of Navarro-Interra LLC, and supports environmental restoration efforts by the Department of Energy, National Nuclear Security Administration for the Nevada Site Office. Safety decisions must be made before a surface crater area, or potential surface crater area, can be reentered for any work. Our statements on cavity collapse and surface crater formation are input into their safety decisions. These statements do not include the effects of erosion that may modify the surface collapse craters over time. They also do not address possible radiation dangers that may be present. Subject matter experts from the LLNL Containment Program who had been active in weapons testing activities performed these evaluations. Information used included drilling and hole construction, emplacement and stemming, timing and sequence of the selected test and nearby tests, geology, yield, depth of burial, collapse times, surface crater sizes, cavity and crater volume estimations, and ground motion. Both classified and unclassified data were reviewed. Various amounts of information are available for these tests, depending on their age and other associated activities. Lack of data can hamper evaluations and introduce uncertainty. We make no attempt to quantify this uncertainty.

  12. Proceedings of the Numerical Modeling for Underground Nuclear Test Monitoring Symposium

    SciTech Connect (OSTI)

    Taylor, S.R.; Kamm, J.R. [eds.

    1993-11-01T23:59:59.000Z

    The purpose of the meeting was to discuss the state-of-the-art in numerical simulations of nuclear explosion phenomenology with applications to test ban monitoring. We focused on the uniqueness of model fits to data, the measurement and characterization of material response models, advanced modeling techniques, and applications of modeling to monitoring problems. The second goal of the symposium was to establish a dialogue between seismologists and explosion-source code calculators. The meeting was divided into five main sessions: explosion source phenomenology, material response modeling, numerical simulations, the seismic source, and phenomenology from near source to far field. We feel the symposium reached many of its goals. Individual papers submitted at the conference are indexed separately on the data base.

  13. Development and Testing of a Groundwater Management Model for the Faultless Underground Nuclear Test, Central Nevada Test Area

    SciTech Connect (OSTI)

    Douglas P. Boyle; Gregg Lamorey; Scott Bassett; Greg Pohll; Jenny Chapman

    2006-01-25T23:59:59.000Z

    This document describes the development and application of a user-friendly and efficient groundwater management model of the Central Nevada Test Area (CNTA) and surrounding areas that will allow the U.S. Department of Energy and state personnel to evaluate the impact of future proposed scenarios. The management model consists of a simple hydrologic model within an interactive groundwater management framework. This framework is based on an object user interface that was developed by the U.S. Geological Survey and has been used by the Desert Research Institute researchers and others to couple disparate environmental resource models, manage the necessary temporal and spatial data, and evaluate model results for management decision making. This framework was modified and applied to the CNTA and surrounding Hot Creek Valley. The utility of the management model was demonstrated through the application of hypothetical future scenarios including mineral mining, regional expansion of agriculture, geothermal energy production, and export of water to large urban areas outside the region. While the results from some of the scenarios indicated potential impacts to the region near CNTA and others did not, together they demonstrate the usefulness of the management tool for managers who need to evaluate the impact proposed changes in groundwater use in or near CNTA may have on radionuclide migration.

  14. Surface effects of underground nuclear explosions

    SciTech Connect (OSTI)

    Allen, B.M.; Drellack, S.L. Jr.; Townsend, M.J.

    1997-06-01T23:59:59.000Z

    The effects of nuclear explosions have been observed and studied since the first nuclear test (code named Trinity) on July 16, 1945. Since that first detonation, 1,053 nuclear tests have been conducted by the US, most of which were sited underground at the Nevada Test Site (NTS). The effects of underground nuclear explosions (UNEs) on their surroundings have long been the object of much interest and study, especially for containment, engineering, and treaty verification purposes. One aspect of these explosion-induced phenomena is the disruption or alteration of the near-surface environment, also known as surface effects. This report was prepared at the request of the Los Alamos National Laboratory (LANL), to bring together, correlate, and preserve information and techniques used in the recognition and documentation of surface effects of UNEs. This report has several main sections, including pertinent background information (Section 2.0), descriptions of the different types of surface effects (Section 3.0), discussion of their application and limitations (Section 4.0), an extensive bibliography and glossary (Section 6.0 and Appendix A), and procedures used to document geologic surface effects at the NTS (Appendix C). Because a majority of US surface-effects experience is from the NTS, an overview of pertinent NTS-specific information also is provided in Appendix B. It is not within the scope of this report to explore new relationships among test parameters, physiographic setting, and the types or degree of manifestation of surface effects, but rather to compile, summarize, and capture surface-effects observations and interpretations, as well as documentation procedures and the rationale behind them.

  15. Prediction of Pseudo relative velocity response spectra at Yucca Mountain for underground nuclear explosions conducted in the Pahute Mesa testing area at the Nevada testing site; Yucca Mountain Site Characterization Project

    SciTech Connect (OSTI)

    Phillips, J.S.

    1991-12-01T23:59:59.000Z

    The Yucca Mountain Site Characterization Project (YMP), managed by the Office of Geologic Disposal of the Office of Civilian Radioactive Waste Management of the US Department of Energy, is examining the feasibility of siting a repository for commercial, high-level nuclear wastes at Yucca Mountain on and adjacent to the Nevada Test Site (NTS). This work, intended to extend our understanding of the ground motion at Yucca Mountain resulting from testing of nuclear weapons on the NTS, was funded by the Yucca Mountain project and the Military Applications Weapons Test Program. This report summarizes one aspect of the weapons test seismic investigations conducted in FY88. Pseudo relative velocity response spectra (PSRV) have been calculated for a large body of surface ground motions generated by underground nuclear explosions. These spectra have been analyzed and fit using multiple linear regression techniques to develop a credible prediction technique for surface PSRVs. In addition, a technique for estimating downhole PSRVs at specific stations is included. A data summary, data analysis, prediction development, prediction evaluation, software summary and FORTRAN listing of the prediction technique are included in this report.

  16. COST AND SCHEDULE FOR DRILLING AND MINING UNDERGROUND TEST FACILITIES

    E-Print Network [OSTI]

    Lamb, D.W.

    2013-01-01T23:59:59.000Z

    SCHEDULE FOR DRILLING AND MINING UNDERGROUND TEST FACILITIEStimes are calculated for a mining and drilling progrilln toof cost and time to compl mining and core drilling for

  17. Glass produced by underground nuclear explosions. [Rainier

    SciTech Connect (OSTI)

    Schwartz, L.; Piwinskii, A.; Ryerson, F.; Tewes, H.; Beiriger, W.

    1983-01-01T23:59:59.000Z

    Detonation of an underground nuclear explosive produces a strong shock wave which propagates spherically outward, vaporizing the explosive and nearby rock and melting, the surrounding rock. The vaporized material expands adiabatically, forming a cavity. As the energy is dissipated during the cavity formation process, the explosive and rock debris condense and mix with the melted rock. The melt flows to the bottom of the cavity where it is quenched by fractured rock fragments falling from above as the cavity collapses. Measurements indicate that about 740 tonnes of rock and/or soil are melted for every kiloton (10/sup 12/ calories) of explosive energy, or about 25% of the explosive energy goes to melting rock. The resulting glass composition reflects the composition of the unaltered rock with explosive debris. The appearance ranges from white pumice to dense, dark lava. The bulk composition and color vary with the amount of explosive iron incorporated into the glass. The refractory explosion products are mixed with the solidified melt, although the degree of mixing is variable. Electron microprobe studies of glasses produced by Rainier in welded tuff have produced the following results: glasses are dehydrated relative to the host media, glasses are extremely heterogeneous on a 20 ..mu..m scale, a ubiquitous feature is the presence of dark marble-cake regions in the glass, which were locally enriched in iron and may be related to the debris, optically amorphous regions provide evidence of shock melting, only limited major element redistribution and homogenization occur within the cavity.

  18. Focused evaluation of selected remedial alternatives for the underground test area

    SciTech Connect (OSTI)

    NONE

    1997-04-01T23:59:59.000Z

    The Nevada Test Site (NTS), located in Nye County in southern Nevada, was the location of 928 nuclear tests conducted between 1951 and 1992. Of the total tests, 824 were nuclear tests performed underground. This report describes the approach taken to determine whether any specific, proven, cost-effective technologies currently exist to aid in the removal of the radioactive contaminants from the groundwater, in the stabilization of these contaminants, and in the removal of the source of the contaminants.

  19. Underground nuclear energy complexes - technical and economic advantages

    SciTech Connect (OSTI)

    Myers, Carl W [Los Alamos National Laboratory; Kunze, Jay F [IDAHO STATE UNIV; Giraud, Kellen M [BABECOCK AND WILCOX; Mahar, James M [IDAHO STATE UNIV

    2010-01-01T23:59:59.000Z

    Underground nuclear power plant parks have been projected to be economically feasible compared to above ground instalIations. This paper includes a thorough cost analysis of the savings, compared to above ground facilities, resulting from in-place entombment (decommissioning) of facilities at the end of their life. reduced costs of security for the lifetime of the various facilities in the underground park. reduced transportation costs. and reduced costs in the operation of the waste storage complex (also underground). compared to the fair share of the costs of operating a national waste repository.

  20. Nevada National Security Site Underground Test Area (UGTA) Flow...

    Office of Environmental Management (EM)

    December 12, 2014 To view all the P&RA CoP 2014 Technical Exchange Meeting videos click here. Video Presentation Nevada National Security Site Underground Test Area...

  1. An underground characterization program for a nuclear fuel waste disposal vault in plutonic rock

    SciTech Connect (OSTI)

    Thompson, P.M.; Everitt, R.A. [AECL Research, Pinawa, Manitoba (Canada). Whiteshell Labs.

    1993-12-31T23:59:59.000Z

    The Canadian Nuclear Fuel Waste Management Program (CNFWMP) is developing a concept for disposing of nuclear fuel waste that involves placing and sealing it in a disposal vault excavated 500 to 1,000 m deep in the stable plutonic rock of the Canadian Shield. In this concept, engineered and natural barriers serve to isolate the waste from the biosphere. Since 1983, underground characterization and testing in support of the CNFWMP has been ongoing at the Underground Research Laboratory (URL) in southeastern Manitoba. This paper draws on experience gained at the URL to recommend an approach to underground characterization that would provide the necessary information to make design decisions for a disposal vault in plutonic rock.

  2. Program for large-scale underground-coal-gasification tests

    SciTech Connect (OSTI)

    Hammesfahr, F.W.; Winter, P.L.

    1982-11-01T23:59:59.000Z

    The continuing development of underground coal gasification technology requires extended multi-module field programs in which the output gas is linked to surface usage. This effort was to appraise whether existing surface facilities in the utility, petroleum refinery, or natural gas industries could be used to reduce the cost of such an extended multi-module test and whether regional demand in areas having underground coal gasification coal resources could support the manufacture of transportation fuels from underground coal gasification gases. To limit the effort to a reasonable level but yet to permit a fair test of the concept, effort was focused on five states, Illinois, New Mexico, Texas, Washington, and Wyoming, which have good underground coal gasification reserves. Studies of plant distribution located 25 potential sites within 3 miles of the underground coal gasification amenable reserves in the five states. Distribution was 44% to utilities, 44% to refineries, and 12% to gas processing facilities. The concept that existing surface facilities, currently or potentially gas-capable, might contribute to the development of underground coal gasification technology by providing a low cost industrial application for the gas produced in a multi-module test appears valid. To further test the concept, three industries were reviewed in depth. These were the electric utility, natural gas, and petroleum industries. When looking at a fuel substitution of the type proposed, each industry had its special perspective. These are discussed in detail in the report.

  3. Hanna, Wyoming underground coal gasification field test series

    SciTech Connect (OSTI)

    Bartke, T.C.; Gunn, R.D.

    1983-01-01T23:59:59.000Z

    The six in situ coal gasification field tests conducted by LETC near Hanna, WY, demonstrated typical gasification rates of 100 tons/day for continuous operation of about 30 days. Featuring high coal recovery and high product-gas calorific values, the underground process proved to be simple, reliable, and potentially controllable.

  4. REGIONAL THERMOHYDROLOGICAL EFFECTS OF AN UNDERGROUND REPOSITORY FOR NUCLEAR WASTES IN HARD ROCK

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2014-01-01T23:59:59.000Z

    underground repository for nuclear waste in hard rock, LBL-and Vath, J.E. , Nuclear waste projections and source-termthe Scientific Basis for Nuclear Waste Management, Material

  5. Underground Exploration

    E-Print Network [OSTI]

    Underground Exploration and Testing A Report to Congress and the Secretary of Energy Nuclear Waste . . . . . . . . . . . . . . . . . . . . . . . . 14 Use rail to support tunnel boring machine operation . . . . . . . . . 14 Excavate smaller diameter tunnels outside the portal-to-portal loop . 15 Use a tunnel boring machine to excavate the core test area

  6. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOE Patents [OSTI]

    Hampel, V.E.

    1988-05-17T23:59:59.000Z

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  7. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOE Patents [OSTI]

    Hampel, Viktor E. (Pleasanton, CA)

    1989-01-01T23:59:59.000Z

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  8. Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Irene Farnham

    2011-05-01T23:59:59.000Z

    This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

  9. Underground tank vitrification: Engineering-scale test results

    SciTech Connect (OSTI)

    Campbell, B.E.; Timmerman, C.L.; Bonner, W.F.

    1990-06-01T23:59:59.000Z

    Contamination associated with underground tanks at US Department of Energy sites and other sites may be effectively remediated by application of in situ vitrification (ISV) technology. In situ vitrification converts contaminated soil and buried wastes such as underground tanks into a glass and crystalline block, similar to obsidian with crystalline phases. A radioactive engineering-scale test performed at Pacific Northwest Laboratory in September 1989 demonstrated the feasibility of using ISV for this application. A 30-cm-diameter (12-in.-diameter) buried steel and concrete tank containing simulated tank sludge was vitrified, producing a solid block. The tank sludge used in the test simulated materials in tanks at Oak Ridge National Laboratory. Hazardous components of the tank sludge were immobilized or removed and captured in the off-gas treatment system. The steel tank was converted to ingots near the bottom of the block and the concrete walls were dissolved into the resulting glass and crystalline block. Although one of the four moving electrodes froze'' in place about halfway into the test, operations were able to continue. The test was successfully completed and all the tank sludge was vitrified. 7 refs., 12 figs., 5 tabs.

  10. Xenon monitoring and the Comprehensive Nuclear-Test-Ban Treaty

    SciTech Connect (OSTI)

    Bowyer, Theodore W. [Nuclear Explosion Monitoring Program, Pacific Northwest National Laboratory, Richland, Washington 99352 (United States)

    2014-05-09T23:59:59.000Z

    How do you monitor (verify) a CTBT? It is a difficult challenge to monitor the entire world for nuclear tests, regardless of size. Nuclear tests 'normally' occur underground, above ground or underwater. Setting aside very small tests (let's limit our thinking to 1 kiloton or more), nuclear tests shake the ground, emit large amounts of radioactivity, and make loud noises if in the atmosphere (or hydroacoustic waves if underwater)

  11. NNSA Commemorates the 20th Anniversary of the Last Underground...

    National Nuclear Security Administration (NNSA)

    Commemorates the 20th Anniversary of the Last Underground Nuclear Test | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the...

  12. Underground Test Area Project Waste Management Plan (Rev. No. 2, April 2002)

    SciTech Connect (OSTI)

    IT Corporation, Las Vegas

    2002-04-24T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office (NNSA/NV) initiated the UGTA Project to characterize the risk posed to human health and the environment as a result of underground nuclear testing activities at the Nevada Test Site (NTS). The UGTA Project investigation sites have been grouped into Corrective Action Units (CAUs) in accordance with the most recent version of the Federal Facility Agreement and Consent Order. The primary UGTA objective is to gather data to characterize the groundwater aquifers beneath the NTS and adjacent lands. The investigations proposed under the UGTA program may involve the drilling and sampling of new wells; recompletion, monitoring, and sampling of existing wells; well development and hydrologic/ aquifer testing; geophysical surveys; and subsidence crater recharge evaluation. Those wastes generated as a result of these activities will be managed in accordance with existing federal and state regulations, DOE Orders, and NNSA/NV waste minimization and pollution prevention objectives. This Waste Management Plan provides a general framework for all Underground Test Area (UGTA) Project participants to follow for the characterization, storage/accumulation, treatment, and disposal of wastes generated by UGTA Project activities. The objective of this waste management plan is to provide guidelines to minimize waste generation and to properly manage wastes that are produced. Attachment 1 to this plan is the Fluid Management Plan and details specific strategies for management of fluids produced under UGTA operations.

  13. Design and Field Testing of an Autonomous Underground Tramming System

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    , the repetitive "load-haul-dump" cycle is well suited to automation. In this case, a vehicle called a load underground mining vehicle. Described is the development of a fast, re- liable, and robust "autotramming in underground mining operations by robotiz- ing some of the functions of underground vehicles. For example

  14. Analysis, comparison, and modeling of radar interferometry, date of surface deformation signals associated with underground explosions, mine collapses and earthquakes. Phase I: underground explosions, Nevada Test Site

    SciTech Connect (OSTI)

    Foxall, W; Vincent, P; Walter, W

    1999-07-23T23:59:59.000Z

    We have previously presented simple elastic deformation modeling results for three classes of seismic events of concern in monitoring the CTBT--underground explosions, mine collapses and earthquakes. Those results explored the theoretical detectability of each event type using synthetic aperture radar interferometry (InSAR) based on commercially available satellite data. In those studies we identified and compared the characteristics of synthetic interferograms that distinguish each event type, as well the ability of the interferograms to constrain source parameters. These idealized modeling results, together with preliminary analysis of InSAR data for the 1995 mb 5.2 Solvay mine collapse in southwestern Wyoming, suggested that InSAR data used in conjunction with regional seismic monitoring holds great potential for CTBT discrimination and seismic source analysis, as well as providing accurate ground truth parameters for regional calibration events. In this paper we further examine the detectability and ''discriminating'' power of InSAR by presenting results from InSAR data processing, analysis and modeling of the surface deformation signals associated with underground explosions. Specifically, we present results of a detailed study of coseismic and postseismic surface deformation signals associated with underground nuclear and chemical explosion tests at the Nevada Test Site (NTS). Several interferograms were formed from raw ERS-1/2 radar data covering different time spans and epochs beginning just prior to the last U.S. nuclear tests in 1992 and ending in 1996. These interferograms have yielded information about the nature and duration of the source processes that produced the surface deformations associated with these events. A critical result of this study is that significant post-event surface deformation associated with underground nuclear explosions detonated at depths in excess of 600 meters can be detected using differential radar interferometry. An immediate implication of this finding is that underground nuclear explosions may not need to be captured coseismically by radar images acquired before and after an event in order to be detectable. This has obvious advantages in CTBT monitoring since suspect seismic events--which usually can be located within a 100 km by 100 km area of an ERS-1/2 satellite frame by established seismic methods-can be imaged after the event has been identified and located by existing regional seismic networks. Key Words: InSAR, SLC images, interferogram, synthetic interferogram, ERS-1/2 frame, phase unwrapping, DEM, coseismic, postseismic, source parameters.

  15. Hydrologic Resources Management Program and Underground Test Area Project FY 2000 Progress Report

    SciTech Connect (OSTI)

    Davisson, M L; Eaton, G F; Hakemi, N L; Hudson, G B; Hutcheon, I D; Lau, C A; Kersting, A B; Kenneally, J M; Moran, J E; Phinney, D L; Rose, T P; Smith, D K; Sylwester, E R; Wang, L; Williams, R; Zavarin, M

    2001-07-01T23:59:59.000Z

    This report highlights the results of FY 2000 technical studies conducted by the Analytical and Nuclear Chemistry Division (ANCD) at Lawrence Livermore National Laboratory (LLNL) in support of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area (UGTA) Project. This is the latest in a series of annual reports published by LLNL-ANCD to document recent investigations of radionuclide migration and transport processes at the Nevada Test Site (NTS). The HRMP is sponsored by Defense Programs (DP) at the U.S. Department of Energy, Nevada Operations Office (DOENV), and supports DP operations at the NTS through studies of radiochemical and hydrologic processes that are relevant to the DP mission. Other organizations that support the HRMP include Los Alamos National Laboratory (LANL), the U.S. Geological Survey (USGS), the Desert Research Institute (DRI) of the University of Nevada, the U.S. Environmental Protection Agency (EPS), and Bechtel Nevada (BN). The UGTA Project is sponsored by the Environmental Management (EM) program at DOENV; its goal is to determine the extent of radionuclide contamination in groundwater resulting from underground nuclear testing at the NTS. The project strategy follows guidelines set forth in a Federal Facilities Agreement and Consent Order between the U.S. Department of Energy, the U.S. Department of Defense, and the State of Nevada. Participating contractors include LLNL (both ANCD and the Energy and Environmental Sciences Directorate), LANL, USGS, DRI, BN, and IT Corporation (with subcontract support from Geotrans Inc.).

  16. Underground Infrastructure Impacts Due to a Surface Burst Nuclear Device in an Urban Canyon Environment

    SciTech Connect (OSTI)

    Bos, Randall J. [Los Alamos National Laboratory; Dey, Thomas N. [Los Alamos National Laboratory; Runnels, Scott R. [Los Alamos National Laboratory

    2012-07-03T23:59:59.000Z

    Investigation of the effects of a nuclear device exploded in a urban environment such as the Chicago studied for this particular report have shown the importance on the effects from the urban canyons so typical of today's urban environment as compared to nuclear test event effects observed at the Nevada Test Site (NTS) and the Pacific Testing Area on which many of the typical legacy empirical codes are based on. This report first looks at the some of the data from nuclear testing that can give an indication of the damage levels that might be experienced due to a nuclear event. While it is well known that a above ground blast, even a ground burst, very poorly transmits energy into the ground ( < 1%) and the experimental results discussed here are for fully coupled detonations, these results do indicate a useful measure of the damage that might be expected. The second part of the report looks at effects of layering of different materials that typically would make up the near ground below surface environment that a shock would propagate through. As these simulations support and is widely known in the community, the effects of different material compositions in these layers modify the shock behavior and especially modify the energy dispersal and coupling into the basement structures. The third part of the report looks at the modification of the underground shock effects from a surface burst 1 KT device due to the presence of basements under the Chicago buildings. Without direct knowledge of the basement structure, a simulated footprint of a uniform 20m depth was assumed underneath each of the NGI defined buildings in the above ground environment. In the above ground case, the underground basement structures channel the energy along the line of site streets keeping the shock levels from falling off as rapidly as has been observed in unobstructed detonations. These simulations indicate a falloff of factors of 2 per scaled length as compared to 10 for the unobstructed case. Again, as in the above ground case, the basements create significant shielding causing the shock profile to become more square and reducing the potential for damage diagonal to the line of sight streets. The results for a 1KT device is that the heavily damaged zone (complete destruction) will extend out to 50m from the detonation ({approx}100m for 10KT). The heavily to moderately damaged zone will extend out to 100m ({approx}200m for 10KT). Since the destruction will depend on geometric angle from the detonation and also the variability of response for various critical infrastructure, for planning purposes the area out to 100m from the detonation should be assumed to be non-operational. Specifically for subway tunnels, while not operational, they could be human passable for human egress in the moderately damaged area. The results of the simulations presented in this report indicate only the general underground infrastructure impact. Simulations done with the actual basement geometry would be an important improvement. Equally as important or even more so, knowing the actual underground material configurations and material composition would be critical information to refine the calculations. Coupling of the shock data into structural codes would help inform the emergency planning and first response communities on the impact to underground structures and the state of buildings after the detonation.

  17. amchitka underground nuclear: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    searches, with a 20 kiloton liquid scintillator detector of unprecedented 3% energy resolution (at 1 MeV) at 700-meter deep underground and to have other rich scientific...

  18. The strengthening and repair of underground structures: A new approach to the management of nuclear waste

    SciTech Connect (OSTI)

    Colgate, S.A.

    1991-01-01T23:59:59.000Z

    This paper presents three closely related ideas and technologies: (1) The secure, repairable, long time confinement of nuclear radioactive waste underground by a large surrounding region of compressive overstress; (2) The inherent tectonic weakness and vulnerability of the normal underground environment and its modification by overstress; (3) The process of creating overstress by the sequential periodic high pressure injection of a finite gel strength rapid setting grout. 12 refs., 6 figs.

  19. Pricetown I underground coal gasification field test: operations report

    SciTech Connect (OSTI)

    Agarwal, A.K.; Seabaugh, P.W.; Zielinski, R.E.

    1981-01-01T23:59:59.000Z

    An Underground Coal Gasification (UCG) field test in bituminous coal was successfully completed near Pricetown, West Virginia. The primary objective of this field test was to determine the viability of the linked vertical well (LVV) technology to recover the 900 foot deep, 6 foot thick coal seam. A methane rich product gas with an average heating value of approximately 250 Btu/SCF was produced at low air injection flow rates during the reverse combustion linkage phase. Heating value of the gas produced during the linkage enhancement phase was 221 Btu/SCF with air injection. The high methane formation has been attributed to the thermal and hydrocracking of tars and oils along with hydropyrolysis and hydrogasification of coal char. The high heating value of the gas was the combined effect of residence time, flow pattern, injection flow rate, injection pressure, and back pressure. During the gasification phase, a gas with an average heating value of 125 Btu/SCF was produced with only air injection, which resulted in an average energy production of 362 MMBtu/day.

  20. Steam tracer experiment at the Hoe Creek No. 3 underground coal gasification field test

    SciTech Connect (OSTI)

    Thorsness, C.B.

    1980-11-26T23:59:59.000Z

    Water plays an important role in in-situ coal gasification. To better understand this role, we conducted a steam tracer test during the later stages of the Hoe Creek No. 3 underground coal gasification field test. Deuterium oxide was used as the tracer. This report describes the tracer test and the analysis of the data obtained. The analysis indicates that at Hoe Creek the injected steam interacts with a large volume of water as it passes through the underground system. We hypothesize that this water is undergoing continual reflux in the underground system, resulting in a tracer response typical of a well-stirred tank.

  1. EA-1219: Hoe Creek Underground Coal Gasification Test Site Remediation, Campbell County, Wyoming

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts for the proposed Hoe Creek Underground Coal Gasification Test Site Remediation that would be performed at the Hoe Creek site in Campbell County, Wyoming.

  2. Regional groundwater flow and tritium transport modeling and risk assessment of the underground test area, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    None

    1997-10-01T23:59:59.000Z

    The groundwater flow system of the Nevada Test Site and surrounding region was evaluated to estimate the highest potential current and near-term risk to the public and the environment from groundwater contamination downgradient of the underground nuclear testing areas. The highest, or greatest, potential risk is estimated by assuming that several unusually rapid transport pathways as well as public and environmental exposures all occur simultaneously. These conservative assumptions may cause risks to be significantly overestimated. However, such a deliberate, conservative approach ensures that public health and environmental risks are not underestimated and allows prioritization of future work to minimize potential risks. Historical underground nuclear testing activities, particularly detonations near or below the water table, have contaminated groundwater near testing locations with radioactive and nonradioactive constituents. Tritium was selected as the contaminant of primary concern for this phase of the project because it is abundant, highly mobile, and represents the most significant contributor to the potential radiation dose to humans for the short term. It was also assumed that the predicted risk to human health and the environment from tritium exposure would reasonably represent the risk from other, less mobile radionuclides within the same time frame. Other contaminants will be investigated at a later date. Existing and newly collected hydrogeologic data were compiled for a large area of southern Nevada and California, encompassing the Nevada Test Site regional groundwater flow system. These data were used to develop numerical groundwater flow and tritium transport models for use in the prediction of tritium concentrations at hypothetical human and ecological receptor locations for a 200-year time frame. A numerical, steady-state regional groundwater flow model was developed to serve as the basis for the prediction of the movement of tritium from the underground testing areas on a regional scale. The groundwater flow model was used in conjunction with a particle-tracking code to define the pathlines followed by groundwater particles originating from 415 points associated with 253 nuclear test locations. Three of the most rapid pathlines were selected for transport simulations. These pathlines are associated with three nuclear test locations, each representing one of the three largest testing areas. These testing locations are: BOURBON on Yucca Flat, HOUSTON on Central Pahute Mesa, and TYBO on Western Pahute Mesa. One-dimensional stochastic tritium transport simulations were performed for the three pathlines using the Monte Carlo method with Latin hypercube sampling. For the BOURBON and TYBO pathlines, sources of tritium from other tests located along the same pathline were included in the simulations. Sensitivity analyses were also performed on the transport model to evaluate the uncertainties associated with the geologic model, the rates of groundwater flow, the tritium source, and the transport parameters. Tritium concentration predictions were found to be mostly sensitive to the regional geology in controlling the horizontal and vertical position of transport pathways. The simulated concentrations are also sensitive to matrix diffusion, an important mechanism governing the migration of tritium in fractured carbonate and volcanic rocks. Source term concentration uncertainty is most important near the test locations and decreases in importance as the travel distance increases. The uncertainty on groundwater flow rates is as important as that on matrix diffusion at downgradient locations. The risk assessment was performed to provide conservative and bounding estimates of the potential risks to human health and the environment from tritium in groundwater. Risk models were designed by coupling scenario-specific tritium intake with tritium dose models and cancer and genetic risk estimates using the Monte Carlo method. Estimated radiation doses received by individuals from chronic exposure to tritium, and the corre

  3. US Department of Energy DOE Nevada Operations Office, Nevada Test Site: Underground safety and health standards

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    The Nevada Test Site Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada Test Site Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all.

  4. Underground Facility at Nevada National Security Site | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14Russian Nuclear Warheads Arrives in United States and Will

  5. Underground collocation of nuclear power plant reactors and repository to facilitate the post-renaissance expansion of nuclear power

    SciTech Connect (OSTI)

    Myers, Carl W [Los Alamos National Laboratory; Elkins, Ned Z [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    Underground collocation of nuclear power reactors and the nuclear waste management facilities supporting those reactors, termed an underground nuclear park (UNP), appears to have several advantages compared to the conventional approach to siting reactors and waste management facilities. These advantages include the potential to lower reactor capital and operating cost, lower nuclear waste management cost, and increase margins of physical security and safety. Envirorunental impacts related to worker health, facility accidents, waste transportation, and sabotage and terrorism appear to be lower for UNPs compared to the current approach. In-place decommissioning ofUNP reactors appears to have cost, safety, envirorunental and waste disposal advantages. The UNP approach has the potential to lead to greater public acceptance for the deployment of new power reactors. Use of the UNP during the post-nuclear renaissance time frame has the potential to enable a greater expansion of U.S. nuclear power generation than might otherwise result. Technical and economic aspects of the UNP concept need more study to determine the viability of the concept.

  6. Hydrologic Resources Management Program and Underground Test Area Project FY 2006 Progress Report

    SciTech Connect (OSTI)

    Culham, H W; Eaton, G F; Genetti, V; Hu, Q; Kersting, A B; Lindvall, R E; Moran, J E; Blasiyh Nuno, G A; Powell, B A; Rose, T P; Singleton, M J; Williams, R W; Zavarin, M; Zhao, P

    2008-04-08T23:59:59.000Z

    This report describes FY 2006 technical studies conducted by the Chemical Biology and Nuclear Science Division (CBND) at Lawrence Livermore National Laboratory (LLNL) in support of the Hydrologic Resources Management Program (HRMP) and the Underground Test Area Project (UGTA). These programs are administered by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office (NNSA/NSO) through the Defense Programs and Environmental Restoration Divisions, respectively. HRMP-sponsored work is directed toward the responsible management of the natural resources at the Nevada Test Site (NTS), enabling its continued use as a staging area for strategic operations in support of national security. UGTA-funded work emphasizes the development of an integrated set of groundwater flow and contaminant transport models to predict the extent of radionuclide migration from underground nuclear testing areas at the NTS. The report is organized on a topical basis and contains four chapters that highlight technical work products produced by CBND. However, it is important to recognize that most of this work involves collaborative partnerships with the other HRMP and UGTA contract organizations. These groups include the Energy and Environment Directorate at LLNL (LLNL-E&E), Los Alamos National Laboratory (LANL), the Desert Research Institute (DRI), the U.S. Geological Survey (USGS), Stoller-Navarro Joint Venture (SNJV), and National Security Technologies (NSTec). Chapter 1 is a summary of FY 2006 sampling efforts at near-field 'hot' wells at the NTS, and presents new chemical and isotopic data for groundwater samples from four near-field wells. These include PM-2 and U-20n PS 1DDh (CHESHIRE), UE-7ns (BOURBON), and U-19v PS No.1ds (ALMENDRO). Chapter 2 is a summary of the results of chemical and isotopic measurements of groundwater samples from three UGTA environmental monitoring wells. These wells are: ER-12-4 and U12S located in Area 12 on Rainier Mesa and USGS HGH No.2 WW2 located in Yucca Flat. In addition, three springs were sampled White Rock Spring and Captain Jack Spring in Area 12 on Rainier Mesa and Topopah Spring in Area 29. Chapter 3 is a compilation of existing noble gas data that has been reviewed and edited to remove inconsistencies in presentation of total vs. single isotope noble gas values reported in the previous HRMP and UGTA progress reports. Chapter 4 is a summary of the results of batch sorption and desorption experiments performed to determine the distribution coefficients (Kd) of Pu(IV), Np(V), U(VI), Cs and Sr to zeolitized tuff (tuff confining unit, TCU) and carbonate (lower carbonate aquifer, LCA) rocks in synthetic NTS groundwater Chapter 5 is a summary of the results of a series of flow-cell experiments performed to examine Np(V) and Pu(V) sorption to and desorption from goethite. Np and Pu desorption occur at a faster rate and to a greater extent than previously reported. In addition, oxidation changes occurred with the Pu whereby the surface-sorbed Pu(IV) was reoxidized to aqueous Pu(V) during desorption.

  7. The Hanna, Wyoming, underground coal gasification field test series

    SciTech Connect (OSTI)

    Bartke, T.C.; Gunn, R.D.

    1983-01-01T23:59:59.000Z

    Six field tests of in-situ coal gasification have been conducted by the Department of Energy's Laramie Energy Technology Center Near Hanna, Wyoming with typical gasification rates of 100 tons of coal per day for continuous operation of about 30 days. This paper presents an overview of the Hanna field tests.

  8. Identification and Characterization of Hydrogeologic Units at the Nevada Test Site Using Geophysical Logs: Examples from the Underground Test Area Project

    SciTech Connect (OSTI)

    Lance Prothro, Sigmund Drellack, Margaret Townsend

    2009-03-25T23:59:59.000Z

    The diverse and complex geology of the Nevada Test Site region makes for a challenging environment for identifying and characterizing hydrogeologic units penetrated by wells drilled for the U.S. Department of Energy, National Nuclear Security Administration, Underground Test Area (UGTA) Environmental Restoration Sub-Project. Fortunately, UGTA geoscientists have access to large and robust sets of subsurface geologic data, as well as a large historical knowledge base of subsurface geological analyses acquired mainly during the underground nuclear weapons testing program. Of particular importance to the accurate identification and characterization of hydrogeologic units in UGTA boreholes are the data and interpretation principles associated with geophysical well logs. Although most UGTA participants and stakeholders are probably familiar with drill hole data such as drill core and cuttings, they may be less familiar with the use of geophysical logs; this document is meant to serve as a primer on the use of geophysical logs in the UGTA project. Standard geophysical logging tools used in the UGTA project to identify and characterize hydrogeologic units are described, and basic interpretation principles and techniques are explained. Numerous examples of geophysical log data from a variety of hydrogeologic units encountered in UGTA wells are presented to highlight the use and value of geophysical logs in the accurate hydrogeologic characterization of UGTA wells.

  9. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. H. Cox

    2001-06-01T23:59:59.000Z

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots'' from the concrete vault, and the drilling removal of the cement-lined vault sump. Field activities began on November 28, 2000, and ended on December 4, 2000. After verification samples were collected, the vault was repaired with cement. The concrete vault sump, soil excavated beneath the sump, and compactable hot line trash were disposed at the Area 23 Sanitary Landfill. The vault interior was field surveyed following the removal of waste to verify that unrestricted release criteria had been achieved. Since the site is closed by unrestricted release decontamination and verification, post-closure care is not required.

  10. Nuclear Test-Experimental Science: Annual report, fiscal year 1988

    SciTech Connect (OSTI)

    Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

    1988-01-01T23:59:59.000Z

    Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

  11. Rocky Mountain 1: Underground coal gasification test, Hanna, Wyoming. Volume 1. Operations. Summary report

    SciTech Connect (OSTI)

    Not Available

    1989-03-01T23:59:59.000Z

    The Rocky Mountain 1 underground coal gasification (UCG) test was conducted near Hanna, Wyoming during the period January 1986 through March 1988. The report focuses on operations phases that included site selection, facility design, facility construction, well drilling, gasification and environmental monitoring. Two technologies were evaluated as separate modules: the Extended Linked Well (ELW) and the Controlled Retracting Injection Point (CRIP) processes. The test results, along with a discussion of the key test parameters and conclusions of the gasification phase, are provided. A bibliography and schematics are included.

  12. Underground Test Area Fiscal Year 2012 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Farnham, Irene; Marutzky, Sam

    2013-01-01T23:59:59.000Z

    This report is mandated by the Underground Test Area (UGTA) Quality Assurance Project Plan (QAPP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2012. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2012. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, revising the QAPP, and publishing documents. In addition, processes and procedures were developed to address deficiencies identified in the FY 2011 QAPP gap analysis.

  13. Underground Test Area Fiscal Year 2013 Annual Quality Assurance Report Nevada National Security Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Krenzien, Susan; Marutzky, Sam

    2014-01-01T23:59:59.000Z

    This report is required by the Underground Test Area (UGTA) Quality Assurance Plan (QAP) and identifies the UGTA quality assurance (QA) activities for fiscal year (FY) 2013. All UGTA organizations—U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO); Desert Research Institute (DRI); Lawrence Livermore National Laboratory (LLNL); Los Alamos National Laboratory (LANL); Navarro-Intera, LLC (N-I); National Security Technologies, LLC (NSTec); and the U.S. Geological Survey (USGS)—conducted QA activities in FY 2013. The activities included conducting assessments, identifying findings and completing corrective actions, evaluating laboratory performance, and publishing documents. In addition, integrated UGTA required reading and corrective action tracking was instituted.

  14. Closure Report for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    D. S. Tobiason

    2003-07-01T23:59:59.000Z

    This Closure Report (CR) documents the activities undertaken to close Corrective Action Unit (CAU) 262: Area 25 Septic Systems and Underground Discharge Point, in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996. Site closure was performed in accordance with the Nevada Division of Environmental Protection (NDEP)-approved Corrective Action Plan (CAP) for CAU 262 (U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office [NNSA/NV, 2002a]). CAU 262 is located at the Nevada Test Site (NTS) approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada. CAU 262 consists of the following nine Corrective Action Sites (CASs) located in Area 25 of the NTS: CAS 25-02-06, Underground Storage tank CAS 25-04-06, Septic Systems A and B CAS 25-04-07, Septic System CAS 25-05-03, Leachfield CAS 25-05-05, Leachfield CAS 25-05-06, Leachfield CAS 25-05-08, Radioactive Leachfield CAS 25-05-12, Leachfield CAS 25-51-01, Dry Well.

  15. Search for underground openings for in situ test facilities in crystalline rock

    SciTech Connect (OSTI)

    Wollenberg, H.A.; Strisower, B.; Corrigan, D.J.; Graf, A.N.; O'Brien, M.T.; Pratt, H.; Board, M.; Hustrulid, W.

    1980-01-01T23:59:59.000Z

    With a few exceptions, crystalline rocks in this study were limited to plutonic rocks and medium to high-grade metamorphic rocks. Nearly 1700 underground mines, possibly occurring in crystalline rock, were initially identified. Application of criteria resulted in the identification of 60 potential sites. Within this number, 26 mines and 4 civil works were identified as having potential in that they fulfilled the criteria. Thirty other mines may have similar potential. Most of the mines identified are near the contact between a pluton and older sedimentary, volcanic and metamorphic rocks. However, some mines and the civil works are well within plutonic or metamorphic rock masses. Civil works, notably underground galleries associated with pumped storage hydroelectric facilities, are generally located in tectonically stable regions, in relatively homogeneous crystalline rock bodies. A program is recommended which would identify one or more sites where a concordance exists between geologic setting, company amenability, accessibility and facilities to conduct in situ tests in crystalline rock.

  16. Underground Test Area Subproject Phase I Data Analysis Task. Volume VII - Tritium Transport Model Documentation Package

    SciTech Connect (OSTI)

    None

    1996-12-01T23:59:59.000Z

    Volume VII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the tritium transport model documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

  17. Underground Test Area Subproject Phase I Data Analysis Task. Volume VIII - Risk Assessment Documentation Package

    SciTech Connect (OSTI)

    None

    1996-12-01T23:59:59.000Z

    Volume VIII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the risk assessment documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

  18. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository - Volume 3: Appendices

    SciTech Connect (OSTI)

    Taylor, L.L.; Wilson, J.R. (INEEL); Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K. (SNL); Rath, J.S. (New Mexico Engineering Research Institute)

    1998-10-01T23:59:59.000Z

    The United States Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).

  19. Safe testing nuclear rockets economically

    SciTech Connect (OSTI)

    Howe, S. D. (Steven D.); Travis, B. J. (Bryan J.); Zerkle, D. K. (David K.)

    2002-01-01T23:59:59.000Z

    Several studies over the past few decades have recognized the need for advanced propulsion to explore the solar system. As early as the 1960s, Werner Von Braun and others recognized the need for a nuclear rocket for sending humans to Mars. The great distances, the intense radiation levels, and the physiological response to zero-gravity all supported the concept of using a nuclear rocket to decrease mission time. These same needs have been recognized in later studies, especially in the Space Exploration Initiative in 1989. One of the key questions that has arisen in later studies, however, is the ability to test a nuclear rocket engine in the current societal environment. Unlike the RoverMERVA programs in the 1960s, the rocket exhaust can no longer be vented to the open atmosphere. As a consequence, previous studies have examined the feasibility of building a large-scale version of the Nuclear Furnace Scrubber that was demonstrated in 1971. We have investigated an alternative that would deposit the rocket exhaust along with any entrained fission products directly into the ground. The Subsurface Active Filtering of Exhaust, or SAFE, concept would allow variable sized engines to be tested for long times at a modest expense. A system overview, results of preliminary calculations, and cost estimates of proof of concept demonstrations are presented. The results indicate that a nuclear rocket could be tested at the Nevada Test Site for under $20 M.

  20. Excavation of the Partial Seam CRIP underground coal gasification test site

    SciTech Connect (OSTI)

    Cena, R.J.; Britten, J.A.; Thorsness, C.B.

    1987-08-14T23:59:59.000Z

    In the fall of 1983, Lawrence Livermore National Laboratory conducted the Partial Seam CRIP (PSC) underground coal gasification (UCG) field experiment at the Washington Irrigation and Development Company mine near Centralia, Washington. The test, in the subbituminous Big Dirty coal seam, lasted 30 days during which time 1400 cubic meters of coal were consumed from two injection/production well combinations. In the spring of 1986, normal mining activity in the vicinity of the PSC test allowed the opportunity to carefully excavate the experiment and examine the post-burn cavities. The mining operation dug out the front and back half of the test area and most of the overburden above the UCG cavities, leaving approximately 23,000 cubic meters of earth containing the main portion of the test area undisturbed. Under direction of the Wyoming Research Institute (WRI), this remaining earth was carefully excavated, in slices perpendicular to the original injection/production line, using small earthmoving equipment to uncover and sample the final burn cavities. Preliminary results of the excavation were presented by WRI at the 12th Underground Coal Conversion Symposium. We present additional results and conclusions based on all of the information obtained. Topics covered include: comparison to material balance and thermal instrumentation data, analysis and composition of samples taken from the cavity and general cavity shape and characteristics in comparison with mechanistic models of cavity growth. 10 refs., 10 figs., 1 tab.

  1. Hanna, Wyoming underground coal gasification data base. Volume 2. The Hanna I field test

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project, and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation of all the data for the tests in Volumes 2 through 6. Based on the recommendations of A.D. Little, Inc. in a 1971 report prepared for the US Bureau of Mines, the Hanna I test represented the first field test in reestablishing a field program by the US Bureau of Mines. The test was directed toward comparing results from a thick subbitiminous coal seam with those obtained during the field test series conducted at Gorgas, AL, in the 1940's and 1950's. Hanna I was conducted from March 1973 through February 1974. This report covers: (1) site selection and characteristics; (2) test objectives; (3) facility description; (4) pre-operation tests; (5) test operations summary; and (6) post-test activity. 9 refs., 10 figs., 4 tabs.

  2. Hanna, Wyoming underground coal gasification data base. Volume 3. The Hanna II, Phase I field test

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project, and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation of all the data for the tests in Volumes 2 through 6. Hanna II, Phase I was conducted during the spring and summer of 1975, at a site about 700 feet up dip (to the southwest) of the Hanna I test. The test was conducted in two stages - Phase IA and IB. Phase IA consisted of linking and gasification operations between Wells 1 and 3 and Phase IB of linking from the 1-3 gasification zone to Well 2, followed by a short period of gasification from Well 2 to Well 3 over a broad range of air injection rates, in order to determine system turndown capabilities and response times. This report covers: (1) site selection and characteristics; (2) test objectives; (3) facilities description; (4) pre-operational testing; (5) test operations summary; and (6) post-test activity. 7 refs., 11 figs., 8 tabs.

  3. Hanna, Wyoming underground coal gasification data base. Volume 5. Hanna III field test research report

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation of all the data for the tests in Volumes 2 through 6. Hanna III was conducted during the spring and summer of 1977. The test involved only two process wells but also had twelve water monitoring wells, eight in the Hanna No. 1 coal seam and four in an aquifer above the coal seam. The test was designed to obtain information regarding the effects of the process on groundwater within the target seam and the overlying aquifer. The site for Hanna III had a low productivity aquifer above the Hanna No. 1 seam. The wells within the seam and the overlying aquifer were placed in such a manner that maximum information on groundwater flow and quality could be obtained. This report covers: (1) site selection and characterization; (2) test objectives; (3) facilities description; (4) pre-operation tests; (5) test operations summary; and (6) post-test activity. 4 refs., 11 figs., 5 tabs.

  4. Underground infrastructure damage for a Chicago scenario

    SciTech Connect (OSTI)

    Dey, Thomas N [Los Alamos National Laboratory; Bos, Rabdall J [Los Alamos National Laboratory

    2011-01-25T23:59:59.000Z

    Estimating effects due to an urban IND (improvised nuclear device) on underground structures and underground utilities is a challenging task. Nuclear effects tests performed at the Nevada Test Site (NTS) during the era of nuclear weapons testing provides much information on how underground military structures respond. Transferring this knowledge to answer questions about the urban civilian environment is needed to help plan responses to IND scenarios. Explosions just above the ground surface can only couple a small fraction of the blast energy into an underground shock. The various forms of nuclear radiation have limited penetration into the ground. While the shock transmitted into the ground carries only a small fraction of the blast energy, peak stresses are generally higher and peak ground displacement is lower than in the air blast. While underground military structures are often designed to resist stresses substantially higher than due to the overlying rocks and soils (overburden), civilian structures such as subways and tunnels would generally only need to resist overburden conditions with a suitable safety factor. Just as we expect the buildings themselves to channel and shield air blast above ground, basements and other underground openings as well as changes of geology will channel and shield the underground shock wave. While a weaker shock is expected in an urban environment, small displacements on very close-by faults, and more likely, soils being displaced past building foundations where utility lines enter could readily damaged or disable these services. Immediately near an explosion, the blast can 'liquefy' a saturated soil creating a quicksand-like condition for a period of time. We extrapolate the nuclear effects experience to a Chicago-based scenario. We consider the TARP (Tunnel and Reservoir Project) and subway system and the underground lifeline (electric, gas, water, etc) system and provide guidance for planning this scenario.

  5. Preliminary studies of tunnel interface response modeling using test data from underground storage facilities.

    SciTech Connect (OSTI)

    Sobolik, Steven Ronald; Bartel, Lewis Clark

    2010-11-01T23:59:59.000Z

    In attempting to detect and map out underground facilities, whether they be large-scale hardened deeply-buried targets (HDBT's) or small-scale tunnels for clandestine border or perimeter crossing, seismic imaging using reflections from the tunnel interface has been seen as one of the better ways to both detect and delineate tunnels from the surface. The large seismic impedance contrast at the tunnel/rock boundary should provide a strong, distinguishable seismic response, but in practice, such strong indicators are often lacking. One explanation for the lack of a good seismic reflection at such a strong contrast boundary is that the damage caused by the tunneling itself creates a zone of altered seismic properties that significantly changes the nature of this boundary. This report examines existing geomechanical data that define the extent of an excavation damage zone around underground tunnels, and the potential impact on rock properties such as P-wave and S-wave velocities. The data presented from this report are associated with sites used for the development of underground repositories for the disposal of radioactive waste; these sites have been excavated in volcanic tuff (Yucca Mountain) and granite (HRL in Sweden, URL in Canada). Using the data from Yucca Mountain, a numerical simulation effort was undertaken to evaluate the effects of the damage zone on seismic responses. Calculations were performed using the parallelized version of the time-domain finitedifference seismic wave propagation code developed in the Geophysics Department at Sandia National Laboratories. From these numerical simulations, the damage zone does not have a significant effect upon the tunnel response, either for a purely elastic case or an anelastic case. However, what was discovered is that the largest responses are not true reflections, but rather reradiated Stoneley waves generated as the air/earth interface of the tunnel. Because of this, data processed in the usual way may not correctly image the tunnel. This report represents a preliminary step in the development of a methodology to convert numerical predictions of rock properties to an estimation of the extent of rock damage around an underground facility and its corresponding seismic velocity, and the corresponding application to design a testing methodology for tunnel detection.

  6. Groundwater restoration field test at the Hoe Creek underground coal gasification site

    SciTech Connect (OSTI)

    Nordin, J.S.; Barrash, W.; Nolan, B.T.

    1988-02-01T23:59:59.000Z

    Three underground coal gasification burns were conducted at the Hoe Creek Site in the Powder River Basin. Some contaminants were released in the groundwater. The Department of Energy (DOE) analyzed the water from a network of wells. Two million gallons of groundwater were pumped from wells adjacent to the Hoe Creek II underground coal gasification cavity, passed through filters and carbon adsorbers, and reinjected into the cavity. Phenol was the target compound of the water treatment system. The phenol concentration pumped from well WS-10 decreased from 974 parts per billion (ppB) when treatment began on July 2, 1987, to about 200 ppB when treatment ceased on August 29, 1987. Phenol concentrations pumped from well WS-22 fluctuated during the tests, but they decreased to the 150 to 200 ppB range by the time treatment was terminated. The phenol concentration of treated water reinjected into the Hoe Creek II cavity was below detectable limits (less than 20 ppB). Pumping rates were about 18 gallons per minute (gpm) from well WS-10 and 6 to 8 gpm from well WS-22. Hoe Creek is located approximately 20 miles southwest of Gillette, Wyoming. 12 refs., 5 figs., 8 tabs.

  7. Nuclear explosives testing readiness evaluation

    SciTech Connect (OSTI)

    Valk, T.C.

    1993-09-01T23:59:59.000Z

    This readiness evaluation considers hole selection and characterization, verification, containment issues, nuclear explosive safety studies, test authorities, event operations planning, canister-rack preparation, site preparation, diagnostic equipment setup, device assembly facilities and processes, device delivery and insertion, emplacement, stemming, control room activities, readiness briefing, arming and firing, test execution, emergency response and reentry, and post event analysis to include device diagnostics, nuclear chemistry, and containment. This survey concludes that the LLNL program and its supporting contractors could execute an event within six months of notification, and a second event within the following six months, given the NET group`s evaluation and the following three restraints: (1) FY94 (and subsequent year) funding is essentially constant with FY93, (2) Preliminary work for the initial event is completed to the historical sic months status, (3) Critical personnel, currently working in dual use technologies, would be recallable as needed.

  8. Radioactivity pollution and protection of underground waters within the location of nuclear power plants in Jaslovske Bohunice

    SciTech Connect (OSTI)

    Plsko, J.; Kostolansky, M. [EKOSUR, Trnava (Slovakia); Polak, R. [HYDROPOL, Bratislava (Slovakia)

    1993-12-31T23:59:59.000Z

    As a result of research conducted at the Nuclear Power Plant (NPP) A-1 in connection with the decommissioning of the A-1 reactor, tritium contamination has been found in the ground water. A program has been undertaken for the monitoring and protection of underground waters, both onsite and offsite. The paper describes the present level of knowledge on the actual hydrogeological and radiological status of the area.

  9. Geological evaluation of the proposed Rocky Mountain 1 underground coal gasification test site, Hanna, Wyoming

    SciTech Connect (OSTI)

    Oliver, R.L.

    1987-02-01T23:59:59.000Z

    To characterize the proposed Rocky Mountain 1 underground coal gasification test site near Hanna, Wyoming, 30 drill and/or core holes were completed and downhole geophysically logged during the summer of 1986. Core testing was conducted to identify coal quality and predict behavior during gasification. Data were then interpreted to provide information on process parameters and restoration to be used by process and environmental engineers. The coal seam at the Rocky Mountain 1 site dips to the northeast at 7/sup 0/ and shows only minor folding of strata. A fault with 30 feet of stratigraphic displacement is located approximately 300 feet northeast of the northern boundary of the proposed burn area. From core and outcrop observations, tectonic fracturing is predicted to be minor, although local areas of fracturing may exist. Overburden stratigraphy consists of interbedded sandstone, siltstone, and shale with minor coal. The Hanna No. 1 coal (target of the experiments) is approximately 30 feet thick. It contains an upper bench approximately 3 to 4 feet thick of lower quality (higher ash, lower Btu), a central bench about 20 feet thick of higher quality (lower ash, higher Btu), and a lower bench approximately 3 to 4 feet thick also of lower quality. The benches are separated by shaley zones approximately 1 to 2 feet thick, which are correlative across the site. Another shaley zone exists near the base of the central bench. The coal varies vertically and somewhat laterally across the site but averages at a high volatile C bituminous rank. Average-as-received proximate analysis values for the coal are 8.8 wt % moisture, 27.3 wt % ash, 32.0 wt % volatile matter, 31.9 wt % fixed carbon, and approximately 8600 Btu/lb heating value. Average-as-received sulfur content is 0.7 wt %. Site characteristics are very amenable to underground coal gasification, and no hindrances to the test due to geologic conditions are expected. 9 refs., 21 figs., 6 tabs.

  10. The Hanna and Hoe Creek underground coal gasification test sites: Status report, (June 1986-June 1987)

    SciTech Connect (OSTI)

    Berdan, G.L.; Nolan, B.T.; Barteaux, W.L.; Barrash, W.

    1987-06-01T23:59:59.000Z

    To comply with a cooperative agreement with the U.S. Department of Energy (DOE), the Western Research Institute (WRI) is required to submit an annual report summarizing the status of environmentally related work performed by WRI at the Hanna and Hoe Creek underground coal gasification (UCG) sites. The following is a summary of work performed at these two sites from June 1986 to June 1987. Several tasks for restoring the water quailty at Hoe Creek were: (1) groundwater treatment demonstration (1986); (2) bench-scale carbon adsorption experiments (1987); (3) design of the scaled-up treatment system (1987); (4) well-pumping test (1987). A summary of the results of each task is presented. 6 refs., 8 figs., 4 tabs.

  11. Environmental assessment for the Hoe Creek underground, Coal Gasification Test Site Remediation, Campbell County, Wyoming

    SciTech Connect (OSTI)

    NONE

    1997-10-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has prepared this EA to assess environmental and human health Issues and to determine potential impacts associated with the proposed Hoe Creek Underground Coal Gasification Test Site Remediation that would be performed at the Hoe Creek site in Campbell County, Wyoming. The Hoe Creek site is located south-southwest of the town of Gillette, Wyoming, and encompasses 71 acres of public land under the stewardship of the Bureau of Land Management. The proposed action identified in the EA is for the DOE to perform air sparging with bioremediation at the Hoe Creek site to remove contaminants resulting from underground coal gasification (UCG) experiments performed there by the DOE in the late 1970s. The proposed action would involve drilling additional wells at two of the UCG test sites to apply oxygen or hydrogen peroxide to the subsurface to volatilize benzene dissolved in the groundwater and enhance bioremediation of non-aqueous phase liquids present in the subsurface. Other alternatives considered are site excavation to remove contaminants, continuation of the annual pump and treat actions that have been used at the site over the last ten years to limit contaminant migration, and the no action alternative. Issues examined in detail in the EA are air quality, geology, human health and safety, noise, soils, solid and hazardous waste, threatened and endangered species, vegetation, water resources, and wildlife. Details of mitigative measures that could be used to limit any detrimental effects resulting from the proposed action or any of the alternatives are discussed, and information on anticipated effects identified by other government agencies is provided.

  12. Underground tank vitrification: A pilot-scale in situ vitrification test of a tank containing a simulated mixed waste sludge

    SciTech Connect (OSTI)

    Thompson, L.E.; Powell, T.D.; Tixier, J.S.; Miller, M.C. [Pacific Northwest Lab., Richland, WA (United States); Owczarski, P.C. [Science Applications International Corp., Richland, WA (United States)

    1993-09-01T23:59:59.000Z

    This report documents research on sludge vitrification. The first pilot scale in-situ vitrification test of a simulated underground tank was successfully completed by researchers at Pacific Northwest Laboratory. The vitrification process effectively immobilized the vast majority of radionuclides simulants and toxic metals were retained in the melt and uniformly distributed throughout the monolith.

  13. Role of hydrogeology in Rocky Mountain 1 underground coal gasification test, Hanna basin, Wyoming

    SciTech Connect (OSTI)

    Daly, D.J.; Schmit, C.R.; Beaver, F.W.; Evans, J.M. (North Dakota Mining and Mineral Resources Research Institute, Grand Forks (USA))

    1989-09-01T23:59:59.000Z

    Experience has shown that the designs and implementation of Underground Coal Gasification (UCG) operations that are technically sound and environmentally safe require a thorough understanding of the hydrogeology of the UCG site, complemented by an understanding of the potential interactions between the elements of the hydrogeologic system and UCG process. This is significant because UCG is conducted in the saturated zone, consumes large volumes of ground water, and has the potential to adversely affect ground water quality and flow. The textural, mineralogical, chemical, and structural character of the geologic materials constituting the UCG reactor, as well as the occurrence, flow, and quality of fluids moving through that three-dimensional matrix of geologic materials, must be understood. The US Department of Energy and an industry consortium led by the Gas Research Institute recently conducted the Rocky Mountain 1 Test in the Hanna basin of Wyoming. For this test, the hydrogeologic aspects of the site were characterized to an extent unprecedented in UCG testing. This information was then used to develop and evaluate operating strategies intended to prevent or minimize contamination. Such strategies included gasifying at less than hydrostatic pressure to enhance ground water flow toward the gasification modules and to restrict contamination to the module area. Hydrogeologic information also allowed a more complete evaluation of process-setting interactions. For example, a substantial and widespread drop in elevation heat noted for the ground water in the target coal emphasized the importance of an adequate water supply for UCG, particularly in a long-term commercial operation.

  14. Lawrence Livermore National Laboratory underground coal gasification data base. [US DOE-supported field tests; data

    SciTech Connect (OSTI)

    Cena, R. J.; Thorsness, C. B.

    1981-08-21T23:59:59.000Z

    The Department of Energy has sponsored a number of field projects to determine the feasibility of converting the nation's vast coal reserves into a clean efficient energy source via underground coal gasification (UCG). Due to these tests, a significant data base of process information has developed covering a range of coal seams (flat subbituminous, deep flat bituminous and steeply dipping subbituminous) and processing techniques. A summary of all DOE-sponsored tests to data is shown. The development of UCG on a commercial scale requires involvement from both the public and private sectors. However, without detailed process information, accurate assessments of the commercial viability of UCG cannot be determined. To help overcome this problem the DOE has directed the Lawrence Livermore National Laboratory (LLNL) to develop a UCG data base containing raw and reduced process data from all DOE-sponsored field tests. It is our intent to make the data base available upon request to interested parties, to help them assess the true potential of UCG.

  15. Nuclear waste repository transparency technology test bed demonstrations at WIPP

    SciTech Connect (OSTI)

    BETSILL,J. DAVID; ELKINS,NED Z.; WU,CHUAN-FU; MEWHINNEY,JAMES D.; AAMODT,PAUL

    2000-01-27T23:59:59.000Z

    Secretary of Energy, Bill Richardson, has stated that one of the nuclear waste legacy issues is ``The challenge of managing the fuel cycle's back end and assuring the safe use of nuclear power.'' Waste management (i.e., the back end) is a domestic and international issue that must be addressed. A key tool in gaining acceptance of nuclear waste repository technologies is transparency. Transparency provides information to outside parties for independent assessment of safety, security, and legitimate use of materials. Transparency is a combination of technologies and processes that apply to all elements of the development, operation, and closure of a repository system. A test bed for nuclear repository transparency technologies has been proposed to develop a broad-based set of concepts and strategies for transparency monitoring of nuclear materials at the back end of the fuel/weapons cycle. WIPP is the world's first complete geologic repository system for nuclear materials at the back end of the cycle. While it is understood that WIPP does not currently require this type of transparency, this repository has been proposed as realistic demonstration site to generate and test ideas, methods, and technologies about what transparency may entail at the back end of the nuclear materials cycle, and which could be applicable to other international repository developments. An integrated set of transparency demonstrations was developed and deployed during the summer, and fall of 1999 as a proof-of-concept of the repository transparency technology concept. These demonstrations also provided valuable experience and insight into the implementation of future transparency technology development and application. These demonstrations included: Container Monitoring Rocky Flats to WIPP; Underground Container Monitoring; Real-Time Radiation and Environmental Monitoring; Integrated level of confidence in the system and information provided. As the world's only operating deep geologic repository, the Waste Isolation Pilot Plant (WIPP) offers a unique opportunity to serve as an international cooperative test bed for developing and demonstrating technologies and processes in a fully operational repository system setting. To address the substantial national security implications for the US resulting from the lack of integrated, transparent management and disposition of nuclear materials at the back-end of the nuclear fuel and weapons cycles, it is proposed that WIPP be used as a test bed to develop and demonstrate technologies that will enable the transparent and proliferation-resistant geologic isolation of nuclear materials. The objectives of this initiative are to: (1) enhance public confidence in safe, secure geologic isolation of nuclear materials; (2) develop, test, and demonstrate transparency measures and technologies for the back-end of nuclear fuel cycle; and (3) foster international collaborations leading to workable, effective, globally-accepted standards for the transparent monitoring of geological repositories for nuclear materials. Test-bed activities include: development and testing of monitoring measures and technologies; international demonstration experiments; transparency workshops; visiting scientist exchanges; and educational outreach. These activities are proposed to be managed by the Department of Energy/Carlsbad Area Office (DOE/CAO) as part of The Center for Applied Repository and Underground Studies (CARUS).

  16. Comprehensive baseline environmental audit of former underground test areas in Colorado, Nevada, and New Mexico

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    This report documents the results of the Comprehensive Baseline Environmental Audit of Former Underground Test Areas (FUTAS) in the States of Colorado, Nevada, and New Mexico. DOE and contractor systems for management of environmental protection activities on the Nevada Test Site (NTS) were not within the scope of the audit. The audit was conducted May 16-May 26, 1994, by the Office of Environmental Audit (EH-24). DOE 5482.1 B, {open_quotes}Environment, Safety, and Health Appraisal Program{close_quotes}, establishes the mission of EH-24, which is to provide comprehensive, independent oversight of Department-wide environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is to enhance environmental protection and minimize risk to public health and the environment. EH-24 accomplishes its mission using systematic and periodic evaluations of DOE`s environmental programs within line organizations and supplemental activities that strengthen self-assessment and oversight functions within program, field, and contractor organizations. These evaluations function as a vehicle through which the Secretary and program managers are apprised of the status and vulnerabilities of Departmental environmental activities and environmental management systems. Several types of evaluations are conducted, including: (1) comprehensive baseline environmental audits; (2) routine environmental audits; (3) environmental management assessments; and (4) special issue reviews.

  17. Nuclear Celebrations

    E-Print Network [OSTI]

    Hacker, Randi; Tsutsui, William

    2006-11-01T23:59:59.000Z

    Broadcast Transcript: The North Korean situation is frightening for many reasons but none, perhaps, more eerily disturbing than images of North Koreans celebrating in brightly colored costumes just days after the nation's underground nuclear test...

  18. A new era of nuclear test verification

    SciTech Connect (OSTI)

    Auer, Matthias; Prior, Mark K.

    2014-09-01T23:59:59.000Z

    The global network of sensors commissioned to monitor compliance with the Comprehensive Nuclear-Test-Ban Treaty has proven capable of that task and more.

  19. Safety aspects of ground testing for large nuclear rockets

    SciTech Connect (OSTI)

    Goldman, M.I.

    1988-02-01T23:59:59.000Z

    Present nuclear rocket reactors under test in Nevada are operated at nominal power levels of 1000 Mw. It does not seem unreasonable in the future to anticipate reactors with power levels in the range up to 5,000 Mw for space applications. It has been shown that the normal testing of large nuclear rocket engines at NRDS could impose some restrictions on the fuel performance which would not otherwise be required by space flight operation. The only apparent alternative would require a capability for decontaminating effluent gases prior to release to the atmosphere. In addition to the source restrictions, tests will almost certainly be controlled by wind and atmospheric stability conditions, and the requirements for monitoring and control of off-site exposures will be much more stringent than those presently in force. An analysis of maximum accidents indicates that projections of present credible occurrences cannot be tolerated in larger engine tests. The apparent alternatives to a significant (order of magnitude or better) reduction in credible accident consequences, are the establishment of an underground test facility, a facility in an area equivalent to the Pacific weapons proving ground, or in space.

  20. Hanna, Wyoming underground coal gasification data base. Volume 6. Hanna IVA and IVB field test research report

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation of all the data for the tests in Volumes 2 through 6. The reports in this series include: The Hanna IV test was designed as the first underground coal gasification test using commercial well spacings of 100 and 150 feet between well pairs in a linear 3-well pattern. The test was initiated in late 1977 and completed in late 1979. This long duration was due to unfavorable geologic conditions (faulting) which could not be successfully overcome resulting in the test being split into Hanna IVA and Hanna IVB with about one year between the conduct of each. This report covers: (1) specific site selection and characteristics; (2) test objectives; (3) facility description; (4) pre-operation tests; (5) test operations summary; and (6) post-test activity. 5 refs., 19 figs., 13 tabs.

  1. Rocky mountain 1: Underground coal-gasification test, Hanna, Wyoming. Summary report, Volume 1. Appendix. Final report

    SciTech Connect (OSTI)

    Vardaman, M.H.

    1989-02-01T23:59:59.000Z

    The Rocky Mountain 1 underground coal gasification test was conducted near Hanna, Wyoming during the period January 1986 through March 1988. These appendixes include information supporting Volume I as well as complete data for certain aspects of the gasification phase. These aspects include daily operations reports, raw and corrected process data, thermocouple and Time Domain Reflectometer results, and monitoring well pressure and level data obtained during the gasification phase. Piping and instrumentation diagrams and supplemental informations on the data acquisition system are included.

  2. Fehner and Gosling, Atmospheric Nuclear Weapons Testing, 1951...

    Energy Savers [EERE]

    Atmospheric Nuclear Weapons Testing, 1951-1963. Battlefield of the Cold War: The Nevada Test Site, Volume I Fehner and Gosling, Atmospheric Nuclear Weapons Testing, 1951-1963....

  3. Transferability of Data Related to the Underground Test Area Project, Nevada Test Site, Nye County, Nevada: Revision 0

    SciTech Connect (OSTI)

    Stoller-Navarro Joint Venture

    2004-06-24T23:59:59.000Z

    This document is the collaborative effort of the members of an ad hoc subcommittee of the Underground Test Area (UGTA) Technical Working Group (TWG). The UGTA Project relies on data from a variety of sources; therefore, a process is needed to identify relevant factors for determining whether material-property data collected from other areas can be used to support groundwater flow, radionuclide transport, and other models within a Corrective Action Unit (CAU), and for documenting the data transfer decision and process. This document describes the overall data transfer process. Separate Parameter Descriptions will be prepared that provide information for selected specific parameters as determined by the U.S. Department of Energy (DOE) UGTA Project Manager. This document and its accompanying appendices do not provide the specific criteria to be used for transfer of data for specific uses. Rather, the criteria will be established by separate parameter-specific and model-specific Data Transfer Protocols. The CAU Data Documentation Packages and data analysis reports will apply the protocols and provide or reference a document with the data transfer evaluations and decisions.

  4. Underground Test Area Subproject Phase I Data Analysis Task. Volume V - Transport Parameter and Source Term Data Documentation Package

    SciTech Connect (OSTI)

    None

    1996-12-01T23:59:59.000Z

    Volume V of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the transport parameter and source term data. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

  5. Corrective Action Decision Document for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    1999-12-23T23:59:59.000Z

    This corrective action decision document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, under the Federal Facility Agreement and Consent Order. Located on the Nevada Test Site (NTS), CAU 135 consists of three Corrective Action Sites (CASs): 25-02-01, Underground Storage Tanks, referred to as the Engine, Maintenance, Assembly, and Disassembly Waste Holdup Tanks and Vault; 25-02-03, Underground Electrical Vault, referred to as the Deluge Valve Pit at the Test Cell A Facility; and 25-02-10, Underground Storage Tank, referred to as the former location of an aboveground storage tank for demineralized water at the Test Cell A Facility. Two of these CASs (25-02-03 and 25-02-10) were originally considered as underground storage tanks, but were found to be misidentified. Further, radio logical surveys conducted by Bechtel Nevada in January 1999 found no radiological contamination detected above background levels for these two sites; therefore, the closure report for CAU 135 will recommend no further action at these two sites. A corrective action investigation for the one remaining CAS (25-02-01) was conducted in June 1999, and analytes detected during this investigation were evaluated against preliminary action levels. It was determined that contaminants of potential concern included polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Two corrective action objectives were identified for this CAS (i.e., prevention and mitigation of human exposure to sediments and surrounding areas), and subsequently two CAAs developed for consideration based on a review of existing data, future use, and current operations at the NTS. These CAAs were: Alternative 1 - No Further Action, and Alternative 2 - Unrestricted Release Decontamination and Verification Survey. Alternative 2 was chosen as the preferred CAA, after evaluation of technical merit which focused on performance, reliability, feasibility, and safety. This alternative was judged to meet all applicable state and federal regulations for closure of the site and reduces the potential future exposure pathways to the contaminated surfaces at this site.

  6. Final Report - Hydraulic Conductivity with Depth for Underground Test Area (UGTA) Wells

    SciTech Connect (OSTI)

    P. Oberlander; D. McGraw; C. Russell

    2007-10-31T23:59:59.000Z

    Hydraulic conductivity with depth has been calculated for Underground Test Area (UGTA) wells in volcanic tuff and carbonate rock. The following wells in volcanic tuff are evaluated: ER-EC-1, ER-EC-2a, ER-EC-4, ER-EC-5, ER-5-4#2, ER-EC-6, ER-EC-7, and ER-EC-8. The following wells in carbonate rock are evaluated: ER-7-1, ER-6-1, ER-6-1#2, and ER-12-3. There are a sufficient number of wells in volcanic tuff and carbonate rock to associate the conductivity values with the specific hydrogeologic characteristics such as the stratigraphic unit, hydrostratigraphic unit, hydrogeologic unit, lithologic modifier, and alteration modifier used to describe the hydrogeologic setting. Associating hydraulic conductivity with hydrogeologic characteristics allows an evaluation of the data range and the statistical distribution of values. These results are relevant to how these units are considered in conceptual models and represented in groundwater models. The wells in volcanic tuff illustrate a wide range of data values and data distributions when associated with specific hydrogeologic characteristics. Hydraulic conductivity data within a hydrogeologic characteristic can display normal distributions, lognormal distributions, semi-uniform distribution, or no identifiable distribution. There can be multiple types of distributions within a hydrogeologic characteristic such as a single stratigraphic unit. This finding has implications for assigning summary hydrogeologic characteristics to hydrostratigraphic and hydrogeologic units. The results presented herein are specific to the hydrogeologic characteristic and to the wells used to describe hydraulic conductivity. The wells in carbonate rock are associated with a fewer number of hydrogeologic characteristics. That is, UGTA wells constructed in carbonate rock have tended to be in similar hydrogeologic materials, and show a wide range in hydraulic conductivity values and data distributions. Associations of hydraulic conductivity and hydrogeologic characteristics are graphically presented even when there are only a few data. This approach benchmarks what is currently known about the association of depth-specific hydraulic conductivity and hydrogeologic characteristics.

  7. External Peer Review Team Report Underground Testing Area Subproject for Frenchman Flat, Revision 1

    SciTech Connect (OSTI)

    Sam Marutzky

    2010-09-01T23:59:59.000Z

    An external peer review was conducted to review the groundwater models used in the corrective action investigation stage of the Underground Test Area (UGTA) subproject to forecast zones of potential contamination in 1,000 years for the Frenchman Flat area. The goal of the external peer review was to provide technical evaluation of the studies and to assist in assessing the readiness of the UGTA subproject to progress to monitoring activities for further model evaluation. The external peer review team consisted of six independent technical experts with expertise in geology, hydrogeology,'''groundwater modeling, and radiochemistry. The peer review team was tasked with addressing the following questions: 1. Are the modeling approaches, assumptions, and model results for Frenchman Flat consistent with the use of modeling studies as a decision tool for resolution of environmental and regulatory requirements? 2. Do the modeling results adequately account for uncertainty in models of flow and transport in the Frenchman Flat hydrological setting? a. Are the models of sufficient scale/resolution to adequately predict contaminant transport in the Frenchman Flat setting? b. Have all key processes been included in the model? c. Are the methods used to forecast contaminant boundaries from the transport modeling studies reasonable and appropriate? d. Are the assessments of uncertainty technically sound and consistent with state-of-the-art approaches currently used in the hydrological sciences? 3. Are the datasets and modeling results adequate for a transition to Corrective Action Unit monitoring studies—the next stage in the UGTA strategy for Frenchman Flat? The peer review team is of the opinion that, with some limitations, the modeling approaches, assumptions, and model results are consistent with the use of modeling studies for resolution of environmental and regulatory requirements. The peer review team further finds that the modeling studies have accounted for uncertainty in models of flow and transport in the Frenchman Flat except for a few deficiencies described in the report. Finally, the peer review team concludes that the UGTA subproject has explored a wide range of variations in assumptions, methods, and data, and should proceed to the next stage with an emphasis on monitoring studies. The corrective action strategy, as described in the Federal Facility Agreement and Consent Order, states that the groundwater flow and transport models for each corrective action unit will consider, at a minimum, the following: • Alternative hydrostratigraphic framework models of the modeling domain. • Uncertainty in the radiological and hydrological source terms. • Alternative models of recharge. • Alternative boundary conditions and groundwater flows. • Multiple permissive sets of calibrated flow models. • Probabilistic simulations of transport using plausible sets of alternative framework and recharge models, and boundary and groundwater flows from calibrated flow models. • Ensembles of forecasts of contaminant boundaries. • Sensitivity and uncertainty analyses of model outputs. The peer review team finds that these minimum requirements have been met. While the groundwater modeling and uncertainty analyses have been quite detailed, the peer review team has identified several modeling-related issues that should be addressed in the next phase of the corrective action activities: • Evaluating and using water-level gradients from the pilot wells at the Area 5 Radioactive Waste Management Site in model calibration. • Re-evaluating the use of geochemical age-dating data to constrain model calibrations. • Developing water budgets for the alluvial and upper volcanic aquifer systems in Frenchman Flat. • Considering modeling approaches in which calculated groundwater flow directions near the water table are not predetermined by model boundary conditions and areas of recharge, all of which are very uncertain. • Evaluating local-scale variations in hydraulic conductivity on the calculated contaminant boundaries. • Evaluat

  8. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 2: Methodology and Results

    SciTech Connect (OSTI)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.C.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-10-01T23:59:59.000Z

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3).

  9. A thousand suns : political motivations for nuclear weapons testing

    E-Print Network [OSTI]

    Raas, Whitney

    2006-01-01T23:59:59.000Z

    Nuclear weapon testing is the final step in the nuclear development process, an announcement of ability and strength. The consequences of a nuclear test are far from easy to bear, however: economic sanctions can be crippling ...

  10. Results of the groundwater restoration project, Hanna Underground Coal Gasification Test Site, Wyoming: Topical report

    SciTech Connect (OSTI)

    Oliver, R.L.

    1988-01-01T23:59:59.000Z

    Underground coal gasification (UCG) experiments conducted during the 1970s at the Department of Energy (DOE) site near Hanna, Wyoming, formed six underground cavities in the Hanna No. 1 coal seam, an aquifer of low permeability. When the first Hanna UCG experiment began in March 1973, researchers had little information about what effects the geologic or hydrologic characteristics of the area might have on the UCG process; likewise, the effects of UCG on the environment were unknown. Since the UCG experiments were completed, dilute concentrations of pyrolysis products and leachates have been detected in groundwater monitoring wells in and near some of the six cavities. Three primary UCG indicator constituents have been measured at elevated concentrations: phenols, TDS, and sulfate. The Hanna III cavity water exceeded the DOE target level for TDS and sulfate, and the Hanna I cavity water exceeded the DOE target level for phenols. The indicated phenols contamination, however, was in groundwater sampled from a well which was previously used as a production well during the experiment. Water pumped during the restoration project and a new well located approximately 10 ft from the old production well was sampled and no elevated phenols concentration was detected. Therefore, the restoration performed on the Hanna I cavity water was not necessary. The restoration was performed, however, because these indications were not available until during the restoration. Locally, various other constituents exceed DOE target levels, but concentrations are very near target levels and are well within livestock use limits. 2 refs., 7 figs., 5 tabs.

  11. Last U.S. Underground Nuclear Test Conducted | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.gov OfficeAdministrationSecurityimpacts

  12. Underground Storage Tanks (West Virginia)

    Broader source: Energy.gov [DOE]

    This rule governs the construction, installation, upgrading, use, maintenance, testing, and closure of underground storage tanks, including certification requirements for individuals who install,...

  13. Hanna, Wyoming underground coal gasification data base. Volume 4. Hanna II, Phases II and III field test research report

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation of all the data for the tests in Volumes 2 through 6. Hanna II, Phases II and III, were conducted during the winter of 1975 and the summer of 1976. The two phases refer to linking and gasification operations conducted between two adjacent well pairs as shown in Figure 1 with Phase II denoting operations between Wells 5 and 6 and Phase III operations between Wells 7 and 8. All of the other wells shown were instrumentation wells. Wells 7 and 8 were linked in November and December 1975. This report covers: (1) specific site selection and characteristics; (2) test objectives; (3) facilities description; (4) pre-operation tests; (5) test operations summary; and (6) post-test activity. 16 refs., 21 figs., 17 tabs.

  14. Underground coal gasification data base. [Information on 14 US DOE sponsored tests; also available on computer tapes

    SciTech Connect (OSTI)

    Cena, R.J.; Thorsness, C.B.; Ott, L.L.

    1982-11-24T23:59:59.000Z

    The Lawrence Livermore National Laboratory has developed a data base containing results from fourteen DOE-sponsored underground coal gasification (UCG) field tests. These tests include three performed by LLNL near Gillette, Wyoming at the Hoe Creek site, eight performed by LETC at a site near Hanna, Wyoming, two by GULF near Rawlings, Wyoming, and one performed by METC near Princetown, West Virginia. All tests were done in flat lying coal seams except the Rawlings tests, which utilized a steeply dipping seam. The report presents process parameters and the results of material and energy balances for each test in a variety of forms. The raw process data used to construct the data base is first discussed along with material and energy balance conventions. Following this, each test is described with the process geometry and a brief operating chronology given. Differential and integral summary information in tabular and graphic form is provided for each test. Computer tapes of the entire data base may be requested from the authors through the Lawrence Livermore National Laboratory.

  15. Analysis of Rocky Mountain I Underground Coal Gasification test. Topical report, March 1989-December 1989

    SciTech Connect (OSTI)

    Lan, S.S.; Floyd, F.M.

    1989-12-01T23:59:59.000Z

    In the Rocky Mountain I Underground Coal Gasification (UCG) Project, the Extended Linked Well (ELW) module and the Controlled Retracting Injection Point (CRIP) module were operated and demonstrated side-by-side. This engineering analysis of the process data was conducted to establish the viability of these technologies for commercial use. The data indicate that an optimum oxygen rate (700 SCFM) exists for the CRIP module and that the optimum steam/oxygen rate is comparable to that for moving bed gasifiers (1.3:1). Data from the post oxygen injection period indicate that 6-10% of carbon in the product gas from the ELW module was a result of pyrolysis. The gas produced by devolatilization was essentially free of carbon dioxide.

  16. TOWARD END-TO-END MODELING FOR NUCLEAR EXPLOSION MONITORING: SIMULATION OF UNDERGROUND NUCLEAR EXPLOSIONS AND EARTHQUAKES USING HYDRODYNAMIC AND ANELASTIC SIMULATIONS, HIGH-PERFORMANCE COMPUTING AND THREE-DIMENSIONAL EARTH MODELS

    SciTech Connect (OSTI)

    Rodgers, A; Vorobiev, O; Petersson, A; Sjogreen, B

    2009-07-06T23:59:59.000Z

    This paper describes new research being performed to improve understanding of seismic waves generated by underground nuclear explosions (UNE) by using full waveform simulation, high-performance computing and three-dimensional (3D) earth models. The goal of this effort is to develop an end-to-end modeling capability to cover the range of wave propagation required for nuclear explosion monitoring (NEM) from the buried nuclear device to the seismic sensor. The goal of this work is to improve understanding of the physical basis and prediction capabilities of seismic observables for NEM including source and path-propagation effects. We are pursuing research along three main thrusts. Firstly, we are modeling the non-linear hydrodynamic response of geologic materials to underground explosions in order to better understand how source emplacement conditions impact the seismic waves that emerge from the source region and are ultimately observed hundreds or thousands of kilometers away. Empirical evidence shows that the amplitudes and frequency content of seismic waves at all distances are strongly impacted by the physical properties of the source region (e.g. density, strength, porosity). To model the near-source shock-wave motions of an UNE, we use GEODYN, an Eulerian Godunov (finite volume) code incorporating thermodynamically consistent non-linear constitutive relations, including cavity formation, yielding, porous compaction, tensile failure, bulking and damage. In order to propagate motions to seismic distances we are developing a one-way coupling method to pass motions to WPP (a Cartesian anelastic finite difference code). Preliminary investigations of UNE's in canonical materials (granite, tuff and alluvium) confirm that emplacement conditions have a strong effect on seismic amplitudes and the generation of shear waves. Specifically, we find that motions from an explosion in high-strength, low-porosity granite have high compressional wave amplitudes and weak shear waves, while an explosion in low strength, high-porosity alluvium results in much weaker compressional waves and low-frequency compressional and shear waves of nearly equal amplitude. Further work will attempt to model available near-field seismic data from explosions conducted at NTS, where we have accurate characterization of the sub-surface from the wealth of geological and geophysical data from the former nuclear test program. Secondly, we are modeling seismic wave propagation with free-surface topography in WPP. We have model the October 9, 2006 and May 25, 2009 North Korean nuclear tests to investigate the impact of rugged topography on seismic waves. Preliminary results indicate that the topographic relief causes complexity in the direct P-waves that leads to azimuthally dependent behavior and the topographic gradient to the northeast, east and southeast of the presumed test locations generate stronger shear-waves, although each test gives a different pattern. Thirdly, we are modeling intermediate period motions (10-50 seconds) from earthquakes and explosions at regional distances. For these simulations we run SPECFEM3D{_}GLOBE (a spherical geometry spectral element code). We modeled broadband waveforms from well-characterized and well-observed events in the Middle East and central Asia, as well as the North Korean nuclear tests. For the recent North Korean test we found that the one-dimensional iasp91 model predicts the observed waveforms quite well in the band 20-50 seconds, while waveform fits for available 3D earth models are generally poor, with some exceptions. Interestingly 3D models can predict energy on the transverse component for an isotropic source presumably due to surface wave mode conversion and/or multipathing.

  17. LLNL underground coal gasification project. Quarterly progress report, July-Sep 1980. [Hoe Creek and Gorgas, Alabama tests

    SciTech Connect (OSTI)

    Olness, D.U. (ed.)

    1980-10-14T23:59:59.000Z

    Laboratory studies of forward gasification through drilled holes in blocks of coal have continued. Such studies give insight into cavity growth mechanisms and particulate production. In addition to obtaining a qualitative comparison of the forward burn characteristics of two coals, we obtained information on the influence of bedding plane/cleat structure orientation on the early-time shape of the burn cavity in the Roland coal. We have improved our model of the coal drying rate during underground coal gasification (UCG) by adding refinements to the model. To aid in analyzing and predicting the performance of UCG tests, we have developed a simple gas-compositional model. When the model was tested against experimental data from the three Hoe Creek experiments, it was able to match very closely the observed gas compositions, energy fractions, and water influxes. This model can be used to make performance predictions consistent with the material and energy balance constraints of the underground system. A postburn coring and wireline-logging study is under way at the Hoe Creek No. 3 site to investigate the overall effect of the directionally-drilled, horizontal linking hole to better estimate the amount of coal gasified and the shape of the combustion front, and to provide additional information on subsurface deformation and thermal effects. The site reclamation work was completed, including the dismantling of all surface equipment and piping and the plugging and sealing of process and diagnostics wells. Final grading of the reclaimed land has been completed, and the area is ready for disk-seeding. Our survey of the UCG literature has continued with a review of the extensive tests at Gorgas, Alabama, carried on by the US Bureau of Mines from 1947 to 1959.

  18. Laboratory's role in Cold War nuclear weapons testing program...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    70th anniversary lecture Laboratory's role in Cold War nuclear weapons testing program focus of next 70th anniversary lecture Lab's role in the development of nuclear weapons...

  19. The science case for 37Ar as a monitor for underground nuclear explosions

    SciTech Connect (OSTI)

    Haas, Derek A.; Orrell, John L.; Bowyer, Ted W.; McIntyre, Justin I.; Miley, Harry S.; Aalseth, Craig E.; Hayes, James C.

    2010-06-04T23:59:59.000Z

    A new calculation of the production of 37Ar from nuclear explosion neutron interactions on 40Ca in a suite of common sub-surface materials (rock, etc) is presented. Even in mineral structures that are relatively low in Ca, the resulting 37Ar signature is large enough for detection in cases of venting or gaseous diffusion driven by barometric pumping. Field and laboratory detection strategies and projected sensitivities are presented.

  20. Nuclear cask testing films misleading and misused

    SciTech Connect (OSTI)

    Audin, L. [Audin (Lindsay), Ossining, NY (United States)

    1991-10-01T23:59:59.000Z

    In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ``proof`` to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests.

  1. Nuclear cask testing films misleading and misused

    SciTech Connect (OSTI)

    Audin, L. (Audin (Lindsay), Ossining, NY (United States))

    1991-10-01T23:59:59.000Z

    In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This paper discusses factors which cast doubt on the veracity of the films and the results of the tests.

  2. Madelyn Creedon visits NNSS U1a underground complex | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.govSecurity AdministrationNuclearMC&ASecurity

  3. Corrective Action Investigation Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada, Revision No. 1 (9/2001)

    SciTech Connect (OSTI)

    NNSA /NV

    2000-07-20T23:59:59.000Z

    This corrective action investigation plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 262 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 262 consists of nine Corrective Action Sites (CASs): Underground Storage Tank (25-02-06), Septic Systems A and B (25-04-06), Septic System (25-04-07), Leachfield (25-05-03), Leachfield (25-05-05), Leachfield (25-05-06), Radioactive Leachfield (25-05-08), Leachfield (25-05-12), and Dry Well (25-51-01). Situated in Area 25 at the Nevada Test Site (NTS), sites addressed by CAU 262 are located at the Reactor-Maintenance, Assembly, and Disassembly (R-MAD); Test Cell C; and Engine-Maintenance, Assembly, and Disassembly (E-MAD) facilities. The R-MAD, Test Cell C, and E-MAD facilities supported nuclear rocket reactor and engine testing as part of the Nuclear Rocket Development Station. The activities associated with the testing program were conducted between 1958 and 1973. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern (COPCs) for the site include oil/diesel-range total petroleum hydrocarbons, volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls, Resource Conservation and Recovery Act metals, and gamma-emitting radionuclides, isotopic uranium, isotopic plutonium, strontium-90, and tritium. The scope of the corrective action field investigation at the CAU will include the inspection of portions of the collection systems, sampling the contents of collection system features in situ of leachfield logging materials, surface soil sampling, collection of samples of soil underlying the base of inlet and outfall ends of septic tanks and outfall ends of diversion structures and distribution boxes, collection of soil samples from biased or a combination of biased and random locations within the boundaries of the leachfields, collection of soil samples at stepout locations (where needed) to further define lateral and vertical extent of contamination, conduction of discrete field screening, and logging of soil borings and collection of geotechnical samples to assess soil characteristics. Historical information indicates that significant quantities of radioactive material were produced during the rocket engine testing program, some of which was disposed of in radioactive waste disposal systems (posted leachfields) at each of these locations. Process and sanitary effluents were generated and disposed of in other leachfields. The results of this field investigation will be used to develop and evaluate corrective action alternatives for these CASs.

  4. EMMA a new underground cosmic-ray experiment T. Enqvista

    E-Print Network [OSTI]

    Usoskin, Ilya G.

    and Nuclear Safety Authority ­ STUK, Helsinki, Finland d Centre for Underground Physics at Pyh¨asalmi (CUPP

  5. Underground coal gasification: Development of theory, laboratory experimentation, interpretation, and correlation with the Hanna field tests: Final report

    SciTech Connect (OSTI)

    Gunn, R.D.; Krantz, W.B.

    1987-03-01T23:59:59.000Z

    The following report is a description of a 7 year effort to develop a theoretical understanding of the underground coal gasification process. The approach used is one of the mathematical model development from known chemical and principles, simplification of the models to isolate important effects, and through validation of models to isolate important effects, and through validation of models with laboratory experiments and field test data. Chapter I contains only introductory material. Chapter II describes the development of two models for reverse combustion: a combustion model and a linearized model for combustion front instability. Both models are required for realistic field predictions. Chapter III contains a discussion of a successful forward gasification model. Chapter IV discusses the spalling-enhanced-drying model is applicable to prediction of cavity growth and subsidence. Chapter VI decribes the correct use of energy and material balances for the analysis of UCG field test data. Chapter VII shows how laboratory experiments were used to validate the models for reverse combustion and forward gasification. It is also shown that laboratory combustion tube experiments can be used to simulate gas compositions expected from field tests. Finally, Chapter VII presents results from a comprehensive economic analysis of UCG involving 1296 separate cases. 37 refs., 49 figs., 12 tabs.

  6. Nuclear Rocket Development Station at the Nevada Test Site |...

    Office of Environmental Management (EM)

    Rocket Development Station at the Nevada Test Site Nuclear Rocket Development Station at the Nevada Test Site During the 1950s, the United States launched a nuclear rocket program...

  7. Seismic requirements for design of nuclear power plants and nuclear test facilities

    SciTech Connect (OSTI)

    Not Available

    1985-02-01T23:59:59.000Z

    This standard establishes engineering requirements for the design of nuclear power plants and nuclear test facilities to accommodate vibratory effects of earthquakes.

  8. Operation Cornerstone onsite radiological safety report for announced nuclear tests, October 1988--September 1989

    SciTech Connect (OSTI)

    Not Available

    1990-08-01T23:59:59.000Z

    Cornerstone was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site (NTS) from October 1, 1988, through September 30, 1989. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Radiation Protection Technicians (RPT) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage were provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined.

  9. Mine seismicity and the Comprehensive Nuclear Test Ban Treaty

    SciTech Connect (OSTI)

    Chiappetta, F. [Blasting Analysis International, Allentown, PA (United States); Heuze, F.; Walter, W. [Lawrence Livermore National Lab., CA (United States); Hopler, R. [Powderman Consulting Inc., Oxford, MD (United States); Hsu, V. [Air Force Technical Applications Center, Patrick AFB, FL (United States); Martin, B. [Thunder Basin Coal Co., Wright, WY (United States); Pearson, C. [Los Alamos National Lab., NM (United States); Stump, B. [Southern Methodist Univ., Dallas, TX (United States); Zipf, K. [Univ. of New South Wales (Australia)

    1998-12-09T23:59:59.000Z

    Surface and underground mining operations generate seismic ground motions which are created by chemical explosions and ground failures. It may come as a surprise to some that the ground failures (coal bumps, first caves, pillar collapses, rockbursts, etc.) can send signals whose magnitudes are as strong or stronger than those from any mining blast. A verification system that includes seismic, infrasound, hydroacoustic and radionuclide sensors is being completed as part of the CTBT. The largest mine blasts and ground failures will be detected by this system and must be identified as distinct from signals generated by small nuclear explosions. Seismologists will analyze the seismic records and presumably should be able to separate them into earthquake-like and non earthquake-like categories, using a variety of so-called seismic discriminants. Non-earthquake essentially means explosion- or implosion-like. Such signals can be generated not only by mine blasts but also by a variety of ground failures. Because it is known that single-fired chemical explosions and nuclear explosion signals of the same yield give very similar seismic records, the non-earthquake signals will be of concern to the Treaty verification community. The magnitude of the mine-related events is in the range of seismicity created by smaller nuclear explosions or decoupled tests, which are of particular concern under the Treaty. It is conceivable that legitimate mining blasts or some mine-induced ground failures could occasionally be questioned. Information such as shot time, location and design parameters may be all that is necessary to resolve the event identity. In rare instances where the legitimate origin of the event could not be resolved by a consultation and clarification procedure, it might trigger on On-Site Inspection (OSI). Because there is uncertainty in the precise location of seismic event as determined by the International Monitoring System (IMS), the OSI can cover an area of up to 1,000 squared kilometers. In active mining districts this area could include several different mining operations. So, an OSI could be disruptive both to the mining community and to the US Government which must host the foreign inspection team. Accordingly, it is in the best interest of all US parties to try and eliminate the possible occurrence of false alarms. This can be achieved primarily by reducing the ambiguity of mine-induced seismic signals, so that even if these remain visible to the IMS they are clearly consistent with recognizable mining patterns.

  10. Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    1999-05-05T23:59:59.000Z

    This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO, CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites (FFACO, 1996). Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at CAU 135, Area 25 Underground Storage Tanks (USTs), which is located on the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada.

  11. Corrective Action Decision Document for Corrective Action Unit 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

    SciTech Connect (OSTI)

    DOE /NV

    1999-06-19T23:59:59.000Z

    This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 423, Building 03-60 Underground Discharge Point (UDP) in accordance with the Federal Facility Agreement and Consent Order (FFACO) of 1996 that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the Nevada Division of Environmental Protection (NDEP); and the U.S Department of Defense (FFACO, 1996). The CADD provides or references the specific information necessary to recommend a preferred corrective action for the single Corrective Action Site (CAS), 03-02-002-0308, within CAU 423. Corrective Action Unit 423 is located at the Tonopah Test Range (TTR), Nevada. The TTR is approximately 255 kilometers (km) (140 miles[mi]) northwest of Las Vegas, Nevada. The UDP is approximately 73 meters (m) (240 feet [ft]) northwest of the northwest corner of Building 03-60, the Auto Maintenance Shop. Corrective Action Unit 423 is comprised of the UDP and an associated discharge line extending from Building 03-60. The UDP received waste oil products from the Auto Maintenance Shop, a light-duty fleet maintenance shop in the Area 3 compound, from 1965 to 1989 or 1990 (DOE/NV, 1997).

  12. Addendum to the Closure Report for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    Lynn Kidman

    2008-10-01T23:59:59.000Z

    This document constitutes an addendum to the July 2003, Closure Report for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications.

  13. A STUDY OF REGIONAL TEMPERATURE AND THERMOHYDROLOGICAL EFFECTS OF AN UNDERGROUND REPOSITORY FOR NUCLEAR WASTES IN HARD ROCK

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2010-01-01T23:59:59.000Z

    generated by the stored nuclear wastes. Spent fuel 10-yeartask force for review of nuclear waste manage­ ment, DOE/ER-Review Group on Nuclear Waste Management. Subground report

  14. A STUDY OF REGIONAL TEMPERATURE AND THERMOHYDROLOGICAL EFFECTS OF AN UNDERGROUND REPOSITORY FOR NUCLEAR WASTES IN HARD ROCK

    E-Print Network [OSTI]

    Wang, J.S.Y.

    2010-01-01T23:59:59.000Z

    of heat generated by the stored nuclear wastes. Spent fuelmode of heat transfer from the nuclear waste to the rockdensity of heat generated by the stored nuclear wastes Fig.

  15. Supporting the Comprehensive Nuclear-Test-Ban Treaty

    ScienceCinema (OSTI)

    Bowyer, Ted

    2014-06-12T23:59:59.000Z

    PNNL operates the only certified laboratory in the U.S. for the Comprehensive Nuclear-Test-Ban Treaty's International Monitoring System (IMS).

  16. Supporting the Comprehensive Nuclear-Test-Ban Treaty

    SciTech Connect (OSTI)

    Bowyer, Ted

    2014-11-20T23:59:59.000Z

    PNNL operates the only certified laboratory in the U.S. for the Comprehensive Nuclear-Test-Ban Treaty's International Monitoring System (IMS).

  17. Critical assessment of seismic and geomechanics literature related to a high-level nuclear waste underground repository

    SciTech Connect (OSTI)

    Kana, D.D.; Vanzant, B.W.; Nair, P.K. [Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses; Brady, B.H.G. [ITASCA Consulting Group, Inc., Minneapolis, MN (USA)

    1991-06-01T23:59:59.000Z

    A comprehensive literature assessment has been conducted to determine the nature and scope of technical information available to characterize the seismic performance of an underground repository and associated facilities. Significant deficiencies were identified in current practices for prediction of seismic response of underground excavations in jointed rock. Conventional analytical methods are based on a continuum representation of the host rock mass. Field observations and laboratory experiments indicate that, in jointed rock, the behavior of the joints controls the overall performance of underground excavations. Further, under repetitive seismic loading, shear displacement develops progressively at block boundaries. Field observations correlating seismicity and groundwater conditions have provided significant information on hydrological response to seismic events. However, lack of a comprehensive model of geohydrological response to seismicity has limited the transportability conclusions from field observations. Based on the literature study, matters requiring further research in relation to the Yucca Mountain repository are identified. The report focuses on understanding seismic processes in fractured tuff, and provides a basis for work on the geohydrologic response of a seismically disturbed rock mass. 220 refs., 43 figs., 11 tabs.

  18. Examination of the 1970 National Bureau of Standards Underground Corrosion Test Welded Stainless STeel Coupons from Site D

    SciTech Connect (OSTI)

    L. R. Zirker; M. K. Adler Flitton; T. S. Yoder; T. L. Trowbridge

    2008-01-01T23:59:59.000Z

    A 1970 study initiated by the National Bureau of Standards (NBS), now known as the National Institute of Standards and Technology (NIST), buried over 6000 corrosion coupons or specimens of stainless steel Types 201, 202, 301, 304, 316, 409, 410, 430, and 434. The coupons were configured as sheet metal plates, coated plates, cross-welded plates, U-bend samples, sandwiched materials, and welded tubes. All coupons were of various heat-treatments and cold worked conditions and were buried at six distinctive soil-type sites throughout the United States. The NBS scientists dug five sets of two trenches at each of the six sites. In each pair of trenches, they buried duplicate sets of stainless steel coupons. The NBS study was designed to retrieve coupons after one year, two years, four years, eight years, and x years in the soil. During the first eight years of the study, four of five planned removals were completed. After the fourth retrieval, the NBS study was abandoned, and the fifth and final set of specimens remained undisturbed for over 33 years. In 2003, an interdisciplinary research team of industrial, university, and national laboratory investigators were funded under the United States Department of Energy’s Environmental Management Science Program (EMSP; Project Number 86803) to extract part of the remaining set of coupons at one of the test sites, characterize the stainless steel underground corrosion rates, and examine the fate and transport of metal ions into the soil. Extraction of one trench at one of the test sites occurred in April 2004. This report details only the characterization of corrosion found on the 14 welded coupons–two cross welded plates, six U-bends, and six welded tubes–that were retrieved from Site D, located near Wildwood, NJ. The welded coupons included Type 301, 304, 316, and 409 stainless steels. After 33 years in the soil, corrosion on the coupons varied according to alloy. This report discusses the stress corrosion cracking and crevice corrosion cracking of the U-bend coupons; the minimal corrosion found on the cross-bead plates; and the general, pitting, and crevice corrosion found on the welded tubes. In general, the austenitic Type 301, 304 and 316 samples showed little if any corrosion after 33+-years in the soil, whereas the ferritic alloys-Type 409 and 434– showed a spectrum of corrosion.

  19. DOE Underground-Coal-Conversion-Program field-test activities for 1979 and 1980. [Pricetown 1, Hoe Creek 3, Hanna IV, and SDB 1

    SciTech Connect (OSTI)

    Bartke, T.C.

    1983-08-01T23:59:59.000Z

    Under the US Department of Energy's Underground-Coal-Conversion program, four field tests were completed in 1979 and preparations were begun in 1980 for two additional field tests to be operated in 1981. The Laramie Energy Technology Center (LETC) and Sandia National Laboratories (SNL) completed Hanna IV, an air gasification test in Wyoming subbituminous coal. The Morgantown Energy Technology Center (METC) completed Pricetown 1, an air gasification test in West Virginia bituminous coal. Lawrence Livermore National Laboratory (LLNL) completed Hoe Creek 3, a steam-oxygen gasification test in Wyoming subbituminous coal. Gulf Research and Development Co. completed Steeply Dipping Beds (SDB) Test 1, primarily an air gasification test in Wyoming subbituminous coal and the first SDB test in the US. In 1980, Gulf R and D Co. began preparation of SDB Test 2, scheduled for operation in the fall of 1981. The DOE project teams at LETC, METC, LLNL, and SNL, in association with the Washington Irrigation and Development Co. (WIDCo), Washington Water Power (WWP), and the State of Washington, are preparing a field test site in the Centralia-Chehalis coal district of Washington. A series of large coal block tests will be completed prior to the field test, scheduled for operation in 1982 or 1983. This field test will utilize a directionally drilled link and steam-oxygen gasification system. This paper summarizes the results of the four recently completed field tests and the plans for additional tests.

  20. United States nuclear tests, July 1945 through September 1992

    SciTech Connect (OSTI)

    Not Available

    1994-12-01T23:59:59.000Z

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

  1. Nuclear Instruments and Methods in Physics Research A 518 (2004) 775798 CUORE: a cryogenic underground observatory for rare events

    E-Print Network [OSTI]

    -67010 Assergi (L'Aquila), Italy f Laboratorio de Fisica Nuclear y Altas Energias, Universid"ad de of 130 Te (33.8% abundance), cold dark matter, solar axions, and rare nuclear decays. A preliminary

  2. Test facilities for evaluating nuclear thermal propulsion systems

    SciTech Connect (OSTI)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C. (Sandia National Labs., Albuquerque, NM (United States)); Todosow, M. (Brookhaven National Lab., Upton, NY (United States))

    1992-09-22T23:59:59.000Z

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized.

  3. Nuclear Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

  4. Opportunities in underground coal gasification

    SciTech Connect (OSTI)

    Bloomstran, M.A.; Davis, B.E.

    1984-06-01T23:59:59.000Z

    A review is presented of the results obtained on DOE-sponsored field tests of underground coal gasification in steeply-dipping beds at Rawlins, Wyoming. The coal gas composition, process parameters, and process economics are described. Steeply-dipping coal resources, which are not economically mineable using conventional coal mining methods, are identified and potential markets for underground coal gasification products are discussed. It is concluded that in-situ gasification in steeply-dipping deposits should be considered for commercialization.

  5. HEAT TRANSFER IN UNDERGROUND HEATING EXPERIMENTS IN GRANITE, STRIPA, SWEDEN

    E-Print Network [OSTI]

    Chan, T.

    2010-01-01T23:59:59.000Z

    Session on Heat Transfer in Nuclear Waste Disposal, C'.heat transfer processes associated with underground nuclear wasteheat transfer and related processes in an un­ derground environment similar to that expected in a mined nuclear waste

  6. CORRECTIVE ACTION DECISION DOCUMENT FOR CORRECTIVE ACTION UNIT 423: BUILDING 03-60 UNDERGROUND DISCHARGE POINT, TONOPAH TEST RANGE, NEVADA, REVISION 0, JUNE 1998

    SciTech Connect (OSTI)

    NONE

    1998-06-01T23:59:59.000Z

    This Corrective Action Decision Document has been prepared for the Area 3 Building 03-60 Underground Discharge Point (Corrective Action Unit 423) in accordance with the Federal Facility Agreement and Consent Order of 1996 (FFACO, 1996). Corrective Action Unit 423 is located at the Tonopah Test Range and is comprised of Corrective Action Site 03-02-002-0308. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for Corrective Action Unit 423. The scope of this Correction Action Decision Document consists of the following: ? Develop corrective action objectives. ? Identify corrective action alternative screening criteria. ? Develop corrective action alternatives. ? Perform detailed and comparative evaluations of the corrective action alternatives in relation to the corrective action objectives and screening criteria. ? Recommend and justify a preferred corrective action alternative for the Corrective Action Unit. In January 1998, a corrective action investigation was performed as set forth in the Corrective Action Investigation Plan for Corrective Action Unit No. 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada (DOE/NV, 1997). A hydrocarbon plume was found to emanate from near the bottom of the Underground Discharge Point to the west. The plume encompasses approximately 65 square meters (700 square feet). The highest total petroleum hydrocarbon level detected was 2,400 milligrams per kilogram. No other contaminants were detected above preliminary action levels. Details of the investigation can be found in Appendix A of this document. Based on the potential exposure pathways identified during the Data Quality Objectives process, the following corrective action objectives have been identified for Corrective Action Unit 423: ? Prevent or mitigate human exposure to subsurface soil containing contaminants of concern. ? Prevent adverse impacts to groundwater quality. Based on the review of existing data, future land use assumption, and current operations at the Tonopah Test Range, the following alternatives were developed for consideration at the Building 03-60 Underground Discharge Point: ? Alternative 1 - No Action ? Alternative 2 - Closure in Place with Administrative Controls ? Alternative 3 - Partial Excavation, Disposal, and Administrative Controls ? Alternative 4 - In Situ Bioremediation The corrective action alternatives were evaluated based on four general corrective action standards and five remedy selection decision factors. Based on the results of this evaluation, the preferred alternative for Corrective Action Unit 423 is Alternative 2, Closure in Place with Administrative Controls. The preferred corrective action alternative was evaluated on technical merit, focusing on performance, reliability, feasibility, and safety. The alternative was judged to meet all requirements for the technical components evaluated. The alternative also meets all applicable state and federal regulations for closure of the site and will reduce potential future exposure pathways to the contaminated soils.

  7. Nuclear Waste Technical Review Board Members: Curricula Vitae

    E-Print Network [OSTI]

    mines, and storage projects, primarily in the fields of engineering geology and rock mechanics as an international consultant in the planning, designing, and construction of shafts, tunnels, dams, underground and Scisson and the U.S. Atomic Energy Commission on the design of underground openings for nuclear tests

  8. Testing the Physics of Nuclear Isomers

    SciTech Connect (OSTI)

    Hazi, A

    2006-01-25T23:59:59.000Z

    For much of the past century, physicists have searched for methods to control the release of energy stored in an atom's nucleus. Nuclear fission reactors have been one successful approach, but finding other methods to capitalize on this potential energy source have been elusive. One possible source being explored is nuclear isomers. An isomer is a long-lived excited state of an atom's nucleus--a state in which decay back to the nuclear ground state is inhibited. The nucleus of an isomer thus holds an enormous amount of energy. If scientists could develop a method to release that energy instantaneously in a gamma-ray burst, rather than slowly over time, they could use it in a nuclear battery. Research in the late 1990s indicated that scientists were closer to developing such a method--using x rays to trigger the release of energy from the nuclear isomer hafnium-178m ({sup 178m}Hf). To further investigate these claims, the Department of Energy (DOE) funded a collaborative project involving Lawrence Livermore, Los Alamos, and Argonne national laboratories that was designed to reproduce those earlier results.

  9. announced nuclear tests: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    announced nuclear tests First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 ANNOUNCEMENT NUCLEAR...

  10. Clinton Extends Moratorium on Nuclear Weapons Testing | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.gov Office of theNuclearNanotechnologies | National

  11. Reducing emissions to improve nuclear test detection | National Nuclear

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica TreatyWastewantsRequests||Nuclear

  12. Ground test facility for SEI nuclear rocket engines

    SciTech Connect (OSTI)

    Harmon, C.D.; Ottinger, C.A.; Sanchez, L.C.; Shipers, L.R.

    1992-08-01T23:59:59.000Z

    Nuclear Thermal Propulsion (NTP) has been identified as a critical technology in support of the NASA Space Exploration Initiative (SEI). In order to safely develop a reliable, reusable, long-lived flight engine, facilities are required that will support ground tests to qualify the nuclear rocket engine design. Initial nuclear fuel element testing will need to be performed in a facility that supports a realistic thermal and neutronic environment in which the fuel elements will operate at a fraction of the power of a flight weight reactor/engine. Ground testing of nuclear rocket engines is not new. New restrictions mandated by the National Environmental Protection Act of 1970, however, now require major changes to be made in the manner in which reactor engines are now tested. These new restrictions now preclude the types of nuclear rocket engine tests that were performed in the past from being done today. A major attribute of a safely operating ground test facility is its ability to prevent fission products from being released in appreciable amounts to the environment. Details of the intricacies and complications involved with the design of a fuel element ground test facility are presented in this report with a strong emphasis on safety and economy.

  13. atmospheric nuclear tests: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    atmospheric nuclear tests First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Atmospheric Neutrino Tests of...

  14. Investigation of CTBT OSI Radionuclide Techniques at the DILUTED WATERS Nuclear Test Site

    SciTech Connect (OSTI)

    Baciak, James E.; Milbrath, Brian D.; Detwiler, Rebecca S.; Kirkham, Randy R.; Keillor, Martin E.; Lepel, Elwood A.; Seifert, Allen; Emer, Dudley; Floyd, Michael

    2012-11-01T23:59:59.000Z

    Under the Comprehensive Nuclear-Test-Ban Treaty (CTBT), a verification regime that includes the ability to conduct an On-Site Inspection (OSI) will be established. The Treaty allows for an OSI to include many techniques, including the radionuclide techniques of gamma radiation surveying and spectrometry and environmental sampling and analysis. Such radioactivity detection techniques can provide the “smoking gun” evidence that a nuclear test has occurred through the detection and quantification of indicative recent fission products. An OSI faces restrictions in time and manpower, as dictated by the Treaty; not to mention possible logistics difficulties due to the location and climate of the suspected explosion site. It is thus necessary to have a good understanding of the possible source term an OSI will encounter and the proper techniques that will be necessary for an effective OSI regime. One of the challenges during an OSI is to locate radioactive debris that has escaped an underground nuclear explosion (UNE) and settled on the surface near and downwind of ground zero. To support the understanding and selection of sampling and survey techniques for use in an OSI, we are currently designing an experiment, the Particulate Release Experiment (PRex), to simulate a small-scale vent from an underground nuclear explosion. PRex will occur at the Nevada National Security Site (NNSS). The project is conducted under the National Center for Nuclear Security (NCNS) funded by the National Nuclear Security Agency (NNSA). Prior to the release experiment, scheduled for Spring of 2013, the project scheduled a number of activities at the NNSS to prepare for the release experiment as well as to utilize the nuclear testing past of the NNSS for the development of OSI techniques for CTBT. One such activity—the focus of this report—was a survey and sampling campaign at the site of an old UNE that vented: DILUTED WATERS. Activities at DILUTED WATERS included vehicle-based survey, in situ measurements with high-purity germanium (HPGe) and hand-held LaBr3 systems, soil sampling with a variety of tools, and laboratory gamma spectrometric analysis of those samples. A further benefit of the measurement campaign was to gain familiarity with the many logistical aspects of performing radiological field work at NNSS ahead of the PRex. Many practical lessons concerning the proper methodologies and logistics of using the surveying and sampling equipment were noted. These Lessons Learned are compiled together in Appendix A. The vehicle-based survey was successful in that it found a previously unknown hotspot (determined to be 232Th) while it demonstrated that a better method for keeping a serpentine track without staking was needed. Some of the soil sampling equipment was found to be impractical for the application, though core sampling would not be the correct way to take soil samples for a fresh vent deposit (as opposed to an old site like DILUTED WATERS). Due to the site’s age, 137Cs was the only fission radioisotope identified, though others were searched for. While not enough samples were taken and analyzed to definitively link the 137Cs to DILUTED WATERS as opposed to other NNSS activities, results were consistent with the historical DILUTED WATERS plume. MDAs were compared for soil sampling and in situ measurements.

  15. Nuclear Weapons Testing Resumes | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire3627 Federal Register /76SafeguardsSystemsTesting Resumes |

  16. Corrective action investigation plan for Corrective Action Unit Number 423: Building 03-60 Underground Discharge Point, Tonopah Test Range, Nevada

    SciTech Connect (OSTI)

    NONE

    1997-10-27T23:59:59.000Z

    This Corrective Action Investigation Plan (CAIP) contains the environmental sample collection objectives and the criteria for conducting site investigation activities at Corrective Action Unit (CAU) Number 423, the Building 03-60 Underground Discharge Point (UDP), which is located in Area 3 at the Tonopah Test Range (TTR). The TTR, part of the Nellis Air Force Range, is approximately 225 kilometers (140 miles) northwest of Las Vegas, Nevada. CAU Number 423 is comprised of only one Corrective Action Site (CAS) which includes the Building 03-60 UDP and an associated discharge line extending from Building 03-60 to a point approximately 73 meters (240 feet) northwest. The UDP was used between approximately 1965 and 1990 to dispose of waste fluids from the Building 03-60 automotive maintenance shop. It is likely that soils surrounding the UDP have been impacted by oil, grease, cleaning supplies and solvents as well as waste motor oil and other automotive fluids released from the UDP.

  17. Laboratory characterization of the spalling properties of the rock cores from the UCG (Underground Coal Gasification) test site near Porto Alegre in Brazil

    SciTech Connect (OSTI)

    Tantekin, S.B.; Sperry, D.P.; Krantz, W.B.; Britten, J.A.

    1988-02-22T23:59:59.000Z

    One of the principal problems encountered in most of the Underground Coal Gasification (UCG) field tests conducted thus far has been excessive water influx. Spalling-enhanced-drying of coal and overburdens rock has been identified as the principal mechanism of water influx observed in the Hanna UCG field tests in Wyoming Spalling is defined as the chipping, fracturing and breaking off of small rock fragments from the cavity roof due to the combined action of mechanical loading and thermally induced stresses. Spalling is also responsibble for vertical cavity growth and a portion of the heat losses during UCG. A laboratory core characterization method has been developed to determine the spalling properties of overburden rock which are essential to make influx and cavity geometry predictions for a prospective field test. In this study, the spalling properties of the representative rock cores from the UCG test site near Porto Alegre in Brazil have been determined using the laboratory core characterization test which utilizes the temperature-gradient-induced spalling hypothesis.

  18. The behavior of fission products during nuclear rocket reactor tests

    SciTech Connect (OSTI)

    Bokor, P.C.; Kirk, W.L.; Bohl, R.J.

    1991-01-01T23:59:59.000Z

    The experience base regarding fission product behavior developed during the Rover program, the nuclear rocket development program of 1955--1972, will be useful in planning a renewed nuclear rocket program. During the Rover program, 20 reactors were tested at the Nuclear Rocket Development Station in Nevada. Nineteen of these discharged effluent directly into the atmosphere; the last reactor tested, a non-flight-prototypic, fuel-element-testing reactor called the Nuclear Furnace (NF-1) was connected to an effluent cleanup system that removed fission products before the hydrogen coolant (propellant) was discharged to the atmosphere. In general, we are able to increase both test duration and fuel temperature during the test series. Therefore fission product data from the later part of the program are more interesting and more applicable to future reactors. We have collected fission product retention (and release) data reported in both formal and informal publications for six of the later reactor tests; five of these were Los Alamos reactors that were firsts of a kind in configuration or operating conditions. We have also, with the cooperation of Westinghouse, included fission product data from the NRX-A6 reactor, the final member of series of developmental reactors with the same basic geometry, but with significant design and fabrication improvements as the series continued. Table 1 lists the six selected reactors and the test parameters for each.

  19. ENVIRONMENTAL IlONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling7111AWell: Gas productionDynamic ,kL2'

  20. The Nuclear Non-Proliferation Treaty and the Comprehensive Nuclear-Test-Ban Treaty, the relationship

    SciTech Connect (OSTI)

    Graham, Thomas Jr. [7609 Glenbrook Rd., Bethesda, MD 20814 (United States)

    2014-05-09T23:59:59.000Z

    The Nuclear Non-Proliferation Treaty (NPT) is the most important international security arrangement that we have that is protecting the world community and this has been true for many years. But it did not happen by accident, it is a strategic bargain in which 184 states gave up the right forever to acquire the most powerful weapon ever created in exchange for a commitment from the five states allowed to keep nuclear weapons under the NPT (U.S., U.K., Russia, France and China), to share peaceful nuclear technology and to engage in disarmament negotiations aimed at the ultimate elimination of their nuclear stockpiles. The most important part of this is the comprehensive nuclear test ban (CTBT); the thinking by the 184 NPT non-nuclear weapon states was and is that they understand that the elimination of nuclear weapon stockpiles is a long way off, but at least the NPT nuclear weapon states could stop testing the weapons. The CTBT has been ratified by 161 states but by its terms it can only come into force if 44 nuclear potential states ratify; 36 have of the 44 have ratified it, the remaining eight include the United States and seven others, most of whom are in effect waiting for the United States. No state has tested a nuclear weapon-except for complete outlier North Korea-in 15 years. There appears to be no chance that the U.S. Senate will approve the CTBT for ratification in the foreseeable future, but the NPT may not survive without it. Perhaps it is time to consider an interim measure, for the UN Security Council to declare that any future nuclear weapon test any time, anywhere is a 'threat to peace and security', in effect a violation of international law, which in today's world it clearly would be.

  1. Results of Phase 2 postburn drilling, coring, and logging: Rocky Mountain 1 Underground Coal Gasification Test, Hanna, Wyoming

    SciTech Connect (OSTI)

    Oliver, R.L.; Lindblom, S.R.; Covell, J.R.

    1991-02-01T23:59:59.000Z

    The Rocky Mountain 1 (RM1) Underground Coal Gasification (UCG) site consisted of two different module configurations: the controlled retracting injection point (CRIP) and elongated linked well (ELW) configurations. The postburn coring of the RM1 UCG site was designed in two phases to fulfill seven objectives outlined in Western Research Institute's Annual Project Plan for 1989 (Western Research Institute 1989). The seven objectives were to (1) delineate the areal extent of the cavities, (2) identify the extent of roof collapse, (3) obtain samples of all major cavity rock types, (4) characterize outflow channels and cavity stratigraphy, (5) characterize the area near CRIP points and ignition points, (6) further define the structural geology of the site, and (7) identify the vertical positioning of the horizontal process wells within the coal seam. Phase 1 of the coring was completed during the summer of 1989 and served to partially accomplish all seven objectives. A detailed description of Phase 1 results was presented in a separate report (Lindblom et al. 1990). Phase 2, completed during the summer of 1990, was designed to complete the seven objectives; more specifically, to further define the areal extent and location of the cavities, to evaluate the outflow channels for both modules, and to further characterize the structural geology in the ELW module area.

  2. Results of Phase 2 postburn drilling, coring, and logging: Rocky Mountain 1 Underground Coal Gasification Test, Hanna, Wyoming

    SciTech Connect (OSTI)

    Oliver, R.L.; Lindblom, S.R.; Covell, J.R.

    1991-02-01T23:59:59.000Z

    The Rocky Mountain 1 (RM1) Underground Coal Gasification (UCG) site consisted of two different module configurations: the controlled retracting injection point (CRIP) and elongated linked well (ELW) configurations. The postburn coring of the RM1 UCG site was designed in two phases to fulfill seven objectives outlined in Western Research Institute`s Annual Project Plan for 1989 (Western Research Institute 1989). The seven objectives were to (1) delineate the areal extent of the cavities, (2) identify the extent of roof collapse, (3) obtain samples of all major cavity rock types, (4) characterize outflow channels and cavity stratigraphy, (5) characterize the area near CRIP points and ignition points, (6) further define the structural geology of the site, and (7) identify the vertical positioning of the horizontal process wells within the coal seam. Phase 1 of the coring was completed during the summer of 1989 and served to partially accomplish all seven objectives. A detailed description of Phase 1 results was presented in a separate report (Lindblom et al. 1990). Phase 2, completed during the summer of 1990, was designed to complete the seven objectives; more specifically, to further define the areal extent and location of the cavities, to evaluate the outflow channels for both modules, and to further characterize the structural geology in the ELW module area.

  3. Effluent treatment options for nuclear thermal propulsion system ground tests

    SciTech Connect (OSTI)

    Shipers, L.R.; Brockmann, J.E.

    1992-10-16T23:59:59.000Z

    A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the strengths and weaknesses of different methods to handle effluent from nuclear thermal propulsion system ground tests.

  4. Handling effluent from nuclear thermal propulsion system ground tests

    SciTech Connect (OSTI)

    Shipers, L.R.; Allen, G.C.

    1992-09-09T23:59:59.000Z

    A variety of approaches for handling effluent from nuclear thermal propulsion system ground tests in an environmentally acceptable manner are discussed. The functional requirements of effluent treatment are defined and concept options are presented within the framework of these requirements. System concepts differ primarily in the choice of fission-product retention and waste handling concepts. The concept options considered range from closed cycle (venting the exhaust to a closed volume or recirculating the hydrogen in a closed loop) to open cycle (real time processing and venting of the effluent). This paper reviews the different methods to handle effluent from nuclear thermal propulsion system ground tests.

  5. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    SciTech Connect (OSTI)

    DeAnn Long; Michael Murphy

    2008-07-01T23:59:59.000Z

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

  6. Underground coal gasification: environmental update

    SciTech Connect (OSTI)

    Dockter, L.; Mcternan, E.M.

    1985-01-01T23:59:59.000Z

    To evaluate the potential for ground water contamination by underground coal gasification, extensive postburn groundwater monitoring programs are being continued at two test sites in Wyoming. An overview of the environmental concerns related to UCG and some results to date on the two field sites are presented in this report.

  7. Underground Storage Tank Regulations

    Broader source: Energy.gov [DOE]

    The Underground Storage Tank Regulations is relevant to all energy projects that will require the use and building of pipelines, underground storage of any sorts, and/or electrical equipment. The...

  8. Gamma-Ray Bursts Nuclear Test Ban Treaty, 1963

    E-Print Network [OSTI]

    Harrison, Thomas

    Lecture 18 Gamma-Ray Bursts #12;Nuclear Test Ban Treaty, 1963 First Vela satellite pair launched and their predecessors, Vela 4, discovered the first gamma-ray bursts. The discovery was announced by Klebesadel, Strong, and Olson (ApJ, 182, 85) in 1973. #12;First Gamma-Ray Burst The Vela 5 satellites functioned from July, 1969

  9. Guidelines for inservice testing at nuclear power plants

    SciTech Connect (OSTI)

    Campbell, P.

    1995-04-01T23:59:59.000Z

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

  10. Thermal measurements in the nuclear winter fire test

    SciTech Connect (OSTI)

    Schneider, M.E.; Keltner, N.R.; Kent, L.A.

    1989-01-01T23:59:59.000Z

    In March, 1987, a large open pool fire test was performed to provide test measurements to help define the thermal characteristics of large open pool fires and estimates of the smoke source term for the nuclear winter (global effects) scenario. This report will present the results of the thermal measurements as well as comparisons with previous test results. These measurements included flame temperatures, heat fluxes to a variety of calorimeters, and gas velocities in the lower flame regions. 13 refs., 76 figs., 7 tabs.

  11. Testing of Small Graphite Samples for Nuclear Qualification

    SciTech Connect (OSTI)

    Julie Chapman

    2010-11-01T23:59:59.000Z

    Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

  12. Underground gasification for steeply dipping coal beds: Phase III. Quarterly progress report, April 1-June 30, 1981. [Rawlins Test 2

    SciTech Connect (OSTI)

    Not Available

    1981-12-01T23:59:59.000Z

    Preparations are being made for the August start-up of Rawlins Test 2. Site construction activities began May 4 with the mobilization of the construction subcontractor. The drilling program was completed this quarter with the installation of instrumentation wells. The Experimental Basis Document, PGA Operating Manual, and DAS Operating Manual have also been completed.

  13. Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

    SciTech Connect (OSTI)

    Friesen, H.N.

    1995-06-01T23:59:59.000Z

    Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

  14. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2004-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium metal to determine compliance with specifications.

  15. Closure report: Nevada Test Site Underground Storage Tank (UST) number 25-3123-1: Nevada Division of Emergency Management case number H940825D corrective action unit 450

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    This document has been prepared as a final closure report documenting the assessment and corrective actions taken for the petroleum hydrocarbon release associated with underground storage tank (UST) UST25-3123-1. UST25-3123-1 was located at Area 25 within the Nevada Test Site. The UST was identified as abandoned to be closed under the U.S. Department of Energy/Nevada Operations Office Environmental Restoration Division Program during Fiscal Year 1994. The scope of work for closure of the UST included evaluating site conditions and closing the tank in accordance with all applicable regulations. Site evaluation analytic results of a soil sample collected below the tank showed a diesel concentration of 120 mg/kg at a depth of 3 meters. During remedial excavation, approximately 3.8 cubic meters of hydrocarbon impacted soil was removed. Laboratory analysis of the soil sample collected from the excavation bottom confirms that total petroleum hydrocarbon concentrations greater than 100 mg/kg are no longer present. Therefore, it is requested that the site be closed without further action. 4 refs., 2 figs., 3 tabs.

  16. Implications of atmospheric test fallout data for nuclear winter

    SciTech Connect (OSTI)

    Baker, G.H. III

    1987-01-01T23:59:59.000Z

    Atmospheric-test fallout data were used to determine admissable-dust particle-size distributions for nuclear-winter studies. The research was originally motivated by extreme differences noted in the magnitude and longevity of dust effects predicted by particle-size distributions routinely used in fallout predictions versus those used for nuclear-winter studies. Three different sets of historical data were analyzed: (1) stratospheric burden of strontium-90 and tungsten-185, 1954-1967 (92 contributing events); (2) continental US strontium-90 fallout through 1958 (75 contributing events); (3) local fallout from selected Nevada tests (16 events). The contribution of dust to possible long-term climate effects following a nuclear exchange depends strongly on the particle-size distribution. The distribution affects both the atmospheric residence time and optical depth. One-dimensional models of stratospheric/tropospheric fallout removal were developed and used to identify optimum particle distributions. Results indicate that particle distributions that properly predict bulk stratospheric activity transfer tend to be somewhat smaller than number size distributions used in initial nuclear winter studies. In addition, both /sup 90/Sr and /sup 185/W fallout behavior is better predicted by the log normal distribution function than the prevalent power-law hybrid function.

  17. DIGITAL RADIOGRAPHY OF SPECIAL NUCLEAR MATERIAL TEST PACKAGES

    SciTech Connect (OSTI)

    HOWARD, BOYD

    2006-02-02T23:59:59.000Z

    The purpose of this document is to provide a brief introduction to digital radiography (DR), and a description of the DR configuration that was used to radiographically image the Special Nuclear Material (SNM) Test Packages before and after function tests that have been conducted. Also included are (1) Attachment 1, a comprehensive index that describes at which phase of the certification process that digital radiographic images were acquired, (2) digital radiographic images of each of the six packages at various stages of the certification process, and (3) Attachment 2, imaging instructions, that specify the setup procedures and detailed parameters of the DR imaging methodology that were used.

  18. Today and Future Neutrino Experiments at Krasnoyarsk Nuclear Reactor

    E-Print Network [OSTI]

    Yu. V. Kozlov; S. V. Khalturtsev; I. N. Machulin; A. V. Martemyanov; V. P. Martemyanov; A. A. Sabelnikov; V. G. Tarasenkov; E. V. Turbin; V. N. Vyrodov; L. A. Popeko; A. V. Cherny; G. A. Shishkina

    1999-12-22T23:59:59.000Z

    The results of undergoing experiments and new experiment propositions at Krasnoyarsk underground nuclear reactor are presented

  19. Non Nuclear Testing of Reactor Systems In The Early Flight Fission Test Facilities (EFF-TF)

    SciTech Connect (OSTI)

    Van Dyke, Melissa; Martin, James [Marshall Space Flight Center, National Aeronautics and Space Administration, Huntsville, Alabama, 35812 (United States)

    2004-07-01T23:59:59.000Z

    The Early Flight Fission-Test Facility (EFF-TF) can assist in the design and development of systems through highly effective non-nuclear testing of nuclear systems when technical issues associated with near-term space fission systems are 'non-nuclear' in nature (e.g. system's nuclear operations are understood). For many systems, thermal simulators can be used to closely mimic fission heat deposition. Axial power profile, radial power profile, and fuel pin thermal conductivity can be matched. In addition to component and subsystem testing, operational and lifetime issues associated with the steady state and transient performance of the integrated reactor module can be investigated. Instrumentation at the EFF-TF allows accurate measurement of temperature, pressure, strain, and bulk core deformation (useful for accurately simulating nuclear behavior). Ongoing research at the EFF-TF is geared towards facilitating research, development, system integration, and system utilization via cooperative efforts with DOE laboratories, industry, universities, and other Nasa centers. This paper describes the current efforts for the latter portion of 2003 and beginning of 2004. (authors)

  20. Underground Injection Control (Louisiana)

    Broader source: Energy.gov [DOE]

    The Injection and Mining Division (IMD) has the responsibility of implementing two major federal environmental programs which were statutorily charged to the Office of Conservation: the Underground...

  1. Ground test facilities for evaluating nuclear thermal propulsion engines and fuel elements

    SciTech Connect (OSTI)

    Allen, G.C.; Beck, D.F.; Harmon, C.D.; Shipers, L.R.

    1992-08-01T23:59:59.000Z

    Interagency panels evaluating nuclear thermal propulsion development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and design issues of a proposed ground test complex for evaluating nuclear thermal propulsion engines and fuel elements being developed for the Space Nuclear Thermal Propulsion (SNTP) program. 2 refs.

  2. Exhaust gas treatment in testing nuclear rocket engines

    SciTech Connect (OSTI)

    Zweig, H.R.; Fischler, S.; Wagner, W.R. (Rocketdyne Division, Rockwell International Corporation, 6633 Canoga Avenue, P.O. Box 7922, Canoga Park, California 91309-7922 (United States))

    1993-01-15T23:59:59.000Z

    With the exception of the last test series of the Rover program, Nuclear Furnace 1, test-reactor and rocket engine hydrogen gas exhaust generated during the Rover/NERVA program was released directly to the atmosphere, without removal of the associated fission products and other radioactive debris. Current rules for nuclear facilities (DOE Order 5480.6) are far more protective of the general environment; even with the remoteness of the Nevada Test Site, introduction of potentially hazardous quantities of radioactive waste into the atmosphere must be scrupulously avoided. The Rocketdyne treatment concept features a diffuser to provide altitude simulation and pressure recovery, a series of heat exchangers to gradually cool the exhaust gas stream to 100 K, and an activated charcoal bed for adsorption of inert gases. A hydrogen-gas fed ejector provides auxiliary pumping for startup and shutdown of the engine. Supplemental filtration to remove particulates and condensed phases may be added at appropriate locations in the system. The clean hydrogen may be exhausted to the atmosphere and flared, or the gas may be condensed and stored for reuse in testing. The latter approach totally isolates the working gas from the environment.

  3. GRI highlights underground gasification effort

    SciTech Connect (OSTI)

    Not Available

    1987-03-01T23:59:59.000Z

    A consortium headed by the Gas Research Institute is supporting major underground coal gasification tests to take place over the next two years at a site near Hanna, Wyoming. About 200 tons of coal will be gasified per day. Directional drilling will be used to form the horizontal gasification pathways linking the injection and production wells. The objectives of the program include a further evaluation of the controlled-retracting-injection-point technology. The technology involves the use of a device that is capable of igniting successive coal zones as it is retracted through a borehole in the coal seam. Comparable data will also be obtained during the test in sections where a linked-vertical-well concept will be used instead of the retracting-injection method. The linked-vertical-well concept, which has been used in most coal gasification tests, involves drilling a series of vertical wells into the coal seam gasification pathway for the ignition of successive coal zones. A parallel program will be conducted to evaluate environmental control technology applicable to underground coal gasification and to define the process requirements that must be satisfied to meet environmental quality standards. The results of these combined programs will provide the process and environmental data bases necessary to assess the economic potential of underground coal gasification from various US locations for a variety of end-product applications.

  4. Pyroprocessing of Fast Flux Test Facility Nuclear Fuel

    SciTech Connect (OSTI)

    B.R. Westphal; G.L. Fredrickson; G.G. Galbreth; D. Vaden; M.D. Elliott; J.C. Price; E.M. Honeyfield; M.N. Patterson; L. A. Wurth

    2013-10-01T23:59:59.000Z

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electrorefined uranium products exceeded 99%.

  5. Pyroprocessing of fast flux test facility nuclear fuel

    SciTech Connect (OSTI)

    Westphal, B.R.; Wurth, L.A.; Fredrickson, G.L.; Galbreth, G.G.; Vaden, D.; Elliott, M.D.; Price, J.C.; Honeyfield, E.M.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415 (United States)

    2013-07-01T23:59:59.000Z

    Used nuclear fuel from the Fast Flux Test Facility (FFTF) was recently transferred to the Idaho National Laboratory and processed by pyroprocessing in the Fuel Conditioning Facility. Approximately 213 kg of uranium from sodium-bonded metallic FFTF fuel was processed over a one year period with the equipment previously used for the processing of EBR-II used fuel. The peak burnup of the FFTF fuel ranged from 10 to 15 atom% for the 900+ chopped elements processed. Fifteen low-enriched uranium ingots were cast following the electrorefining and distillation operations to recover approximately 192 kg of uranium. A material balance on the primary fuel constituents, uranium and zirconium, during the FFTF campaign will be presented along with a brief description of operating parameters. Recoverable uranium during the pyroprocessing of FFTF nuclear fuel was greater than 95% while the purity of the final electro-refined uranium products exceeded 99%. (authors)

  6. Underground pumped hydroelectric storage

    SciTech Connect (OSTI)

    Allen, R.D.; Doherty, T.J.; Kannberg, L.D.

    1984-07-01T23:59:59.000Z

    Underground pumped hydroelectric energy storage was conceived as a modification of surface pumped storage to eliminate dependence upon fortuitous topography, provide higher hydraulic heads, and reduce environmental concerns. A UPHS plant offers substantial savings in investment cost over coal-fired cycling plants and savings in system production costs over gas turbines. Potential location near load centers lowers transmission costs and line losses. Environmental impact is less than that for a coal-fired cycling plant. The inherent benefits include those of all pumped storage (i.e., rapid load response, emergency capacity, improvement in efficiency as pumps improve, and capacity for voltage regulation). A UPHS plant would be powered by either a coal-fired or nuclear baseload plant. The economic capacity of a UPHS plant would be in the range of 1000 to 3000 MW. This storage level is compatible with the load-leveling requirements of a greater metropolitan area with population of 1 million or more. The technical feasibility of UPHS depends upon excavation of a subterranean powerhouse cavern and reservoir caverns within a competent, impervious rock formation, and upon selection of reliable and efficient turbomachinery - pump-turbines and motor-generators - all remotely operable.

  7. Office of Test and Evaluation | National Nuclear Security Administration

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeeding access toTest and Evaluation | National Nuclear Security

  8. Assessment of a hot hydrogen nuclear propulsion fuel test facility

    SciTech Connect (OSTI)

    Watanabe, H.H.; Howe, S.D.; Wantuck, P.J.

    1991-01-01T23:59:59.000Z

    Subsequent to the announcement of the Space Exploration Initiative (SEI), several studies and review groups have identified nuclear thermal propulsion as a high priority technology for development. To achieve the goals of SEI to place man on Mars, a nuclear rocket will operate at near 2700K and in a hydrogen environment at near 60 atmospheres. Under these conditions, the operational lifetime of the rocket will be limited by the corrosion rate at the hydrogen/fuel interface. Consequently, the Los Alamos National Laboratory has been evaluating requirements and design issues for a test facility. The facility will be able to directly heat fuel samples by electrical resistance, microwave deposition, or radio frequency induction heating to temperatures near 3000K. Hydrogen gas at variable pressure and temperatures will flow through the samples. The thermal gradients, power density, and operating times envisioned for nuclear rockets will be duplicated as close as reasonable. The post-sample flow stream will then be scrubbed and cooled before reprocessing. The baseline design and timetable for the facility will be discussed. 7 refs.

  9. Y-12 defense programs: Nuclear Packaging Systems testing capabilities

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    The Nuclear Packaging Systems (NPS) Department can manage/accomplish any packaging task. The NPS organization is responsible for managing the design, testing, certification, procurement, operation, refurbishment, maintenance, and disposal of packaging used to transport radioactive materials, other hazardous materials, and general cargoes on public roads and within the Oak Ridge Y-12 Plant. Additionally, the NPS Department has developed a Quality Assurance plan for all packaging, design and procurement of nonweapon shipping containers for radioactive materials, and design and procurement of performance-oriented packaging for hazardous materials. Further, the NPS Department is responsible for preparation and submittal of Safety Analysis Reports for Packaging (SARP). The NPS Department coordinates shipping container procurement and safety certification activities that have lead-times of up to two years. A Packaging Testing Capabilities Table at the Oak Ridge complex is included as a table.

  10. Addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 452: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 25-25-09, Spill H940825C (from UST 25-3101-1) • 25-25-14, Spill H940314E (from UST 25-3102-3) • 25-25-15, Spill H941020E (from UST 25-3152-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

  11. Addendum 2 to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Grant Evenson

    2009-05-01T23:59:59.000Z

    This document constitutes an addendum to the Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 454: Historical Underground Storage Tank Release Sites, Nevada Test Site, Nevada, April 1998 as described in the document Supplemental Investigation Report for FFACO Use Restrictions, Nevada Test Site, Nevada (SIR) dated November 2008. The SIR document was approved by NDEP on December 5, 2008. The approval of the SIR document constituted approval of each of the recommended UR removals. In conformance with the SIR document, this addendum consists of: • This page that refers the reader to the SIR document for additional information • The cover, title, and signature pages of the SIR document • The NDEP approval letter • The corresponding section of the SIR document This addendum provides the documentation justifying the cancellation of the URs for CASs: • 12-25-08, Spill H950524F (from UST 12-B-1) • 12-25-10, Spill H950919A (from UST 12-COMM-1) These URs were established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and were based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996). Since these URs were established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, these URs were re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006). This re-evaluation consisted of comparing the original data (used to define the need for the URs) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to remove these URs because contamination is not present at these sites above the risk-based FALs. Requirements for inspecting and maintaining these URs will be canceled, and the postings and signage at each site will be removed. Fencing and posting may be present at these sites that are unrelated to the FFACO URs such as for radiological control purposes as required by the NV/YMP Radiological Control Manual (NNSA/NSO, 2004). This modification will not affect or modify any non-FFACO requirements for fencing, posting, or monitoring at these sites.

  12. Underground Corrosion of Activated Metals, 6-Year Exposure Analysis

    SciTech Connect (OSTI)

    M. K. Adler Flitton; T. S. Yoder

    2006-03-01T23:59:59.000Z

    The subsurface radioactive disposal site located at the Idaho National Laboratory contains neutronactivated metals from non-fuel nuclear-reactor-core components. A long-term underground corrosion test is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in the surrounding arid vadose zone environment. The test uses nonradioactive metal coupons representing the prominent neutron-activated materials buried at the disposal location, namely, Type 304L stainless steel (UNS S30403), Type 316L stainless steel (S31603), nickel-chromium alloy (UNS NO7718), beryllium, aluminum 6061-T6 (A96061), and a zirconium alloy (UNS R60804). In addition, carbon steel (the material presently used in the cask disposal liners and other disposal containers) and a duplex stainless steel (UNS S32550) are also included in the test. This paper briefly describes the ongoing test and presents the results of corrosion analysis from coupons exposed underground for 1, 3, and 6 years.

  13. Underground coal gasification product quality parameters

    SciTech Connect (OSTI)

    Bruggink, P.R.; Davis, B.E.

    1981-01-01T23:59:59.000Z

    A simplified model is described which will indicate the economic value of the raw product gas from an experimental underground coal gasification test on a real-time basis in order to aid in the optimization of the process during the course of the test. The model relates the properties of the product gas and the injection gas to the cost of producing each of five potential commercial products. This model was utilized to evaluate data during the Gulf-DOE underground coal gasification test at Rawlins, Wyoming in the fall of 1981. 6 refs.

  14. Report to Congress on stockpile reliability, weapon remanufacture, and the role of nuclear testing

    SciTech Connect (OSTI)

    Miller, G.H.; Brown, P.S.; Alonso, C.T.

    1987-10-01T23:59:59.000Z

    This report analyzes two issues: (1) ''whether past warhead reliability problems demonstrate that nuclear explosive testing is needed to identify or to correct stockpile reliability,'' or (2) ''whether a program of stockpile inspection, nonnuclear testing, and remanufacture would be sufficient to deal with stockpile reliability problems.'' Chapter 1 examines the reasons for nuclear testing. Although the thrust of the request from Congressman Aspin et al., has to do with the need for nuclear testing as it relates to stockpile reliability and remanufacture, there are other very important reasons for nuclear testing. Since there has been increasing interest in the US Congress for more restrictive nuclear test limits, we have addressed the overall need for nuclear testing and the potential impact of further nuclear test limitations. Chapter 1 also summarizes the major conclusions of a recent study conducted by the Scientific and Academic Advisory Committee (SAAC) for the President of the University of California; the SAAC report is entitled, ''Nuclear Weapon Tests: The Role of the University of California-Department of Energy Laboratories.'' Chapter 2 presents a brief history of stockpile problems that involved post-deployment nuclear testing for their resolution. Chapter 3 addresses the problems involved in remanufacturing nuclear weapons, and Chapter 4 discusses measures that should be taken to prepare for possible future restrictive test limits.

  15. Ground Test Facility for Propulsion and Power Modes of Nuclear Engine Operation

    SciTech Connect (OSTI)

    Michael, WILLIAMS

    2004-11-22T23:59:59.000Z

    Existing DOE Ground Test Facilities have not been used to support nuclear propulsion testing since the Rover/NERVA programs of the 1960's. Unlike the Rover/NERVA programs, DOE Ground Test facilities for space exploration enabling nuclear technologies can no longer be vented to the open atmosphere. The optimal selection of DOE facilities and accompanying modifications for confinement and treatment of exhaust gases will permit the safe testing of NASA Nuclear Propulsion and Power devices involving variable size and source nuclear engines for NASA Jupiter Icy Moon Orbiter (JIMO) and Commercial Space Exploration Missions with minimal cost, schedule and environmental impact. NASA site selection criteria and testing requirements are presented.

  16. Radioxenon detections in the CTBT International Monitoring System likely related to the announced nuclear test in North Korea conducted on February 12, 2013

    SciTech Connect (OSTI)

    Ringbom, Anders; Axelssson, A.; Aldener, M.; Auer, M.; Bowyer, Ted W.; Fritioff, T.; Hoffman, Ian; Khrustalev, Kirill; Nikkinen, Mika; Popov, Vladimir Y.; Popov, Y.; Ungar, R. Kurt; Wotawa, G.

    2014-02-01T23:59:59.000Z

    Abstract: Observations of the radioxenon isotopes 133Xe and 131mXe collected at the IMS stations RN38 and RN58 on April 7-8, and April 12-13 2013, respectively, are unique with respect to the measurement history of these stations. Comparison of measured data with calculated isotopic ratios as well as analysis using atmospheric transport modeling indicate that it is likely that the xenon measured was created in the underground nuclear test conducted by North Korea on February 12, 2013, and released 7 weeks later. More than one release is required to explain all observations. The 131mXe source terms for each release were calculated to 7x1011 Bq, corresponding to about 1-10% of the total xenon inventory for a 10-kt explosion, depending on fractionation and release scenario. The observed ratios could not be used to obtain any information regarding the fissile material that was used in the test.

  17. Transient Testing of Nuclear Fuels and Materials in United States

    SciTech Connect (OSTI)

    Daniel M. Wachs

    2012-12-01T23:59:59.000Z

    The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation LWR fuel with enhanced performance and safety and reduced waste generation since 2010. This program, which has emphasized collaboration between the DOE, U.S. national laboratories and nuclear industry, was refocused from enhanced performance to enhanced accident tolerance following the events at Fukushima in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with standard UO2-Zircaloy, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022 .

  18. Bibliography of reports on studies of the geology, hydrogeology and hydrology at the Nevada Test Site, Nye County, Nevada, from 1951--1996

    SciTech Connect (OSTI)

    Seaber, P.R.; Stowers, E.D.; Pearl, R.H.

    1997-04-01T23:59:59.000Z

    The Nevada Test Site (NTS) was established in 1951 as a proving ground for nuclear weapons. The site had formerly been part of an Air Force bombing and gunnery range during World War II. Sponsor-directed studies of the geology, hydrogeology, and hydrology of the NTS began about 1956 and were broad based in nature, but were related mainly to the effects of the detonation of nuclear weapons. These effects included recommending acceptable media and areas for underground tests, the possibility of off-site contamination of groundwater, air blast and surface contamination in the event of venting, ground-shock damage that could result from underground blasts, and studies in support of drilling and emplacement. The studies were both of a pure scientific nature and of a practical applied nature. The NTS was the site of 828 underground nuclear tests and 100 above-ground tests conducted between 1951 and 1992 (U.S. Department of Energy, 1994a). After July 1962, all nuclear tests conducted in the United States were underground, most of them at the NTS. The first contained underground nuclear explosion was detonated on September 19, 1957, following extensive study of the underground effect of chemical explosives. The tests were performed by U.S. Department of Energy (DOE) and its predecessors, the U.S. Atomic Energy Commission and the Energy Research and Development Administration. As part of a nationwide complex for nuclear weapons design, testing and manufacturing, the NTS was the location for continental testing of new and stockpiled nuclear devices. Other tests, including Project {open_quotes}Plowshare{close_quotes} experiments to test the peaceful application of nuclear explosives, were conducted on several parts of the site. In addition, the Defense Nuclear Agency tested the effect of nuclear detonations on military hardware.

  19. Instrumented, Shielded Test Canister System for Evaluation of Spent Nuclear Fuel in Dry Storage

    SciTech Connect (OSTI)

    Sindelar, R.L.

    1999-10-21T23:59:59.000Z

    This document describes the development of an instrumented, shielded test canister system to store and monitor aluminum-based spent nuclear duel under dry storage conditions.

  20. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

  1. Mass balances for underground coal gasification in steeply dipping beds

    SciTech Connect (OSTI)

    Lindeman, R.; Ahner, P.; Davis, B.E.

    1980-01-01T23:59:59.000Z

    Two different mass balances were used during the recent underground coal gasification tests conducted in steeply dipping coal beds at Rawlins, Wyoming. The combination of both mass balances proved extremely useful in interpreting the test results. One mass balance which assumed char could be formed underground required the solution of 3 simultaneous equations. The assumption of no char decouples the 3 equations in the other mass balance. Both mass balance results are compared to the test data to provide an interpretation of the underground process.

  2. Underground Injection Control (West Virginia)

    Broader source: Energy.gov [DOE]

    This rule set forth criteria and standards for the requirements which apply to the State Underground Injection Control Program (U.I.C.). The UIC permit program regulates underground injections by...

  3. ORISE: Message Testing for a Nuclear Detonation | How ORISE is...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Security, Federal Emergency Management Agency, the Environmental Protection Agency, the Nuclear Regulatory Commission, Department of Energy, Department of Defense, Department of...

  4. Nuclear proliferation and testing: A tale of two treaties

    SciTech Connect (OSTI)

    Corden, Pierce S.; Hafemeister, David

    2014-04-01T23:59:59.000Z

    Despite progress in reducing stockpiles after the end of the Cold War, the disturbing actions of some nations could spread nuclear weapon capabilities and enlarge existing arsenals.

  5. Seismic reflection imaging of underground cavities using open-source software

    SciTech Connect (OSTI)

    Mellors, R J

    2011-12-20T23:59:59.000Z

    The Comprehensive Nuclear Test Ban Treaty (CTBT) includes provisions for an on-site inspection (OSI), which allows the use of specific techniques to detect underground anomalies including cavities and rubble zones. One permitted technique is active seismic surveys such as seismic refraction or reflection. The purpose of this report is to conduct some simple modeling to evaluate the potential use of seismic reflection in detecting cavities and to test the use of open-source software in modeling possible scenarios. It should be noted that OSI inspections are conducted under specific constraints regarding duration and logistics. These constraints are likely to significantly impact active seismic surveying, as a seismic survey typically requires considerable equipment, effort, and expertise. For the purposes of this study, which is a first-order feasibility study, these issues will not be considered. This report provides a brief description of the seismic reflection method along with some commonly used software packages. This is followed by an outline of a simple processing stream based on a synthetic model, along with results from a set of models representing underground cavities. A set of scripts used to generate the models are presented in an appendix. We do not consider detection of underground facilities in this work and the geologic setting used in these tests is an extremely simple one.

  6. Twelve Year Study of Underground Corrosion of Activated Metals

    SciTech Connect (OSTI)

    M. Kay Adler Flitton; Timothy S. Yoder

    2012-03-01T23:59:59.000Z

    The subsurface radioactive disposal facility located at the U.S. Department of Energy’s Idaho site contains neutron-activated metals from non-fuel nuclear-reactor-core components. A long-term corrosion study is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in an arid vadose zone environment. The study uses non-radioactive metal coupons representing the prominent neutron-activated material buried at the disposal location, namely, two types of stainless steels, welded stainless steel, welded nickel-chromium steel alloy, zirconium alloy, beryllium, and aluminum. Additionally, carbon steel (the material used in cask disposal liners and other disposal containers) and duplex stainless steel (high-integrity containers) are also included in the study. This paper briefly describes the test program and presents the corrosion rate results through twelve years of underground exposure.

  7. A perspective on atmospheric nuclear tests in Nevada: Fact Book, Revision 2

    SciTech Connect (OSTI)

    Friesen, H.N.

    1995-06-01T23:59:59.000Z

    This fact book provides historical background and perspective on the nuclear testing program at the Nevada Test Site (NTS). Nuclear tests contributing to the off-site deposition of radioactive fallout are identified, and the concept of cumulative estimated exposure is explained. The difficulty of associating health effects with radiation is presented also. The status of litigation against the government and legislation as of September 1994 are summarized.

  8. Hanford spent nuclear fuel hot conditioning system test procedure

    SciTech Connect (OSTI)

    Cleveland, K.J.

    1997-09-16T23:59:59.000Z

    This document provides the test procedures for cold testing of the prototype Hot Conditioning System (HCS) at the 306E Facility. The primary objective of this testing is to confirm design choices and provide data for the detailed design package prior to procurement of the process equipment. The current scope of testing in this document includes a fabricability study of the HCS, equipment performance testing of the HCS components, heat-up and cool-down cycle simulation, and robotic arm testing.

  9. Nuclear Detection and Sensor Testing Center | Y-12 National Security...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Sensor Testing Center, which offers dedicated facilities for the testing of radiation detection capabilities using enriched and highly enriched uranium. In addition to...

  10. Underground reactor containments: An option for the future?

    SciTech Connect (OSTI)

    Forsberg, C.W. [Oak Ridge National Lab., TN (United States). Chemical Technology Div.; Kress, T.

    1997-02-18T23:59:59.000Z

    Changing world conditions and changing technologies suggest that serious consideration should be given to siting of nuclear power plants underground. Underground siting is not a new concept. Multiple research reactors, several weapons production reactors, and one power reactor have been built underground. What is new are the technologies and incentives that may now make underground siting a preferred option. The conditions and technologies, along with their implications, are discussed herein. Underground containments can be constructed in mined cavities or pits that are then backfilled with thick layers of rock and soil. Conventional above-ground containments resist assaults and accidents because of the strength of their construction materials and the effectiveness of their safety features that are engineered to reduce loads. However, underground containments can provide even more resistance to assaults and accidents because of the inertia of the mass of materials over the reactor. High-technology weapons or some internal accidents can cause existing strong-material containments to fail, but only very-high energy releases can move large inertial masses associated with underground containments. New methods of isolation may provide a higher confidence in isolation that is independent of operator action.

  11. Hydrogeologic investigations at the Nevada Test Site

    SciTech Connect (OSTI)

    Hawkins, W L [Los Alamos National Lab., NM (United States)] [Los Alamos National Lab., NM (United States); Trudeau, D A [Geological Survey, Las Vegas, NV (United States)] [Geological Survey, Las Vegas, NV (United States); Drellack, S L [Raytheon Services Nevada, Inc., Mercury, NV (United States)] [Raytheon Services Nevada, Inc., Mercury, NV (United States)

    1992-01-01T23:59:59.000Z

    The Nevada Test Site was established in 1950 as a continental area for testing nuclear devices and, since 1963, all nuclear detonations there have been underground. Most tests are conducted in vertical shafts with a small percentage conducted in tunnels. The majority of detonation points are above the water table, primarily in volcanic rocks or alluvium. In the testing areas the water table is 450--700 m below the surface. Pre- and post- event geologic investigations are conducted for each test location and long-term studies assess the impact of underground testing on a more regional scale. Studies in progress have not identified any impact on the regional ground water system from testing, but some local effects have been recognized. In some areas where several large tests have been conducted below the water table, water levels hundreds of meters above the regional water table have been measured and radioactivity has been discovered associated with fractures in a few holes. Flow-through and straddle packer testing has revealed unexpectedly high hydraulic pressures at depth. Recently, a multiple completion monitoring well installed to study three zones has confirmed the existence of a significant upward hydraulic gradient. These observations of local pressurization and fracture flow are being further explored to determine the influence of underground nuclear testing on the regional hydrogeologic system.

  12. Underground waste barrier structure

    DOE Patents [OSTI]

    Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

    1988-01-01T23:59:59.000Z

    Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

  13. Construction of a Shallow Underground Low-background Detector for a CTBT Radionuclide Laboratory

    SciTech Connect (OSTI)

    Forrester, Joel B.; Greenwood, Lawrence R.; Miley, Harry S.; Myers, Allan W.; Overman, Cory T.

    2013-05-01T23:59:59.000Z

    The International Monitoring System (IMS) is a verification component of the Comprehensive Nuclear-Test-Ban Treaty (CTBT), and in addition to a series of radionuclide monitoring stations, contains sixteen radionuclide laboratories capable of verification of radionuclide station measurements. This paper presents an overview of a new commercially obtained low-background detector system for radionuclide aerosol measurements recently installed in a shallow (>30 meters water equivalent) underground clean-room facility at Pacific Northwest National Laboratory. Specifics such as low-background shielding materials, active shielding methods, and improvements in sensitivity to IMS isotopes will be covered.

  14. Underground and under scrutiny

    E-Print Network [OSTI]

    Lee, Leslie

    2014-01-01T23:59:59.000Z

    2 txH2O Summer 2014 Story by Leslie Lee The Frio River, located in the Texas Hill Country, is spring-fed and therefore affected by groundwater pumping. Photo from istock.com. Underground and under scrutiny A changing state increasingly... their geological features is more multifaceted. Consider that each aquifer in Texas has different geological and hydrological character- istics, and therefore varying recharge rates, water quality and regional needs, and the complexity heightens. From a legal...

  15. The Sanford Underground Research Facility at Homestake

    E-Print Network [OSTI]

    J. Heise

    2014-01-05T23:59:59.000Z

    The former Homestake gold mine in Lead, South Dakota is being transformed into a dedicated laboratory to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e) and currently hosts three projects: the LUX dark matter experiment, the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment and the CUBED low-background counter. Plans for possible future experiments at SURF are well underway and include long baseline neutrino oscillation experiments, future dark matter experiments as well as nuclear astrophysics accelerators. Facility upgrades to accommodate some of these future projects have already started. SURF is a dedicated facility with significant expansion capability.

  16. The Sanford underground research facility at Homestake

    SciTech Connect (OSTI)

    Heise, J. [Sanford Underground Research Facility, 630 East Summit Street, Lead, SD 57754 (United States)

    2014-06-24T23:59:59.000Z

    The former Homestake gold mine in Lead, South Dakota is being transformed into a dedicated laboratory to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e) and currently hosts three projects: the LUX dark matter experiment, the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment and the CUBED low-background counter. Plans for possible future experiments at SURF are well underway and include long baseline neutrino oscillation experiments, future dark matter experiments as well as nuclear astrophysics accelerators. Facility upgrades to accommodate some of these future projects have already started. SURF is a dedicated facility with significant expansion capability.

  17. United States Nuclear Tests, July 1945 through September 1992, December 2000

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    2000-12-01T23:59:59.000Z

    This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

  18. Y-12 builds capacity to meet nuclear testing schedule - Or: ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    support from Y-12. The test apparatus was essentially a uniquely designed thermonuclear test device, none of them were the same-all were unique designs. To keep pace with...

  19. Preliminary studies and tests of semiconductors for their use as nuclear radiation detectors

    E-Print Network [OSTI]

    Willis, Giles Whitehurst

    1960-01-01T23:59:59.000Z

    PRELIMINARY STUDIES AND TESTS OF SEMICONDUCTORS FOR THEIR USE AS NUCLEAR RADIATION DETECTORS A Thesis By Giles Whi tehurst Will is, Jr ~ Submitted to the Graduate School of the Agricultural and Mechanical College of Texas in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE January 1960 Major Subject: Electrical Engineering PRELIMINARY STUDIES AND TESTS OF SEMI CONDUCTORS FOR THEIR USE AS NUCLEAR RADIATION DETECTORS A Thesis By Giles Whitehurst Willi s& Jr ~ Approved...

  20. Closure report for underground storage tank 161-R1U1 and its associated underground piping

    SciTech Connect (OSTI)

    Mallon, B.J.; Blake, R.G.

    1994-05-01T23:59:59.000Z

    Underground storage tank (UST) 161-31 R at the Lawrence Livermore National Laboratory (LLNL) was registered with the State Water Resources Control Board on June 27, 1984. UST 161-31R was subsequently renamed UST 161-R1U1 (Fig. A-1, Appendix A). UST 161-R1U1 was installed in 1976, and had a capacity of 383 gallons. This tank system consisted of a fiberglass reinforced plastic tank, approximately 320 feet of polyvinyl chloride (PVC) underground piping from Building 161, and approximately 40 feet of PVC underground piping from Building 160. The underground piping connected laboratory drains and sinks inside Buildings 160 and 161 to UST 161-R1U1. The wastewater collected in UST 161-R1U1, contained organic solvents, metals, inorganic acids, and radionuclides, most of which was produced within Building 161. On June 28, 1989, the UST 161-R1U1 piping system.around the perimeter of Building 161 failed a precision test performed by Gary Peters Enterprises (Appendix B). The 161-R1U1 tank system was removed from service after the precision test. In July 1989, additional hydrostatic tests and helium leak detection tests were performed (Appendix B) to determine the locations of the piping failures in the Building 161 piping system. The locations of the piping system failures are shown in Figure A-2 (Appendix A). On July 11, 1989, LLNL submitted an Unauthorized Release Report to Alameda County Department of Environmental Health (ACDEH), Appendix C.

  1. ACCELERATED TESTING OF NEUTRON-ABSORBING ALLOYS FOR NUCLEAR CRITICALITY CONTROL

    SciTech Connect (OSTI)

    Ronald E. Mizia

    2011-10-01T23:59:59.000Z

    The US Department of Energy requires nuclear criticality control materials be used for storage of highly enriched spent nuclear fuel used in government programs and the storage of commercial spent nuclear fuel at the proposed High-Level Nuclear Waste Geological Repository located at Yucca Mountain, Nevada. Two different metallic alloys (Ni-Cr-Mo-Gd and borated stainless steel) have been chosen for this service. An accelerated corrosion test program to validate these materials for this application is described and a performance comparison is made.

  2. Underground Storage Tanks (New Jersey)

    Broader source: Energy.gov [DOE]

    This chapter constitutes rules for all underground storage tank facilities- including registration, reporting, permitting, certification, financial responsibility and to protect human health and...

  3. Underground Storage Tank Program (Vermont)

    Broader source: Energy.gov [DOE]

    These rules are intended to protect public health and the environment by establishing standards for the design, installation, operation, maintenance, monitoring, and closure of underground storage...

  4. Underground Injection Control Regulations (Kansas)

    Broader source: Energy.gov [DOE]

    This article prohibits injection of hazardous or radioactive wastes into or above an underground source of drinking water, establishes permit conditions and states regulations for design,...

  5. Underground Injection Control Rule (Vermont)

    Broader source: Energy.gov [DOE]

    This rule regulates injection wells, including wells used by generators of hazardous or radioactive wastes, disposal wells within an underground source of drinking water, recovery of geothermal...

  6. Sensitivity analysis for joint inversion of ground-penetrating radar and thermal-hydrological data from a large-scale underground heater test

    E-Print Network [OSTI]

    Kowalsky, M.B.; Birkholzer, J.; Peterson, J.; Finsterle, S.; Mukhopadhya y, S.; Tsang, Y.T.

    2008-01-01T23:59:59.000Z

    first step toward comprehensive inversion of the heater testfirst step toward a full inversion of the heater test data,

  7. Saving an Underground Reservoir 

    E-Print Network [OSTI]

    Wythe, Kathy

    2006-01-01T23:59:59.000Z

    significant part of the region?s agricultural economy. Though the area has few rivers and lakes, underneath it lies a supply of water that has provided groundwater for developing this economy. This underground water, the Ogallala Aquifer, is a finite... resource. The amount of water seeping back into the aquifer is much less than the water taken out, especially in the southern half of the aquifer, which spreads out from western Kansas to the High Plains of Texas. ?Water levels are declining 2 to 4...

  8. Underground coal gasification. Presentations

    SciTech Connect (OSTI)

    NONE

    2007-07-01T23:59:59.000Z

    The 8 presentations are: underground coal gasification (UCG) and the possibilities for carbon management (J. Friedmann); comparing the economics of UCG with surface gasification technologies (E. Redman); Eskom develops UCG technology project (C. Gross); development and future of UCG in the Asian region (L. Walker); economically developing vast deep Powder River Basin coals with UCG (S. Morzenti); effectively managing UCG environmental issues (E. Burton); demonstrating modelling complexity of environmental risk management; and UCG research at the University of Queensland, Australia (A.Y. Klimenko).

  9. The Sanford Underground Research Facility at Homestake

    E-Print Network [OSTI]

    Heise, Jaret

    2015-01-01T23:59:59.000Z

    The former Homestake gold mine in Lead, South Dakota has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low-background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-sea...

  10. The Sanford Underground Research Facility at Homestake

    E-Print Network [OSTI]

    Jaret Heise

    2015-03-05T23:59:59.000Z

    The former Homestake gold mine in Lead, South Dakota has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low-background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-search dark matter experiments and the Fermilab-led international long-baseline neutrino program. Planning to understand the infrastructure developments necessary to accommodate these future projects is well advanced and in some cases have already started. SURF is a dedicated research facility with significant expansion capability.

  11. Spent nuclear fuel storage -- Performance tests and demonstrations

    SciTech Connect (OSTI)

    McKinnon, M.A.; DeLoach, V.A.

    1993-04-01T23:59:59.000Z

    This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report.

  12. Depleted argon from underground sources

    SciTech Connect (OSTI)

    Back, H.O.; /Princeton U.; Alton, A.; /Augustana U. Coll.; Calaprice, F.; Galbiati, C.; Goretti, A.; /Princeton U.; Kendziora, C.; /Fermilab; Loer, B.; /Princeton U.; Montanari, D.; /Fermilab; Mosteiro, P.; /Princeton U.; Pordes, S.; /Fermilab

    2011-09-01T23:59:59.000Z

    Argon is a powerful scintillator and an excellent medium for detection of ionization. Its high discrimination power against minimum ionization tracks, in favor of selection of nuclear recoils, makes it an attractive medium for direct detection of WIMP dark matter. However, cosmogenic {sup 39}Ar contamination in atmospheric argon limits the size of liquid argon dark matter detectors due to pile-up. The cosmic ray shielding by the earth means that Argon from deep underground is depleted in {sup 39}Ar. In Cortez Colorado a CO{sub 2} well has been discovered to contain approximately 500ppm of argon as a contamination in the CO{sub 2}. In order to produce argon for dark matter detectors we first concentrate the argon locally to 3-5% in an Ar, N{sub 2}, and He mixture, from the CO{sub 2} through chromatographic gas separation. The N{sub 2} and He will be removed by continuous cryogenic distillation in the Cryogenic Distillation Column recently built at Fermilab. In this talk we will discuss the entire extraction and purification process; with emphasis on the recent commissioning and initial performance of the cryogenic distillation column purification.

  13. First Thermonuclear Device Successfully Tested | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA groupTubahq.na.gov Office ofDepartment ofr EEONuclearNuclear

  14. W88 warhead program performs successful tests | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14Russian Nuclear Warheads Arrives inAdministration W88

  15. Oregon Underground Injection Control Program Authorized Injection...

    Open Energy Info (EERE)

    Oregon Underground Injection Control Program Authorized Injection Systems Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Oregon Underground...

  16. WPCF Underground Injection Control Disposal Permit Evaluation...

    Open Energy Info (EERE)

    WPCF Underground Injection Control Disposal Permit Evaluation and Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: WPCF Underground Injection...

  17. Underground Storage Tank Act (West Virginia)

    Broader source: Energy.gov [DOE]

    New underground storage tank construction standards must include at least the following requirements: (1) That an underground storage tank will prevent releases of regulated substances stored...

  18. Georgia Underground Storage Tank Act (Georgia)

    Broader source: Energy.gov [DOE]

    The Georgia Underground Storage Act (GUST) provides a comprehensive program to prevent, detect, and correct releases from underground storage tanks (“USTs”) of “regulated substances” other than...

  19. Preliminary Notice of Violation, Pacific Underground Construction...

    Broader source: Energy.gov (indexed) [DOE]

    Pacific Underground Construction, Inc. - WEA-2009-02 Preliminary Notice of Violation, Pacific Underground Construction, Inc. - WEA-2009-02 April 7, 2009 Issued to Pacific...

  20. Uncertainties associated with the definition of a hydrologic source term for the Nevada Test Site

    SciTech Connect (OSTI)

    Smith, D.K.; Esser, B.K. [Lawrence Livermore National Lab., CA (United States); Thompson, J.L. [Los Alamos National Lab., NM (United States)

    1995-05-01T23:59:59.000Z

    The U.S. Department of Energy, Nevada Operations Office (DOE/NV) Environmental Restoration Division is seeking to evaluate groundwater contamination resulting from 30 years of underground nuclear testing at the Nevada Test Site (NTS). This evaluation requires knowledge about what radioactive materials are in the groundwater and how they are transported through the underground environment. This information coupled with models of groundwater flow (flow paths and flow rates) will enable predictions of the arrival of each radionuclide at a selected receptor site. Risk assessment models will then be used to calculate the expected environmental and human doses. The accuracy of our predictions depends on the validity of our hydrologic and risk assessment models and on the quality of the data for radionuclide concentrations in ground water at each underground nuclear test site. This paper summarizes what we currently know about radioactive material in NTS groundwater and suggests how we can best use our limited knowledge to proceed with initial modeling efforts. The amount of a radionuclide available for transport in groundwater at the site of an underground nuclear test is called the hydrologic source term. The radiologic source term is the total amount of residual radionuclides remaining after an underground nuclear test. The hydrologic source term is smaller than the radiologic source term because some or most of the radionuclide residual cannot be transported by groundwater. The radiologic source term has been determined for each of the underground nuclear tests fired at the NTS; however, the hydrologic source term has been estimated from measurements at only a few sites.

  1. Plowshare Program - American Atomic Bomb Tests For Industrial Applications

    SciTech Connect (OSTI)

    None

    2012-04-22T23:59:59.000Z

    The United States Atomic Energy Commission (AEC) established the Plowshare Program as a research and development activity to explore the technical and economic feasibility of using nuclear explosives for industrial applications. The reasoning was that the relatively inexpensive energy available from nuclear explosions could prove useful for a wide variety of peaceful purposes. The Plowshare Program began in 1958 and continued through 1975. Between December 1961 and May 1973, the United States conducted 27 Plowshare nuclear explosive tests comprising 35 individual detonations. Conceptually, industrial applications resulting from the use of nuclear explosives could be divided into two broad categories: 1) large-scale excavation and quarrying, where the energy from the explosion was used to break up and/or move rock; and 2) underground engineering, where the energy released from deeply buried nuclear explosives increased the permeability and porosity of the rock by massive breaking and fracturing. Possible excavation applications included: canals, harbors, highway and railroad cuts through mountains, open pit mining, construction of dams, and other quarry and construction-related projects. Underground nuclear explosion applications included: stimulation of natural gas production, preparation of leachable ore bodies for in situ leaching, creation of underground zones of fractured oil shale for in situ retorting, and formation of underground natural gas and petroleum storage reservoirs.

  2. Integral Benchmark Data for Nuclear Data Testing Through the ICSBEP & IRPhEP

    SciTech Connect (OSTI)

    J. Blair Briggs; John D. Bess; Jim Gulliford; Ian Hill

    2013-10-01T23:59:59.000Z

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiment Evaluation Project (IRPhEP) was last discussed directly with the nuclear data community at ND2007. Since ND2007, integral benchmark data that are available for nuclear data testing have increased significantly. The status of the ICSBEP and the IRPhEP is discussed and selected benchmark configurations that have been added to the ICSBEP and IRPhEP Handbooks since ND2007 are highlighted.

  3. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    SciTech Connect (OSTI)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L. (comps.)

    1982-08-01T23:59:59.000Z

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

  4. Geosphere in underground coal gasification

    SciTech Connect (OSTI)

    Daly, D.J.; Groenewold, G.H.; Schmit, C.R.; Evans, J.M.

    1988-07-01T23:59:59.000Z

    The feasibility of underground coal gasification (UCG), the in-situ conversion of coal to natural gas, has been demonstrated through 28 tests in the US alone, mainly in low-rank coals, since the early 1970s. Further, UCG is currently entering the commercial phase in the US with a planned facility in Wyoming for the production of ammonia-urea from UCG-generated natural gas. Although the UCG process both affects and is affected by the natural setting, the majority of the test efforts have historically been focused on characterizing those aspects of the natural setting with the potential to affect the burn. With the advent of environmental legislation, this focus broadened to include the potential impacts of the process on the environment (e.g., subsidence, degradation of ground water quality). Experience to date has resulted in the growing recognition that consideration of the geosphere is fundamental to the design of efficient, economical, and environmentally acceptable UCG facilities. The ongoing RM-1 test program near Hanna, Wyoming, sponsored by the US Department of Energy and an industry consortium led by the Gas Research Institute, reflects this growing awareness through a multidisciplinary research effort, involving geoscientists and engineers, which includes (1) detailed geological site characterization, (2) geotechnical, hydrogeological, and geochemical characterization and predictive modeling, and (3) a strategy for ground water protection. Continued progress toward commercialization of the UCG process requires the integration of geological and process-test information in order to identify and address the potentially adverse environmental ramifications of the process, while identifying and using site characteristics that have the potential to benefit the process and minimize adverse impacts.

  5. Senate Rejects Test Ban Treaty | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved: 5-13-14 FEDERALAmerica HighSTARTOperations /Senate Rejects Test Ban

  6. Underground coal gasification: A near-term alternate fuel

    SciTech Connect (OSTI)

    Avasthi, J.; Singleton, A.M.

    1984-06-01T23:59:59.000Z

    Since the beginning of this century underground coal gasification has been considered as an alternative to mining as a means of utilizing the coal resources not recoverable by conventional methods. The energy crunch of the seventies gave a new impetus to it, and several tests were conducted in the U.S. to demonstrate the feasibility of this method in both horizontal and steeply dipping coal resources. Gulf Research and Development Company has conducted two successful underground coal gasification tests near Rawlins, Wyoming, in steeply dipping coal beds. The results of these tests indicate that the present state of the art is advanced enough for utilization of this technique for commercial purposes. A right combination of resource, consumer, and economic factors will dictate future commercialization of underground coal gasification for the U.S. coal resources.

  7. Water intrusion in underground structures

    E-Print Network [OSTI]

    Nazarchuk, Alex

    2008-01-01T23:59:59.000Z

    This thesis presents a study of the permissible groundwater infiltration rates in underground structures, the consequences of this leakage and the effectiveness of mitigation measures. Design guides and codes do not restrict, ...

  8. Pumping carbon out of underground coal deposits

    SciTech Connect (OSTI)

    Steinberg, M.

    1999-07-01T23:59:59.000Z

    Thin steam and deep coal deposits are difficult and costly to mine. Underground coal gasification (UCG) with air or oxygen was thought to alleviate this problem. Experimental field tests were conducted in Wyoming and Illinois. Problems were encountered concerning a clear path for the team gasification to take place and removal of gas. The high endothermic heat of reaction requiring large quantities of steam and oxygen makes the process expensive. Safety problems due to incomplete reaction is also of concern. A new approach is proposed which can remedy most of these drawbacks for extracting energy from underground coal deposits. It is proposed to hydrogasify the coal underground with a heated hydrogen gas stream under pressure to produce a methane-rich gas effluent stream. The hydrogasification of coal is essentially exothermic so that no steam or oxygen is required. The gases formed are always in a reducing atmosphere making the process safe. The hydrogen is obtained by thermally decomposing the effluent methane above ground to elemental carbon and hydrogen. The hydrogen is returned underground for further hydrogasification of the coal seam. The small amount of oxygen and sulfur in the coal can be processed out above ground by removal as water and H{sub 2}S. Any CO can be removed by a methanation step returning the methane to process. The ash remains in the ground and the elemental carbon produced is the purest form of coal. The particulate carbon can be slurried with water to produce a fuel stream that can be fed to a turbine for efficient combined cycle power plants with lower CO{sub 2} emissions. Coal cannot be used for combined cycle because of its ash and sulfur content destroys the gas turbine. Depending on its composition of coal seam some excess hydrogen is also produced. Hydrogen is, thus, used to pump pure carbon out of the ground.

  9. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    1999-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

  10. Underground caverns for hydrocarbon storage

    SciTech Connect (OSTI)

    Barron, T.F. [Exeter Energy Services, Houston, TX (United States)

    1998-12-31T23:59:59.000Z

    Large, international gas processing projects and growing LPG imports in developing countries are driving the need to store large quantities of hydrocarbon liquids. Even though underground storage is common in the US, many people outside the domestic industry are not familiar with the technology and the benefits underground storage can offer. The latter include lower construction and operating costs than surface storage, added safety, security and greater environmental acceptance.

  11. Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

    SciTech Connect (OSTI)

    Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge Northridge, CA 91330 (United States)

    2012-07-01T23:59:59.000Z

    Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National Laboratories, the 1980's regulatory and demonstration testing of MAGNOX fuel flasks in the United Kingdom (the CEGB 'Operation Smash Hit' tests), and the 1980's regulatory drop and fire tests conducted on the TRUPACT II containers used for transuranic waste shipments to the Waste Isolation Pilot Plant in New Mexico. The primary focus of the paper is a detailed evaluation of the cask testing programs proposed by the NRC in its decision implementing staff recommendations based on the Package Performance Study, and by the State of Nevada recommendations based on previous work by Audin, Resnikoff, Dilger, Halstead, and Greiner. The NRC approach is based on demonstration impact testing (locomotive strike) of a large rail cask, either the TAD cask proposed by DOE for spent fuel shipments to Yucca Mountain, or a similar currently licensed dual-purpose cask. The NRC program might also be expanded to include fire testing of a legal-weight truck cask. The Nevada approach calls for a minimum of two tests: regulatory testing (impact, fire, puncture, immersion) of a rail cask, and extra-regulatory fire testing of a legal-weight truck cask, based on the cask performance modeling work by Greiner. The paper concludes with a discussion of key procedural elements - test costs and funding sources, development of testing protocols, selection of testing facilities, and test peer review - and various methods of communicating the test results to a broad range of stakeholder audiences. (authors)

  12. Hydrogen loops in existing reactors for testing fuel elements for nuclear propulsion

    SciTech Connect (OSTI)

    Olsen, C.S.; Welland, H.; Abraschoff, J. (Idaho National Engineering Laboratory, EG G Idaho Inc., P.O. Box 1625, Idaho Falls, Idaho 83415 (United States)); Thoms, K. (Oak Ridge National Laboratory, P.O. Box, Oak Ridge, Tennessee 37831-8087 (United States))

    1993-01-15T23:59:59.000Z

    The Space Exploration Initiative (SEI) has revitalized interest in adapting nuclear energy for power and propulsion. Prior to the selection of a nuclear thermal propulsion (NTP) system, extensive testing of the various proposed concepts will be required. In today's environmental, safety and health culture, full size rocket engine tests as were done under the Rover/NERVA program will be extremely difficult and expensive to perform and meet NASA's schedules. A different test strategy uses a hydrogen loop in an existing reactor to test a wide variety of single elements or clusters of elements for fuel qualification. This approach is expected to reduce operating and capital costs and expedite the testing schedule. This paper examines the potential of performing subscale tests in a hydrogen loop in an existing reactor such as the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory or the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory. The HFIR is expected to achieve power densities comparable to those achieved in ATR because of the 85 MWt power level and the high thermal and fast flux levels. The available length and diameter of the test region of FHIR are 60 cm and 10 cm whereas the available length and diameter of the test region of ATR are 120 cm and 12 cm respectively.

  13. Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options.

    SciTech Connect (OSTI)

    Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J. (Idaho National Laboratory, Idaho Falls, ID); Parma, Edward J., Jr.; Peters, Curtis D.; Vernon, Milton E.; Pickard, Paul S.

    2007-10-01T23:59:59.000Z

    The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents.

  14. Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo

    E-Print Network [OSTI]

    Shlyakhter, Ilya

    Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo Natural Reactor #3; Alexander I. Shlyakhter November 18, 1982 1 Introduction The following eight quantities enter the important natural constants of cosmology and atomic theory are connected by simple mathematical relations

  15. Ground Testing a Nuclear Thermal Rocket: Design of a sub-scale demonstration experiment

    SciTech Connect (OSTI)

    David Bedsun; Debra Lee; Margaret Townsend; Clay A. Cooper; Jennifer Chapman; Ronald Samborsky; Mel Bulman; Daniel Brasuell; Stanley K. Borowski

    2012-07-01T23:59:59.000Z

    In 2008, the NASA Mars Architecture Team found that the Nuclear Thermal Rocket (NTR) was the preferred propulsion system out of all the combinations of chemical propulsion, solar electric, nuclear electric, aerobrake, and NTR studied. Recently, the National Research Council committee reviewing the NASA Technology Roadmaps recommended the NTR as one of the top 16 technologies that should be pursued by NASA. One of the main issues with developing a NTR for future missions is the ability to economically test the full system on the ground. In the late 1990s, the Sub-surface Active Filtering of Exhaust (SAFE) concept was first proposed by Howe as a method to test NTRs at full power and full duration. The concept relied on firing the NTR into one of the test holes at the Nevada Test Site which had been constructed to test nuclear weapons. In 2011, the cost of testing a NTR and the cost of performing a proof of concept experiment were evaluated.

  16. Development of High Fidelity, Fuel-Like Thermal Simulators for Non-Nuclear Testing

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon M.; Dickens, Ricky; Adams, Mike; Davis, Joe [NASA Marshall Space Flight Center, Nuclear Systems Branch/ER24, MSFC, AL 25812 (United States); Dixon, David [Los Alamos National Laboratory, Decision Applications Division, Los Alamos, NM 87545 (United States); North Carolina State University, Raleigh, NC (United States); Kapernick, Richard [Los Alamos National Laboratory, Decision Applications Division, Los Alamos, NM 87545 (United States)

    2007-01-30T23:59:59.000Z

    Non-nuclear testing can be a valuable tool in the development of a space nuclear power or propulsion system. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Work at the NASA Marshall Space Flight Center seeks to develop high fidelity thermal simulators that not only match the static power profile that would be observed in an operating, fueled nuclear reactor, but also match the dynamic fuel pin performance during feasible transients. Comparison between the fuel pins and thermal simulators is made at the outer fuel clad surface, which corresponds to the outer sheath surface in the thermal simulator. The thermal simulators that are currently being developed are designed to meet the geometric and power requirements of a proposed surface power reactor design, accommodate testing of various axial power profiles, and incorporate imbedded instrumentation. Static and dynamic fuel pin performances for a proposed reactor design have been determined using SINDA/FLUINT thermal analysis software, and initial comparison has been made between the expected nuclear performance and the performance of conceptual thermal simulator designs. Through a series of iterative analysis, a conceptual high fidelity design will be developed, followed by engineering design, fabrication, and testing to validate the overall design process. Although the resulting thermal simulator will be designed for a specific reactor concept, establishing this rigorous design process will assist in streamlining the thermal simulator development for other reactor concepts. This paper presents the current status of high fidelity thermal simulator design relative to a SNAP derivative reactor design that could be applied for Lunar surface power.

  17. Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and yield strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

  18. Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests

    SciTech Connect (OSTI)

    Wilson, C.N.

    1990-06-01T23:59:59.000Z

    The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85{degree}C and 25{degree}C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments with artificially defected cladding and water-tight end fittings, and an undefected fuel rod section with watertight end fittings. Periodic solution samples were taken during test cycles with the sample volumes replenished with fresh J-13 water. Test cycles were periodically terminated and the specimens restarted in fresh J-13 water. The specimens were run for three cycles for a total test duration of 15 months. 22 refs., 32 figs., 26 tabs.

  19. Underground Coal Thermal Treatment

    SciTech Connect (OSTI)

    P. Smith; M. Deo; E. Eddings; A. Sarofim; K. Gueishen; M. Hradisky; K. Kelly; P. Mandalaparty; H. Zhang

    2011-10-30T23:59:59.000Z

    The long-term objective of this work is to develop a transformational energy production technology by insitu thermal treatment of a coal seam for the production of substitute natural gas (SNG) while leaving much of the coalâ??s carbon in the ground. This process converts coal to a high-efficiency, low-GHG emitting gas fuel. It holds the potential of providing environmentally acceptable access to previously unusable coal resources. This topical report discusses the development of experimental capabilities, the collection of available data, and the development of simulation tools to obtain process thermo-chemical and geo-thermal parameters in preparation for the eventual demonstration in a coal seam. It also includes experimental and modeling studies of CO{sub 2} sequestration. Efforts focused on: â?˘ Constructing a suite of three different coal pyrolysis reactors. These reactors offer the ability to gather heat transfer, mass transfer and kinetic data during coal pyrolysis under conditions that mimic in situ conditions (Subtask 6.1). â?˘ Studying the operational parameters for various underground thermal treatment processes for oil shale and coal and completing a design matrix analysis for the underground coal thermal treatment (UCTT). This analysis yielded recommendations for terms of targeted coal rank, well orientation, rubblization, presence of oxygen, temperature, pressure, and heating sources (Subtask 6.2). â?˘ Developing capabilities for simulating UCTT, including modifying the geometry as well as the solution algorithm to achieve long simulation times in a rubblized coal bed by resolving the convective channels occurring in the representative domain (Subtask 6.3). â?˘ Studying the reactive behavior of carbon dioxide (CO{sub 2}) with limestone, sandstone, arkose (a more complex sandstone) and peridotite, including mineralogical changes and brine chemistry for the different initial rock compositions (Subtask 6.4). Arkose exhibited the highest tendency of participating in mineral reactions, which can be attributed to the geochemical complexity of its initial mineral assemblage. In experiments with limestone, continuous dissolution was observed with the release of CO{sub 2} gas, indicated by the increasing pressure in the reactor (formation of a gas chamber). This occurred due to the lack of any source of alkali to buffer the solution. Arkose has the geochemical complexity for permanent sequestration of CO{sub 2} as carbonates and is also relatively abundant. The effect of including NH{sub 3} in the injected gas stream was also investigated in this study. Precipitation of calcite and trace amounts of ammonium zeolites was observed. A batch geochemical model was developed using Geochemists Workbench (GWB). Degassing effect in the experiments was corrected using the sliding fugacity model in GWB. Experimental and simulation results were compared and a reasonable agreement between the two was observed.

  20. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    SciTech Connect (OSTI)

    Michael Kruzic

    2007-09-01T23:59:59.000Z

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D&D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release.

  1. Development of a test system for verification and validation of nuclear transport simulations

    SciTech Connect (OSTI)

    White, Morgan C [Los Alamos National Laboratory; Triplett, Brian S [GENERAL ELECTRIC; Anghaie, Samim [UNIV OF FL

    2008-01-01T23:59:59.000Z

    Verification and validation of nuclear data is critical to the accuracy of both stochastic and deterministic particle transport codes. In order to effectively test a set of nuclear data, the data must be applied to a wide variety of transport problems. Performing this task in a timely, efficient manner is tedious. The nuclear data team at Los Alamos National laboratory in collaboration with the University of Florida has developed a methodology to automate the process of nuclear data verification and validation (V and V). This automated V and V process can efficiently test a number of data libraries using well defined benchmark experiments, such as those in the International Criticality Safety Benchmark Experiment Project (ICSBEP). The process is implemented through an integrated set of Pyton scripts. Material and geometry data are read from an existing medium or given directly by the user to generate a benchmark experiment template file. The user specifies the choice of benchmark templates, codes, and libraries to form a V and V project. The Python scripts generate input decks for multiple transport codes from the templates, run and monitor individual jobs, and parse the relevant output automatically. The output can then be used to generate reports directly or can be stored into a database for later analysis. This methodology eases the burden on the user by reducing the amount of time and effort required for obtaining and compiling calculation results. The resource savings by using this automated methodology could potentially be an enabling technology for more sophisticated data studies, such as nuclear data uncertainty quantification. Once deployed, this tool will allow the nuclear data community to more thoroughly test data libraries leading to higher fidelity data in the future.

  2. Flow characteristics in underground coal gasification

    SciTech Connect (OSTI)

    Chang, H.L.; Himmelblau, D.M.; Edgar, T.F.

    1982-01-01T23:59:59.000Z

    During the underground coal gasification field test at the Hoe Creek site No. 2, Wyoming, helium pulses were introduced to develop information to characterize the flow field, and to estimate the coefficients in dispersion models of the flow. Quantitative analysis of the tracer response curves shows an increasing departure from a plug flow regime with time because of the combined effects of the free and forced convection in addition to the complex non-uniformity of the flow field. The Peclet number was a function of temperature, pressure, gas recovery and characteristic velocity, as well as the split of the gas between the parallel streams in the model. 17 refs.

  3. Full-Scale Accident Testing in Support of Used Nuclear Fuel Transportation.

    SciTech Connect (OSTI)

    Durbin, Samuel G.; Lindgren, Eric R.; Rechard, Rob P.; Sorenson, Ken B.

    2014-09-01T23:59:59.000Z

    The safe transport of spent nuclear fuel and high-level radioactive waste is an important aspect of the waste management system of the United States. The Nuclear Regulatory Commission (NRC) currently certifies spent nuclear fuel rail cask designs based primarily on numerical modeling of hypothetical accident conditions augmented with some small scale testing. However, NRC initiated a Package Performance Study (PPS) in 2001 to examine the response of full-scale rail casks in extreme transportation accidents. The objectives of PPS were to demonstrate the safety of transportation casks and to provide high-fidelity data for validating the modeling. Although work on the PPS eventually stopped, the Blue Ribbon Commission on America’s Nuclear Future recommended in 2012 that the test plans be re-examined. This recommendation was in recognition of substantial public feedback calling for a full-scale severe accident test of a rail cask to verify evaluations by NRC, which find that risk from the transport of spent fuel in certified casks is extremely low. This report, which serves as the re-assessment, provides a summary of the history of the PPS planning, identifies the objectives and technical issues that drove the scope of the PPS, and presents a possible path for moving forward in planning to conduct a full-scale cask test. Because full-scale testing is expensive, the value of such testing on public perceptions and public acceptance is important. Consequently, the path forward starts with a public perception component followed by two additional components: accident simulation and first responder training. The proposed path forward presents a series of study options with several points where the package performance study could be redirected if warranted.

  4. Electronic constant current and current pulse signal generator for nuclear instrumentation testing

    DOE Patents [OSTI]

    Brown, Roger A. (Amsterdam, NY)

    1994-01-01T23:59:59.000Z

    Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

  5. Electronic constant current and current pulse signal generator for nuclear instrumentation testing

    DOE Patents [OSTI]

    Brown, R.A.

    1994-04-19T23:59:59.000Z

    Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

  6. Phase II Transport Model of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

    SciTech Connect (OSTI)

    Gregg Ruskuaff

    2010-01-01T23:59:59.000Z

    This document, the Phase II Frenchman Flat transport report, presents the results of radionuclide transport simulations that incorporate groundwater radionuclide transport model statistical and structural uncertainty, and lead to forecasts of the contaminant boundary (CB) for a set of representative models from an ensemble of possible models. This work, as described in the Federal Facility Agreement and Consent Order (FFACO) Underground Test Area (UGTA) strategy (FFACO, 1996; amended 2010), forms an essential part of the technical basis for subsequent negotiation of the compliance boundary of the Frenchman Flat corrective action unit (CAU) by Nevada Division of Environmental Protection (NDEP) and National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Underground nuclear testing via deep vertical shafts was conducted at the Nevada Test Site (NTS) from 1951 until 1992. The Frenchman Flat area, the subject of this report, was used for seven years, with 10 underground nuclear tests being conducted. The U.S. Department of Energy (DOE), NNSA/NSO initiated the UGTA Project to assess and evaluate the effects of underground nuclear tests on groundwater at the NTS and vicinity through the FFACO (1996, amended 2010). The processes that will be used to complete UGTA corrective actions are described in the “Corrective Action Strategy” in the FFACO Appendix VI, Revision No. 2 (February 20, 2008).

  7. Hanna, Wyoming underground coal gasification data base. Volume 1. General information and executive summary

    SciTech Connect (OSTI)

    Bartke, T.C.; Fischer, D.D.; King, S.B.; Boyd, R.M.; Humphrey, A.E.

    1985-08-01T23:59:59.000Z

    This report is part of a seven-volume series on the Hanna, Wyoming, underground coal gasification field tests. Volume 1 is a summary of the project and each of Volumes 2 through 6 describes a particular test. Volume 7 is a compilation. This report covers: (1) history of underground coal gasification leading to the Hanna tests; (2) area characteristics (basic meteorological and socioeconomic data); (3) site selection history; (4) site characteristics; (5) permitting; and (6) executive summary. 5 figs., 15 tabs.

  8. Implications of atmospheric test fallout data for nuclear winter. Doctoral thesis

    SciTech Connect (OSTI)

    Baker, G.H.

    1987-02-01T23:59:59.000Z

    Atmospheric-test fallout data were used to determine admissible dust-particle size distributions for nuclear winter studies. The research was originally motivated by extreme differences noted in the magnitude and longevity of dust effects predicted by particle-size distributions routinely used in fallout predictions versus those used for nuclear-winter studies. Three different sets of historical data were analyzed: 1) Stratospheric burden of strontium-90 and tungsten-185, 1954-1967 (97 contributing events); 2) Continental U.S strontium-90 fallout through 1958 (75 contributing events); and 3) Local Fallout from selected Nevada tests (16 events). The contribution of dust to possible long-term climate effects following a nuclear exchange depends strongly on the particle-size distribution. The distribution affects both the atmospheric residence time and optical depth. One-dimensional models of stratospheric/tropospheric fallout removal were developed and used to identify optimum particle distributions. Results indicate that particle distributions which properly predict bulk stratospheric activity transfer tend to be somewhat smaller than number size distributions used in initial nuclear winter studies.

  9. Underground storage tank 511-D1U1 closure plan

    SciTech Connect (OSTI)

    Mancieri, S.; Giuntoli, N.

    1993-09-01T23:59:59.000Z

    This document contains the closure plan for diesel fuel underground storage tank 511-D1U1 and appendices containing supplemental information such as staff training certification and task summaries. Precision tank test data, a site health and safety plan, and material safety data sheets are also included.

  10. Recommended Underground Test Area Activity Reference Documents

    National Nuclear Security Administration (NNSA)

    Site, Nevada, DOENV--478-Rev. 1, July 1999. (15033) o Addendum, CAIP for CAU98, June, 2001, DOENV-478, Rev.1-ADD (789217) o Corrective Action Investigation Plan for Corrective...

  11. Recommended Underground Test Area Activity Reference Documents

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilAElectronic Input Options Gary L. Hirsch SNL 2001a,Summary; i-C C1

  12. Spent nuclear fuel retrieval system fuel handling development testing. Final report

    SciTech Connect (OSTI)

    Jackson, D.R.; Meeuwsen, P.V.

    1997-09-01T23:59:59.000Z

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin, clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge), remove the contents from the canisters and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. This report describes fuel handling development testing performed from May 1, 1997 through the end of August 1997. Testing during this period was mainly focused on performance of a Schilling Robotic Systems` Conan manipulator used to simulate a custom designed version, labeled Konan, being fabricated for K-Basin deployment. In addition to the manipulator, the camera viewing system, process table layout, and fuel handling processes were evaluated. The Conan test manipulator was installed and fully functional for testing in early 1997. Formal testing began May 1. The purposes of fuel handling development testing were to provide proof of concept and criteria, optimize equipment layout, initialize the process definition, and identify special needs/tools and required design changes to support development of the performance specification. The test program was set up to accomplish these objectives through cold (non-radiological) development testing using simulated and prototype equipment.

  13. Nevada National Security Site Nuclear Testing Artifacts Become Part of U.S. Cultural Archive

    Broader source: Energy.gov [DOE]

    LAS VEGAS – The Nevada National Security Site’s (NNSS) historic Smoky site may soon join a long list of former nuclear testing locations eligible for inclusion in the National Register of Historic Places. The Desert Research Institute (DRI) is currently working alongside the Nevada Site Office (NSO) to determine the eligibility of Smoky and a number of other EM sites slated for cleanup and closure.

  14. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

    SciTech Connect (OSTI)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01T23:59:59.000Z

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form.

  15. Underground Storage Tanks: New Fuels and Compatibility

    Broader source: Energy.gov [DOE]

    Breakout Session 1C—Fostering Technology Adoption I: Building the Market for Renewables with High Octane Fuels Underground Storage Tanks: New Fuels and Compatibility Ryan Haerer, Program Analyst, Alternative Fuels, Office of Underground Storage Tanks, Environmental Protection Agency

  16. Closure report for underground storage tank 141-R3U1 and its associated underground piping

    SciTech Connect (OSTI)

    Mallon, B.J.; Blake, R.G.

    1994-03-01T23:59:59.000Z

    Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks.

  17. Lead test assembly irradiation and analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) needs to confirm the viability of using a commercial light water reactor (CLWR) as a potential source for maintaining the nation`s supply of tritium. The Proposed Action discussed in this environmental assessment is a limited scale confirmatory test that would provide DOE with information needed to assess that option. This document contains the environmental assessment results for the Lead test assembly irradiation and analysis for the Watts Bar Nuclear Plant, Tennessee, and the Hanford Site in Richland, Washington.

  18. A study of small explosions and earthquakes during 1961--1989 near the Semipalatinsk Test Site, Kazakhstan

    SciTech Connect (OSTI)

    Khalturin, V.I.; Rautian, T.G. [Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Physics of the Earth; Richards, P.G. [Lamont-Doherty Earth Observatory, Palisades, NY (United States)]|[Columbia Univ., New York, NY (United States). Dept. of Geological Sciences

    1994-03-01T23:59:59.000Z

    Several Russian sources have stated that 343 underground nuclear explosions were conducted during 1961--1989 at the Semipalatinsk Test Site. However, only 282 of them appear to have been described, in the openly available technical literature, with well-determined coordinates; and only 272 have both good locations and magnitudes. The authors have used regional data from 52 stations to study 65 seismic sources initially thought to be in or near the Semipalatinsk region, additional to the 272 underground nuclear explosions with known locations and magnitudes. Of these 65 events, the authors believe 8 are not explosions on the test site, namely: two earthquakes close to the test site; three earthquakes or chemical explosions 100--300 km from the test site; and three events at greater distances from Semipalatinsk. Of the remaining 57 events: 10 were known to be underground nuclear explosions with known locations and the authors have supplied magnitudes where none were previously available; one was a chemical explosion at Degelen; they believe 21 were underground nuclear explosions; 13 were chemical explosions at Balapan; 8 were chemical explosions elsewhere on the test site; three were either nuclear or chemical explosions; and one was either a chemical explosion or a cavity collapse. The largest magnitude of their 44 possible underground nuclear explosions is around 5 (February 4, 1965, obscured at many teleseismic stations by a large Aleutian earthquake). Others lie in the magnitude range 3.5--4.5, and clearly most have sub kiloton yields. Their data set of small events is important for purposes of evaluating the detection capability of teleseismic arrays, and the detection and identification capability of regional stations.

  19. Seismic signals from underground cavity collapses and other mining-related failures

    SciTech Connect (OSTI)

    Walter, W.R.; Heuze, F.; Dodge, D.

    1997-07-01T23:59:59.000Z

    The sudden collapse of man-made underground cavities have generated seismic signals as large as magnitude 5.4. Collapses are just one of the many types of mining associated seismicity including coalbumps and rockbursts which need to be identified and distinguished from potential clandestine nuclear explosions under the recently signed Comprehensive Test Ban Treaty (CTBT). Collapses, coalbumps and rockbursts are of concern for seismically monitoring a CTBT for a number of reasons. First, they can look like explosions when using some seismic discriminant measures, such M{sub s}:m{sub b}, M{sub o}: m{sub b}, regional P/S ratios and depth. Second, underground nuclear explosions themselves produce cavities that might collapse, possibly aiding in the detection of a clandestine event. Finally, because all mine-related events occur in the vicinity of underground cavities, they may come under special scrutiny because of the concern that very large, specially constructed cavities could be used to evasively decouple a clandestine test. For these reasons mine-related seismicity in both active and former mining regions have the potential to be false alarms under a CTBT. We are investigating techniques to identify collapses, either directly via waveform modeling, or indirectly by combining several seismic discriminants. We are also investigating the source mechanisms of coalbumps and collapses to better understand the performance of seismic discriminants for these events. In particular we have found similarities in point source models of some longwall coalbumps, room- and-pillar mine collapses and NTS nuclear explosion cavity collapses. In order to understand coalbumps we are analyzing events from central Utah recorded at regional distances in Utah and Nevada including at the auxiliary station ELK. Some of these have anomalous, explosion- like high frequency P/S ratios. We are combining this new study with results from previous field work done in 1995 at a Colorado long-wall coal mining operation. Similarly to longwall coal mines in Utah and elsewhere, this Colorado mine completely excavates a 3m high coal seam in 250 m wide panels leaving the material above unsupported. The roof material above the excavated seam eventually collapses resulting in seismic events.

  20. TSUAHXETSUAHXE UndergroUnd tank

    E-Print Network [OSTI]

    Schladow, S. Geoffrey

    USer waterheatexchange waterheatexchange general exhaUSt lab exhaUSt warmairexhaUSt radiant panel heat radiant panel heat by night air, then stored underground. cold water travels through floors and ceiling panels to absorb heat rain and snowmelt in toilets saves water and reduces stormwater runoff photovoltaic panels turn solar

  1. High Temperature Superconducting Underground Cable

    SciTech Connect (OSTI)

    Farrell, Roger, A.

    2010-02-28T23:59:59.000Z

    The purpose of this Project was to design, build, install and demonstrate the technical feasibility of an underground high temperature superconducting (HTS) power cable installed between two utility substations. In the first phase two HTS cables, 320 m and 30 m in length, were constructed using 1st generation BSCCO wire. The two 34.5 kV, 800 Arms, 48 MVA sections were connected together using a superconducting joint in an underground vault. In the second phase the 30 m BSCCO cable was replaced by one constructed with 2nd generation YBCO wire. 2nd generation wire is needed for commercialization because of inherent cost and performance benefits. Primary objectives of the Project were to build and operate an HTS cable system which demonstrates significant progress towards commercial progress and addresses real world utility concerns such as installation, maintenance, reliability and compatibility with the existing grid. Four key technical areas addressed were the HTS cable and terminations (where the cable connects to the grid), cryogenic refrigeration system, underground cable-to-cable joint (needed for replacement of cable sections) and cost-effective 2nd generation HTS wire. This was the world’s first installation and operation of an HTS cable underground, between two utility substations as well as the first to demonstrate a cable-to-cable joint, remote monitoring system and 2nd generation HTS.

  2. EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho

    Broader source: Energy.gov [DOE]

    This Environmental Assessment (EA) evaluates U.S. Department of Energy (DOE) activities associated with its proposal to resume testing of nuclear fuels and materials under transient high-power test conditions at the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory. The State of Idaho and Shoshone-Bannock Tribes are cooperating agencies.

  3. Containment and Analysis Capability Insights Gained from Drop Testing Representative Spent Nuclear Fuel Containers

    SciTech Connect (OSTI)

    Morton, Dana Keith; Snow, Spencer David; Rahl, Tommy Ervin; Ware, Arthur Gates

    2001-08-01T23:59:59.000Z

    The National Spent Nuclear Fuel Program (NSNFP), operating from the Idaho National Engineering and Environmental Laboratory (INEEL), developed the standardized Department of Energy (DOE) spent nuclear fuel (SNF) canister. This canister is designed to be loaded with DOE SNF (including other radioactive materials) and then be used during interim storage, during transportation to the nation’s repository, and for final disposal at the repository without having to be reopened. The canister has been fully designed and has completed significant testing that clearly demonstrates that it can safely achieve its intended design goals. During 1999, nine 457-mm diameter test canisters were fabricated at the INEEL to represent the standardized DOE SNF canister design. Various "worst case" internals were incorporated. Seven of the test canisters were 4.57 m long and weighed approximately 2721 kg, while two were 3.00 m long and weighed approximately 1360 kg and 1725 kg. Seven of the test canisters were dropped from 9 m onto an essentially unyielding flat surface and one of the test canisters was dropped from 1 m onto a 15-cm diameter puncture post. The final test canister was dropped from 61 cm onto a 50.8 mm thick vertically oriented steel plate, and then fell over to impact another 50.8 mm thick vertically oriented steel plate. This last test represented a canister dropping onto another larger container such as a repository disposal container or waste package. The 1999 drop testing was performed at Sandia National Laboratories (SNL). The nine test canisters experienced varying degrees of damage to their skirts, lifting rings, and pressure boundary components (heads and main body). However, all of the canisters were shown to have maintained their pressure boundary (through pressure testing). Four heavily damaged canisters were also shown to be leaktight via helium leak testing. Pre- and post-drop finite element (FE) analyses were also performed. The results clearly indicated that accurate predictions of canister responses to the drop tests were achieved. The results achieved for the standardized canister can also be applicable to other well-constructed containers (canisters, casks, cans, vessels, etc.) subjected to similar loads. Properly designed containers can maintain a containment system after being subjected to dynamically induced high strains and FE computer analyses can accurately predict the resulting responses.

  4. Uranium Enrichment Standards of the Y-12 Nuclear Detection and Sensor Testing Center

    SciTech Connect (OSTI)

    Cantrell, J.

    2012-05-23T23:59:59.000Z

    The Y-12 National Security Complex has recently fabricated and characterized a new series of metallic uranium standards for use in the Nuclear Detection and Sensor Testing Center (NDSTC). Ten uranium metal disks with enrichments varying from 0.2 to 93.2% {sup 235}U were designed to provide researchers access to a wide variety of measurement scenarios in a single testing venue. Special care was taken in the selection of the enrichments in order to closely bracket the definitions of reactor fuel at 4% {sup 235}U and that of highly enriched uranium (HEU) at 20% {sup 235}U. Each standard is well characterized using analytical chemistry as well as a series of gamma-ray spectrometry measurements. Gamma-ray spectra of these standards are being archived in a reference library for use by customers of the NDSTC. A software database tool has been created that allows for easier access and comparison of various spectra. Information provided through the database includes: raw count data (including background spectra), regions of interest (ROIs), and full width half maximum calculations. Input is being sought from the user community on future needs including enhancements to the spectral database and additional Uranium standards, shielding configurations and detector types. A related presentation are planned for the INMM 53rd Annual Meeting (Hull, et al.), which describe new uranium chemical compound standards and testing opportunities at Y-12 Nuclear Detection and Sensor Testing Center (NDSTC).

  5. Fundamental investigations of underground coal gasification. Final report, March 1982-December 1986

    SciTech Connect (OSTI)

    Gunn, R.D.

    1987-08-01T23:59:59.000Z

    The report presents several mathematical models of underground coal-gasification processes. Through these models, a much better theoretical understanding of underground coal gasification becomes possible. Specific phenomena studied were the effects of high-amplitude pressure oscillation, reverse combustion, spontaneous ignition at high pressures, an analytical model of reverse-combustion channeling, an exploratory study of electrolinking, cavity-growth behavior, and a technical evaluation of the Forestburg underground coal-gasification field test at Forestburg, Alberta. This test is especially interesting because the site was escavated after completion of the experiment.

  6. Validation Analysis of the Groundwater Flow and Transport Model of the Central Nevada Test Area

    SciTech Connect (OSTI)

    A. Hassan; J. Chapman; H. Bekhit; B. Lyles; K. Pohlmann

    2006-09-30T23:59:59.000Z

    The Central Nevada Test Area (CNTA) is a U.S. Department of Energy (DOE) site undergoing environmental restoration. The CNTA is located about 95 km northeast of Tonopah, Nevada, and 175 km southwest of Ely, Nevada (Figure 1.1). It was the site of the Faultless underground nuclear test conducted by the U.S. Atomic Energy Commission (DOE's predecessor agency) in January 1968. The purposes of this test were to gauge the seismic effects of a relatively large, high-yield detonation completed in Hot Creek Valley (outside the Nevada Test Site [NTS]) and to determine the suitability of the site for future large detonations. The yield of the Faultless underground nuclear test was between 200 kilotons and 1 megaton (DOE, 2000). A three-dimensional flow and transport model was created for the CNTA site (Pohlmann et al., 1999) and determined acceptable by DOE and the Nevada Division of Environmental Protection (NDEP) for predicting contaminant boundaries for the site.

  7. Nuclear fuels technologies Fiscal Year 1996 research and development test results

    SciTech Connect (OSTI)

    Beard, C.A.; Blair, H.T.; Buksa, J.J.; Butt, D.P.; Chidester, K.; Eaton, S.L.; Farish, T.J.; Hanrahan, R.J.; Ramsey, K.B.

    1996-11-01T23:59:59.000Z

    During fiscal year 1996, the Department of Energy`s Office of Fissile Materials Disposition (OFMD) funded Los Alamos National Laboratory (LANL) to investigate issues associated with the fabrication of plutonium from dismantled weapons into mixed-oxide (MOX) nuclear fuel for disposition in nuclear power reactors. These issues can be divided into two main categories: issues associated with the fact that the plutonium from dismantled weapons contains gallium, and issues associated with the unique characteristics of the PuO[sub 2] produced by the dry conversion process that OFMD is proposing to convert the weapons material. Initial descriptions of the experimental work performed in fiscal year 1996 to address these issues can be found in Nuclear Fuels Technologies Fiscal Year 1996 Research and Development Test Matrices. However, in some instances the change in programmatic emphasis towards the Parallex program either altered the manner in which some of these experiments were performed (i.e., the work was done as part of the Parallex fabrication development and not as individual separate-effects tests as originally envisioned) or delayed the experiments into Fiscal Year 1997. This report reviews the experiments that were conducted and presents the results.

  8. CALMOS: Innovative device for the measurement of nuclear heating in material testing reactors

    SciTech Connect (OSTI)

    Carcreff, H. [Alternative Energies and Atomic Energy Commission CEA, Saclay Center, DEN/DANS/DRSN/SIREN, Gif Sur Yvette, 91191 (France)

    2011-07-01T23:59:59.000Z

    An R and D program has been carried out since 2002 in order to improve gamma heating measurements in the 70 MWth OSIRIS Material Testing Reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. Throughout this program an innovative calorimetric probe associated to a specific handling system has been designed in order to make measurements both along the fissile height and on the upper part of the core, where nuclear heating rates still remain high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for the process validation, while a displacement system has been especially designed to move the probe axially. A final probe has been designed thanks to modeling results and to preliminary measurements obtained with mock-ups irradiated to a heating level of 2W/g, This paper gives an overview of the development, describes the calorimetric probe, and expected advantages such as the possibility to use complementary methods to get the nuclear heating measurement. Results obtained with mock-ups irradiated in ex-core area of the reactor are presented and discussed. (authors)

  9. Nuclear Data Performance Testing Using Sensitive, but Less Frequently Used ICSBEP Benchmarks

    SciTech Connect (OSTI)

    J. Blair Briggs; John D. Bess

    2011-08-01T23:59:59.000Z

    The International Criticality Safety Benchmark Evaluation Project (ICSBEP) has published the International Handbook of Evaluated Criticality Safety Benchmark Experiments annually since 1995. The Handbook now spans over 51,000 pages with benchmark specifications for 4,283 critical, near critical, or subcritical configurations; 24 criticality alarm placement/shielding configurations with multiple dose points for each; and 200 configurations that have been categorized as fundamental physics measurements relevant to criticality safety applications. Benchmark data in the ICSBEP Handbook were originally intended for validation of criticality safety methods and data; however, the benchmark specifications are now used extensively for nuclear data testing. There are several, less frequently used benchmarks within the Handbook that are very sensitive to thorium and certain key structural and moderating materials. Calculated results for many of those benchmarks using modern nuclear data libraries suggest there is still room for improvement. These and other highly sensitive, but rarely quoted benchmarks are highlighted and data testing results provided using the Monte Carlo N-Particle Version 5 (MCNP5) code and continuous energy ENDF/B-V, VI.8, and VII.0, JEFF-3.1, and JENDL-3.3 nuclear data libraries.

  10. Underground coal gasification using oxygen and steam

    SciTech Connect (OSTI)

    Yang, L.H.; Zhang, X.; Liu, S. [China University of Mining & Technology, Xuzhou (China)

    2009-07-01T23:59:59.000Z

    In this paper, through model experiment of the underground coal gasification, the effects of pure oxygen gasification, oxygen-steam gasification, and moving-point gasification methods on the underground gasification process and gas quality were studied. Experiments showed that H{sub 2} and CO volume fraction in product gas during the pure oxygen gasification was 23.63-30.24% and 35.22-46.32%, respectively, with the gas heating value exceeding 11.00 MJ/m{sup 3}; under the oxygen-steam gasification, when the steam/oxygen ratio stood at 2: 1, gas compositions remained virtually stable and CO + H{sub 2} was basically between 61.66 and 71.29%. Moving-point gasification could effectively improve the changes in the cavity in the coal seams or the effects of roof inbreak on gas quality; the ratio of gas flowing quantity to oxygen supplying quantity was between 3.1:1 and 3.5:1 and took on the linear changes; on the basis of the test data, the reasons for gas quality changes under different gasification conditions were analyzed.

  11. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2011-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

  12. Establishment and testing of a whole body counter for the Texas A&M Nuclear Science Center 

    E-Print Network [OSTI]

    Baca, Bernadette Doris

    1997-01-01T23:59:59.000Z

    The establishment and testing of a whole body counter would benefit the Texas A&M Nuclear Science Center (NSC) Health Physics staff and workers by allowing better assessment of a worker's internal exposure. Presently NSC ...

  13. TEST SYSTEM FOR EVALUATING SPENT NUCLEAR FUEL BENDING STIFFNESS AND VIBRATION INTEGRITY

    SciTech Connect (OSTI)

    Wang, Jy-An John [ORNL] [ORNL; Wang, Hong [ORNL] [ORNL; Bevard, Bruce Balkcom [ORNL] [ORNL; Howard, Rob L [ORNL] [ORNL; Flanagan, Michelle [U.S. Nuclear Regulatory Commission] [U.S. Nuclear Regulatory Commission

    2013-01-01T23:59:59.000Z

    Transportation packages for spent nuclear fuel (SNF) must meet safety requirements specified by federal regulations. For normal conditions of transport, vibration loads incident to transport must be considered. This is particularly relevant for high-burnup fuel (>45 GWd/MTU). As the burnup of the fuel increases, a number of changes occur that may affect the performance of the fuel and cladding in storage and during transportation. The mechanical properties of high-burnup de-fueled cladding have been previously studied by subjecting defueled cladding tubes to longitudinal (axial) tensile tests, ring-stretch tests, ring-compression tests, and biaxial tube burst tests. The objective of this study is to investigate the mechanical properties and behavior of both the cladding and the fuel in it under vibration/cyclic loads similar to the sustained vibration loads experienced during normal transport. The vibration loads to SNF rods during transportation can be characterized by dynamic, cyclic, bending loads. The transient vibration signals in a specified transport environment can be analyzed, and frequency, amplitude and phase components can be identified. The methodology being implemented is a novel approach to study the vibration integrity of actual SNF rod segments through testing and evaluating the fatigue performance of SNF rods at defined frequencies. Oak Ridge National Laboratory (ORNL) has developed a bending fatigue system to evaluate the response of the SNF rods to vibration loads. A three-point deflection measurement technique using linear variable differential transformers is used to characterize the bending rod curvature, and electromagnetic force linear motors are used as the driving system for mechanical loading. ORNL plans to use the test system in a hot cell for SNF vibration testing on high burnup, irradiated fuel to evaluate the pellet-clad interaction and bonding on the effective lifetime of fuel-clad structure bending fatigue performance. Technical challenges include pure bending implementation, remote installation and detachment of the SNF test specimen, test specimen deformation measurement, and identification of a driving system suitable for use in a hot cell. Surrogate test specimens have been used to calibrate the test setup and conduct systematic cyclic tests. The calibration and systematic cyclic tests have been used to identify test protocol issues prior to implementation in the hot cell. In addition, cyclic hardening in unidirectional bending and softening in reverse bending were observed in the surrogate test specimens. The interface bonding between the surrogate clad and pellets was found to impact the bending response of the surrogate rods; confirming this behavior in the actual spent fuel segments will be an important aspect of the hot cell test implementation,

  14. Interim report spent nuclear fuel retrieval system fuel handling development testing

    SciTech Connect (OSTI)

    Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

    1997-06-01T23:59:59.000Z

    Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

  15. Offsite environmental monitoring report; radiation monitoring around United States nuclear test areas, Calendar Year 1996

    SciTech Connect (OSTI)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Huff, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1997-08-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs). No nuclear weapons testing was conducted in 1996 due to the continuing nuclear test moratorium. During this period, R and IE personnel maintained readiness capability to provide direct monitoring support if testing were to be resumed and ascertained compliance with applicable EPA, DOE, state, and federal regulations and guidelines. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no airborne radioactivity from diffusion or resuspension detected by the various EPA monitoring networks surrounding the NTS. There was no indication of potential migration of radioactivity to the offsite area through groundwater and no radiation exposure above natural background was received by the offsite population. All evaluated data were consistent with previous data history.

  16. CONTROL TESTING OF THE UK NATIONAL NUCLEAR LABORATORY'S RADBALL TECHNOLOGY AT SAVANNAH RIVER NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Farfan, E.

    2009-11-23T23:59:59.000Z

    The UK National Nuclear Laboratory (NNL) has developed a remote, non-electrical, radiation-mapping device known as RadBall (patent pending), which offers a means to locate and quantify radiation hazards and sources within contaminated areas of the nuclear industry. To date, the RadBall has been deployed in a number of technology trials in nuclear waste reprocessing plants at Sellafield in the UK. The trials have demonstrated the successful ability of the RadBall technology to be deployed and retrieved from active areas. The positive results from these initial deployment trials and the anticipated future potential of RadBall have led to the NNL partnering with the Savannah River National Laboratory (SRNL) to further underpin and strengthen the technical performance of the technology. RadBall consists of a colander-like outer shell that houses a radiation-sensitive polymer sphere. It has no power requirements and can be positioned in tight or hard-to reach places. The outer shell works to collimate radiation sources and those areas of the polymer sphere that are exposed react, becoming increasingly less transparent, in proportion to the absorbed dose. The polymer sphere is imaged in an optical-CT scanner which produces a high resolution 3D map of optical attenuation coefficients. Subsequent analysis of the optical attenuation maps provides information on the spatial distribution and strength of the sources in a given area forming a 3D characterization of the area of interest. This study completed at SRNL addresses key aspects of the testing of the RadBall technology. The first set of tests was performed at Savannah River Nuclear Solutions Health Physics Instrument Calibration Laboratory (HPICL) using various gamma-ray sources and an x-ray machine with known radiological characteristics. The objective of these preliminary tests was to identify the optimal dose and collimator thickness. The second set of tests involved a highly contaminated hot cell. The objective of this part of the testing was to characterize a hot cell with unknown radiation sources. The RadBall calibration experiments and hot cell deployment completed at SRNL were successful in that for each trial, the technology was able to locate the radiation sources. The NNL believe that the ability of RadBall to be remotely deployed with no electrical supplies into difficult to access areas of plant and locate and quantify radiation hazards is a unique radiation mapping service. The NNL consider there to be significant business potential associated with this innovative technology.

  17. Radiochemical data collected on events from which radioactivity escaped beyond the borders of the Nevada test range complex. [NONE

    SciTech Connect (OSTI)

    Hicks, H.G.

    1981-02-12T23:59:59.000Z

    This report identifies all nuclear events in Nevada that are known to have sent radioactivity beyond the borders of the test range complex. There have been 177 such tests, representing seven different types: nuclear detonations in the atmosphere, nuclear excavation events, nuclear safety events, underground nuclear events that inadvertently seeped or vented to the atmosphere, dispersion of plutonium and/or uranium by chemical high explosives, nuclear rocket engine tests, and nuclear ramjet engine tests. The source term for each of these events is given, together with the data base from which it was derived (except where the data are classified). The computer programs used for organizing and processing the data base and calculating radionuclide production are described and included, together with the input and output data and details of the calculations. This is the basic formation needed to make computer modeling studies of the fallout from any of these 177 events.

  18. Testing nuclear parton distributions with pA collisions at the LHC

    E-Print Network [OSTI]

    Paloma Quiroga-Arias; Jose Guilherme Milhano; Urs Achin Wiedemann

    2010-02-12T23:59:59.000Z

    Global perturbative QCD analyses, based on large data sets from electron-proton and hadron collider experiments, provide tight constraints on the parton distribution function (PDF) in the proton. The extension of these analyses to nuclear parton distributions (nPDF) has attracted much interest in recent years. nPDFs are needed as benchmarks for the characterization of hot QCD matter in nucleus-nucleus collisions, and attract further interest since they may show novel signatures of non-linear density-dependent QCD evolution. However, it is not known from first principles whether the factorization of long-range phenomena into process-independent parton distribution, which underlies global PDF extractions for the proton, extends to nuclear effects. As a consequence, assessing the reliability of nPDFs for benchmark calculations goes beyond testing the numerical accuracy of their extraction and requires phenomenological tests of the factorization assumption. Here we argue that a proton-nucleus collision program at the LHC would provide a set of measurements allowing for unprecedented tests of the factorization assumption underlying global nPDF fits.

  19. Testing collinear factorization and nuclear parton distributions with pA collisions at the LHC

    E-Print Network [OSTI]

    Paloma Quiroga-Arias; Jose Guilherme Milhano; Urs Achim Wiedemann

    2010-10-07T23:59:59.000Z

    Global perturbative QCD analyses, based on large data sets from electron-proton and hadron collider experiments, provide tight constraints on the parton distribution function (PDF) in the proton. The extension of these analyses to nuclear parton distributions (nPDF) has attracted much interest in recent years. nPDFs are needed as benchmarks for the characterization of hot QCD matter in nucleus-nucleus collisions, and attract further interest since they may show novel signatures of non- linear density-dependent QCD evolution. However, it is not known from first principles whether the factorization of long-range phenomena into process-independent parton distribution, which underlies global PDF extractions for the proton, extends to nuclear effects. As a consequence, assessing the reliability of nPDFs for benchmark calculations goes beyond testing the numerical accuracy of their extraction and requires phenomenological tests of the factorization assumption. Here we argue that a proton-nucleus collision program at the LHC would provide a set of measurements allowing for unprecedented tests of the factorization assumption underlying global nPDF fits.

  20. Experimental results from pressure testing a 1:6-scale nuclear power plant containment

    SciTech Connect (OSTI)

    Horschel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1992-01-01T23:59:59.000Z

    This report discusses the testing of a 1:6-scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over 1200 transducers to prepare for the test. The containment model was tested to failure to determine its response to static internal overpressurization. As part of the US Nuclear Regulatory Commission`s program on containment integrity, the test results will be used to assess the capability of analytical methods to predict the performance of containments under severe-accident loads. The scaled dimensions of the cylindrical wall and hemispherical dome were typical of a full-size containment. Other typical features included in the heavily reinforced model were equipment hatches, personnel air locks, several small piping penetrations, and a ihin steel liner that was attached to the concrete by headed studs. In addition to the transducers attached to the model, an acoustic detection system and several video and still cameras were used during testing to gather data and to aid in the conduct of the test. The model and its instrumentation are briefly discussed, and is followed by the testing procedures and measured response of the containment model. A summary discussion is included to aid in understanding the significance of the test as it applies to real world reinforced concrete containment structures. The data gathered during SIT and overpressure testing are included as an appendix.

  1. Acoustic emission monitoring of hot functional testing: Watts Bar Unit 1 Nuclear Reactor

    SciTech Connect (OSTI)

    Hutton, P.H.; Dawson, J.F.; Friesel, M.A.; Harris, J.C.; Pappas, R.A.

    1984-06-01T23:59:59.000Z

    Acoustic emission (AE) monitoring of selected pressure boundary areas at TVA's Watts Bar, Unit 1 Nuclear Power Plant during hot functional preservice testing is described in this report. The report deals with background, methodology, and results. The work discussed here is a major milestone in a program supported by NRC to develop and demonstrate application of AE monitoring for continuous surveillance of reactor pressure boundaries to detect and evaluate growing flaws. The subject work demonstrated that anticipated problem areas can be overcome. Work is continuing toward AE monitoring during reactor operation.

  2. Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

    SciTech Connect (OSTI)

    Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

    1982-03-01T23:59:59.000Z

    Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

  3. The Advanced Test Reactor National Scientific User Facility Advancing Nuclear Technology

    SciTech Connect (OSTI)

    T. R. Allen; J. B. Benson; J. A. Foster; F. M. Marshall; M. K. Meyer; M. C. Thelen

    2009-05-01T23:59:59.000Z

    To help ensure the long-term viability of nuclear energy through a robust and sustained research and development effort, the U.S. Department of Energy (DOE) designated the Advanced Test Reactor and associated post-irradiation examination facilities a National Scientific User Facility (ATR NSUF), allowing broader access to nuclear energy researchers. The mission of the ATR NSUF is to provide access to world-class nuclear research facilities, thereby facilitating the advancement of nuclear science and technology. The ATR NSUF seeks to create an engaged academic and industrial user community that routinely conducts reactor-based research. Cost free access to the ATR and PIE facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to DOE mission. Extensive publication of research results is expected as a condition for access. During FY 2008, the first full year of ATR NSUF operation, five university-led experiments were awarded access to the ATR and associated post-irradiation examination facilities. The ATR NSUF has awarded four new experiments in early FY 2009, and anticipates awarding additional experiments in the fall of 2009 as the results of the second 2009 proposal call. As the ATR NSUF program mature over the next two years, the capability to perform irradiation research of increasing complexity will become available. These capabilities include instrumented irradiation experiments and post-irradiation examinations on materials previously irradiated in U.S. reactor material test programs. The ATR critical facility will also be made available to researchers. An important component of the ATR NSUF an education program focused on the reactor-based tools available for resolving nuclear science and technology issues. The ATR NSUF provides education programs including a summer short course, internships, faculty-student team projects and faculty/staff exchanges. In June of 2008, the first week-long ATR NSUF Summer Session was attended by 68 students, university faculty and industry representatives. The Summer Session featured presentations by 19 technical experts from across the country and covered topics including irradiation damage mechanisms, degradation of reactor materials, LWR and gas reactor fuels, and non-destructive evaluation. High impact research results from leveraging the entire research infrastructure, including universities, industry, small business, and the national laboratories. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. Current partner facilities include the MIT Reactor, the University of Michigan Irradiated Materials Testing Laboratory, the University of Wisconsin Characterization Laboratory, and the University of Nevada, Las Vegas transmission Electron Microscope User Facility. Needs for irradiation of material specimens at tightly controlled temperatures are being met by dedication of a large in-pile pressurized water loop facility for use by ATR NSUF users. Several environmental mechanical testing systems are under construction to determine crack growth rates and fracture toughness on irradiated test systems.

  4. Abstract--An all-day tour to observe arid land reclamation on the Nevada Test Site was conducted in conjunction with the

    E-Print Network [OSTI]

    of Energy must study and characterize Yucca Mountain, Nevada, as a potential site for long-term underground storage of high- level nuclear waste. Site characterization activities include a variety of geo- logical Reclamation On the Nevada Test Site--A Field Tour Von K. Winkel W. Kent Ostler In: Roundy, Bruce A.; Mc

  5. Rocky Mountain 1 Underground Coal Gasification Project

    SciTech Connect (OSTI)

    Not Available

    1992-03-01T23:59:59.000Z

    The Rocky Mountain 1 Underground Coal Gasification Test or Burn was conducted from approximately mid-November, 1987 through February, 1988. After the burn the project began proceeding with the following overall tasks: venting, flushing and cooling of the cavities; subsurface or groundwater cleanup; post-burn coring and drilling; groundwater monitoring, and site restoration/reclamation. By the beginning of 1991 field activities associated with venting, flushing and cooling of the cavities and post-burn coring and drilling had been completed. However, data analysis continued including the University of North Dakota analyzing drilling and coring data, and the US Department of Energy (DOE)/EG G developing a chronological listing of project events.

  6. Flow characteristics in underground coal gasification

    SciTech Connect (OSTI)

    Chang, H.L.; Himmelblau, D.M.; Edgar, T.F.

    1982-01-01T23:59:59.000Z

    During the Hoe Creek No. 2 (Wyoming) underground-coal-gasification field test, researchers introduced helium pulses to characterize the flow field and to estimate the coefficients in dispersion models of the flow. Flow models such as the axial-dispersion and parallel tanks-in-series models allowed interpretation of the in situ combustion flow field from the residence time distribution of the tracer gas. A quantitative analysis of the Hoe Creek tracer response curves revealed an increasing departure from a plug-flow regime with time, which was due to the combined effects of the free and forced convection in addition to the complex nonuniformity of the flow field. The Peclet number was a function of temperature, pressure, gas recovery, and characteristic velocity, as well as the split of the gas between the parallel streams in the model.

  7. SPACE-R nuclear power system TFE mock-up SC-320 demonstration test

    SciTech Connect (OSTI)

    Nikolaev, Y.V.; Eremin, S.A.; Kolesov, V.S.; Lapochkin, N.V.; Izhvanov, O.L.; Semin, R.N.; Androsov, V.N.; Agafonov, V.N. [Research Institute of SIA ``LUCH``, Podolsk (Russian Federation); Koester, J.K. [Space Power Incorporated, 621 River Oaks Parkway, San-Jose, California 95134 (United States)

    1996-03-01T23:59:59.000Z

    As a result of its 1993{endash}94 work, NII NPO {open_quote}{open_quote}LUCH{close_quote}{close_quote} developed a thermionic fuel element (TFE) SC-320 intended for use as part of a nuclear thermionic reactor-converter known as SPACE-R designed in the US and rated at 40 kW of output electric power. This paper presents the results of the demonstration electric power tests of the SC-320 TFE mock-up conducted in the US at the TSET testing facility located at the University of New Mexico. The data obtained are compared to the calculated characteristics as well as the output parameters of the Topaz-2 NPS TFEs. {copyright} {ital 1996 American Institute of Physics.}

  8. SPACE-R nuclear power system SC-320 thermionic fuel element performance tests

    SciTech Connect (OSTI)

    Luchau, D.W.; Bruns, D.R. [Team Specialty Services, Inc., Albuquerque, NM (United States); Nikolaev, Y.V. [SIA LUCH Scientific Research Inst., Podolsk (Russian Federation)] [and others

    1996-12-31T23:59:59.000Z

    In 1993 and 1994, the Russian Scientific Research Institute NII NPO ``LUCH`` and Space Power, Inc., (SPI), of San Jose, California, developed a prototype of the single-cell thermionic fuel element (TFE) for the SPACE-R space nuclear power system (NPS). The SPACE-R system was designed as a part of the US Department of Energy`s (DOE) Space Reactor Development Program to develop a long life, space reactor system capable of supplying up to 40 kW(e) output power. The jointly developed SC-320 TFE is a prototype of the next generation thermionic converter for nuclear applications in space. This paper presents the results of the initial demonstration tests and subsequent parametric evaluations conducted on the SC-320 TFE as compared to the calculated performance characteristics. The demonstration tests were conducted jointly by Russian and American specialists at the Thermionic Evaluation Facility (TEF) at the New Mexico Engineering Research Institute (NMERI) of the University of New Mexico in Albuquerque.

  9. Final Report - Spent Nuclear Fuel Retrieval System Manipulator System Cold Validation Testing

    SciTech Connect (OSTI)

    D.R. Jackson; G.R. Kiebel

    1999-08-24T23:59:59.000Z

    Manipulator system cold validation testing (CVT) was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin; clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge); remove the contents from the canisters; and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. The FRS is composed of three major subsystems. The Manipulator Subsystem provides remote handling of fuel, scrap, and debris; the In-Pool Equipment subsystem performs cleaning of fuel and provides a work surface for handling materials; and the Remote Viewing Subsystem provides for remote viewing of the work area by operators. There are two complete and identical FRS systems, one to be installed in the K-West basin and one to be installed in the K-East basin. Another partial system will be installed in a cold test facility to provide for operator training.

  10. Background Radiation Survey of the Radiological/Nuclear Countermeasures Test and Evaluation Center

    SciTech Connect (OSTI)

    Colin Okada

    2010-09-16T23:59:59.000Z

    In preparation for operations at the Radiological/Nuclear Countermeasures Test and Evaluation Complex (Rad/NucCTEC), the Department of Homeland Security Domestic Nuclear Detection Office (DHS/DNDO) requested that personnel from the Remote Sensing Laboratory (RSL) conduct a survey of the present radiological conditions at the facility. The measurements consist of the exposure rate from a high-pressure ion chamber (HPIC), high-resolution spectra from a high-purity germanium (HPGe) system in an in situ configuration, and low-resolution spectra from a sodium iodide (NaI) detector in a radiation detection backpack. Measurements with these systems were collected at discrete locations within the facility. Measurements were also collected by carrying the VECTOR backpack throughout the complex to generate a map of the entire area. The area was also to be surveyed with the Kiwi (an array of eight-2-inch x 4-inch x 16-inch NaI detectors) from the Aerial Measuring Systems; however, conflicts with test preparation activities at the site prevented this from being accomplished.

  11. SiC-CMC-Zircaloy-4 Nuclear Fuel Cladding Performance during 4-Point Tubular Bend Testing

    SciTech Connect (OSTI)

    IJ van Rooyen; WR Lloyd; TL Trowbridge; SR Novascone; KM Wendt; SM Bragg-Sitton

    2013-09-01T23:59:59.000Z

    The U.S. Department of Energy Office of Nuclear Energy (DOE NE) established the Light Water Reactor Sustainability (LWRS) program to develop technologies and other solutions to improve the reliability, sustain the safety, and extend the life of current reactors. The Advanced LWR Nuclear Fuel Development Pathway in the LWRS program encompasses strategic research focused on improving reactor core economics and safety margins through the development of an advanced fuel cladding system. Recent investigations of potential options for “accident tolerant” nuclear fuel systems point to the potential benefits of silicon carbide (SiC) cladding. One of the proposed SiC-based fuel cladding designs being investigated incorporates a SiC ceramic matrix composite (CMC) as a structural material supplementing an internal Zircaloy-4 (Zr-4) liner tube, referred to as the hybrid clad design. Characterization of the advanced cladding designs will include a number of out-of-pile (nonnuclear) tests, followed by in-pile irradiation testing of the most promising designs. One of the out-of-pile characterization tests provides measurement of the mechanical properties of the cladding tube using four point bend testing. Although the material properties of the different subsystems (materials) will be determined separately, in this paper we present results of 4-point bending tests performed on fully assembled hybrid cladding tube mock-ups, an assembled Zr-4 cladding tube mock-up as a standard and initial testing results on bare SiC-CMC sleeves to assist in defining design parameters. The hybrid mock-up samples incorporated SiC-CMC sleeves fabricated with 7 polymer impregnation and pyrolysis (PIP) cycles. To provide comparative information; both 1- and 2-ply braided SiC-CMC sleeves were used in this development study. Preliminary stress simulations were performed using the BISON nuclear fuel performance code to show the stress distribution differences for varying lengths between loading points and clad configurations. The 2-ply sleeve samples show a higher bend momentum compared to those of the 1-ply sleeve samples. This is applicable to both the hybrid mock-up and bare SiC-CMC sleeve samples. Comparatively both the 1- and 2-ply hybrid mock-up samples showed a higher bend stiffness and strength compared with the standard Zr-4 mock-up sample. The characterization of the hybrid mock-up samples showed signs of distress and preliminary signs of fraying at the protective Zr-4 sleeve areas for the 1-ply SiC-CMC sleeve. In addition, the microstructure of the SiC matrix near the cracks at the region of highest compressive bending strain shows significant cracking and flaking. The 2-ply SiC-CMC sleeve samples showed a more bonded, cohesive SiC matrix structure. This cracking and fraying causes concern for increased fretting during the actual use of the design. Tomography was proven as a successful tool to identify open porosity during pre-test characterization. Although there is currently insufficient data to make conclusive statements regarding the overall merit of the hybrid cladding design, preliminary characterization of this novel design has been demonstrated.

  12. Speciation by monobrachial centric fusions: A test of the model using nuclear DNA sequences from the bat genus Rhogeessa

    E-Print Network [OSTI]

    Hillis, David

    Speciation by monobrachial centric fusions: A test of the model using nuclear DNA sequences from chromosomal rearrangements in a model termed speciation by monobrachial centric fusions. Recently a more comprehensive test of speciation by monobrachial centric fusions in Rhogeessa. Our analysis

  13. Underground storage of oil and gas

    SciTech Connect (OSTI)

    Bergman, S.M.

    1984-09-01T23:59:59.000Z

    The environmental and security advantages of underground storage of oil and gas are well documented. In many cases, underground storage methods such as storage in salt domes, abandoned mines, and mined rock caverns have proven to be cost effective when compared to storage in steel tanks constructed for that purpose on the surface. In good rock conditions, underground storage of large quantities of hydrocarbon products is normally less costly--up to 50-70% of the surface alternative. Under fair or weak rock conditions, economic comparisons between surface tanks and underground caverns must be evaluated on a case to case basis. The key to successful underground storage is enactment of a realistic geotechnical approach. In addition to construction cost, storage of petroleum products underground has operational advantages over similar storage above ground. These advantages include lower maintenance costs, less fire hazards, less land requirements, and a more even storage temperature.

  14. The Underground Corrosion of Selected Type 300 Stainless Steels After 34 Years

    SciTech Connect (OSTI)

    T. S. Yoder; M. K. Adler Flitton

    2009-03-01T23:59:59.000Z

    Recently, interest in long-term underground corrosion has greatly increased because of the ongoing need to dispose of nuclear waste. Additionally, the Nuclear Waste Policy Act of 1982 requires disposal of high-level nuclear waste in an underground repository. Current contaminant release and transport models use limited available short-term underground corrosion rates when considering container and waste form degradation. Consequently, the resulting models oversimplify the complex mechanisms of underground metal corrosion. The complexity of stainless steel corrosion mechanisms and the processes by which corrosion products migrate from their source are not well depicted by a corrosion rate based on general attack. The research presented here is the analysis of austenitic stainless steels after 33˝ years of burial. In this research, the corrosion specimens were analyzed using applicable ASTM standards as well as microscopic and X-ray examination to determine the mechanisms of underground stainless steel corrosion. As presented, the differences in the corrosion mechanisms vary with the type of stainless steel and the treatment of the samples. The uniqueness of the long sampling time allows for further understanding of the actual stainless steel corrosion mechanisms, and when applied back into predictive models, will assist in reduction of the uncertainty in parameters for predicting long-term fate and transport.

  15. National Center for Nuclear Security - NCNS

    SciTech Connect (OSTI)

    None

    2014-11-12T23:59:59.000Z

    As the United States embarks on a new era of nuclear arms control, the tools for treaty verification must be accurate and reliable, and must work at stand-off distances. The National Center for Nuclear Security, or NCNS, at the Nevada National Security Site, is poised to become the proving ground for these technologies. The center is a unique test bed for non-proliferation and arms control treaty verification technologies. The NNSS is an ideal location for these kinds of activities because of its multiple environments; its cadre of experienced nuclear personnel, and the artifacts of atmospheric and underground nuclear weapons explosions. The NCNS will provide future treaty negotiators with solid data on verification and inspection regimes and a realistic environment in which future treaty verification specialists can be trained. Work on warhead monitoring at the NCNS will also support future arms reduction treaties.

  16. National Center for Nuclear Security - NCNS

    ScienceCinema (OSTI)

    None

    2015-01-09T23:59:59.000Z

    As the United States embarks on a new era of nuclear arms control, the tools for treaty verification must be accurate and reliable, and must work at stand-off distances. The National Center for Nuclear Security, or NCNS, at the Nevada National Security Site, is poised to become the proving ground for these technologies. The center is a unique test bed for non-proliferation and arms control treaty verification technologies. The NNSS is an ideal location for these kinds of activities because of its multiple environments; its cadre of experienced nuclear personnel, and the artifacts of atmospheric and underground nuclear weapons explosions. The NCNS will provide future treaty negotiators with solid data on verification and inspection regimes and a realistic environment in which future treaty verification specialists can be trained. Work on warhead monitoring at the NCNS will also support future arms reduction treaties.

  17. An overview of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite

    SciTech Connect (OSTI)

    Voss, S.S. [Los Alamos National Lab., NM (United States); Reynolds, E.L. [Applied Physics Laboratory, Laurel, MD (United States)

    1994-06-01T23:59:59.000Z

    Early in 1992 the idea of purchasing a Russian designed and fabricated space reactor power system and integrating it with a US designed satellite went from fiction to reality with the purchase of the first two Topaz II reactors by the Strategic Defense Initiative Organization (now the Ballistic Missile Defense Organization (BMDO). The New Mexico Alliance was formed to establish a ground test facility in which to perform nonnuclear systems testing of the Topaz II, and to evaluate the Topaz 11 system for flight testing with respect to safety, performance, and operability. In conjunction, SDIO requested that the Applied Physics Laboratory in Laurel, MD propose a mission and design a satellite in which the Topaz II could be used as the power source. The outcome of these two activities was the design of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite which combines a modified Russian Topaz II power system with a US designed satellite to achieve a specified mission. Due to funding reduction within the SDIO, the Topaz II flight program was postponed indefinitely at the end of Fiscal Year 1993. The purpose of this paper is to present an overview of the NEPSTP mission and the satellite design at the time the flight program ended.

  18. Testing of a naturally aged nuclear power plant inverter and battery charger

    SciTech Connect (OSTI)

    Gunther, W.E.

    1988-09-01T23:59:59.000Z

    A naturally aged inverter and battery charger were obtained from the Shippingport facility. This equipment was manufactured in 1974, and was installed at Shippingport in 1975 as part of a major plant modification. Testing was performed on this equipment under the auspices of the NRC's Nuclear Plant Aging Research (NPAR) Program to evaluate the type and extent of degradation due to aging, and to determine the effectiveness of condition monitoring techniques which could be used to detect aging effects. Steady state testing was conducted over the equipment's entire operating range. Step load changes were also initiated in order to monitor the electrical response. During this testing, component temperatures were monitored and circuit waveforms analyzed. Results indicated that aging had not substantially affected equipment operation. On the other hand, when compared with original acceptance test data, the monitoring techniques employed were sensitive to changes in measurable component and equipment parameters indicating the viability of detecting degradation prior to catastrophic failure. 7 refs., 34 figs., 12 tabs.

  19. A micro hot test of the Chalmers-GANEX extraction system on used nuclear fuel

    SciTech Connect (OSTI)

    Bauhn, L.; Hedberg, M.; Aneheim, E.; Ekberg, C.; Loefstroem-Engdahl, E.; Skarnemark, G. [Department of Chemical and Biological Engineering, Nuclear Chemistry, Chalmers University of Technology, Kemivaegen 4, SE-412 96 Goeteborg (Sweden)

    2013-07-01T23:59:59.000Z

    In the present study, a 'micro hot test' has been performed using the Chalmers-GANEX (Group Actinide Extraction) system for partitioning of used nuclear fuel. The test included a pre-extraction step using N,N-di-2- ethylhexyl-butyramide (DEHBA) in n-octanol to remove the bulk part of the uranium. This pre-extraction was followed by a group extraction of actinides using the mixture of TBP and CyMe{sub 4}-BTBP in cyclohexanone as suggested in the Chalmers-GANEX process, and a three stage stripping of the extracted actinides. Distribution ratios for the extractions and stripping were determined based on a combination of ?- and ?-spectrometry, as well as ICP-MS measurements. Successful extraction of uranium, plutonium and the minor actinides neptunium, americium and curium was achieved. However, measurements also indicated that co-extraction of europium occurs to some extent during the separation. These results were expected based on previous experiments using trace concentrations of actinides and lanthanides. Since this test was only performed in one stage with respect to the group actinide extraction, it is expected that multi stage tests will give even better results. (authors)

  20. Oregon Underground Injection Control Registration Application...

    Open Energy Info (EERE)

    Oregon Underground Injection Control Registration Application Fees (DEQ Form UIC 1003-GIC) Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Oregon...

  1. Washington Environmental Permit Handbook - Underground Injection...

    Open Energy Info (EERE)

    Washington Environmental Permit Handbook - Underground Injection Control Registration webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site:...

  2. Oregon Underground Injection Control Registration Geothermal...

    Open Energy Info (EERE)

    Oregon Underground Injection Control Registration Geothermal Heating Systems (DEQ Form UICGEO-1004(f)) Jump to: navigation, search OpenEI Reference LibraryAdd to library Form:...

  3. ,"Tennessee Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  4. ,"Missouri Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  5. ,"Montana Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  6. ,"Iowa Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  7. ,"Pennsylvania Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  8. ,"Oregon Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  9. ,"Colorado Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  10. ,"Indiana Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  11. ,"Wyoming Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  12. ,"Kansas Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  13. ,"Maryland Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  14. ,"Alaska Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  15. ,"Nebraska Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  16. ,"Mississippi Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  17. ,"Utah Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  18. ,"Illinois Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  19. ,"Oklahoma Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  20. ,"Arkansas Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  1. ,"Virginia Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  2. ,"California Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  3. ,"Texas Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  4. ,"Kentucky Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  5. ,"Ohio Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  6. ,"Michigan Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  7. ,"Minnesota Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  8. ,"Washington Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  9. ,"Alabama Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  10. ,"Louisiana Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  11. Pipelines and Underground Gas Storage (Iowa)

    Broader source: Energy.gov [DOE]

    These rules apply to intrastate transport of natural gas and other substances via pipeline, as well as underground gas storage facilities. The construction and operation of such infrastructure...

  12. Wells, Borings, and Underground Uses (Minnesota)

    Broader source: Energy.gov [DOE]

    This section regulates wells, borings, and underground storage with regards to protecting groundwater resources. The Commissioner of the Department of Health has jurisdiction, and can grant permits...

  13. Final report spent nuclear fuel retrieval system primary cleaning development testing

    SciTech Connect (OSTI)

    Ketner, G.L.; Meeuwsen, P.V.

    1997-09-01T23:59:59.000Z

    Developmental testing of the primary cleaning station for spent nuclear fuel (SNF) and canisters is reported. A primary clean machine will be used to remove the gross sludge from canisters and fuel while maintaining water quality in the downstream process area. To facilitate SNF separation from canisters and minimize the impact to water quality, all canisters will be subjected to mechanical agitation and flushing with the Primary Clean Station. The Primary Clean Station consists of an outer containment box with an internally mounted, perforated wash basket. A single canister containing up to 14 fuel assemblies will be loaded into the wash basket, the confinement box lid closed, and the wash basket rotated for a fixed cycle time. During this cycle, basin water will be flushed through the wash basket and containment box to remove and entrain the sludge and carry it out of the box. Primary cleaning tests were performed to provide information concerning the removal of sludge from the fuel assemblies while in the basin canisters. The testing was also used to determine if additional fuel cleaning is required outside of the fuel canisters. Hydraulic performance and water demand requirements of the cleaning station were also evaluated. Thirty tests are reported in this document. Tests demonstrated that sludge can be dislodged and suspended sufficiently to remove it from the canister. Examination of fuel elements after cleaning suggested that more than 95% of the exposed fuel surfaces were cleaned so that no visual evidence of remained. As a result of testing, recommendations are made for the cleaning cycle. 3 refs., 16 figs., 4 tabs.

  14. above-ground nuclear tests: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Power Station; June This; Page Intentionally; Left Blank 456 Benchmarking Nuclear Fission Theory Nuclear Experiment (arXiv) Summary: We suggest a small set of fission observables...

  15. DOE (Department of Energy) nuclear weapon R and T (research, development, and testing): Objectives, roles, and responsibilities

    SciTech Connect (OSTI)

    Otey, G.R.

    1989-07-01T23:59:59.000Z

    An overview of the DOE nuclear weapons research, development, and testing program is given along with a description of the program objectives and the roles and responsibilities of the various involved organizations. The relationship between the DoD and DOE is described and the division of responsibilities for weapon development as well as the coordinated planning and acquisition activities are reviewed. Execution of the RD T program at the nuclear weapons laboratories is outlined. 24 refs., 3 figs.

  16. Concentration of Actinides in Plant Mounds at Safety Test Nuclear Sites in Nevada

    SciTech Connect (OSTI)

    David S. Shafer; Jenna Gommes

    2008-09-15T23:59:59.000Z

    Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada Test Site, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety test sites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety test sites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office has proposed that the majority of its contaminated soil 'Corrective Action Units', including the safety test sites, be closed by fencing and posting with administrative controls. The concentration of actinides in the shrub mounds has important implications for postclosure management of the safety test sites. Because resuspension factors at safety test sites can be three to four orders-of-magnitude higher than soil sites associated with atmospheric tests where criticality occurred, the shrub mounds are an important factor in stabilization of actinide contaminants. Loss of shrubs associated with mounds from fire or plant die-back from drought could cause radionuclides at these sites to become more prone to suspension and water erosion until the sites are stabilized. Alternatively, although shrub mounds are usually composed of predominantly fine sand size particles, smaller silt and clay size particles in them are often high in CaCO{sub 3} content. The CaCO{sub 3} may act as a cementing agent to limit erosion of the shrub mounds even if the vegetation cover is temporarily lost.

  17. OSI Passive Seismic Experiment at the Former Nevada Test Site

    SciTech Connect (OSTI)

    Sweeney, J J; Harben, P

    2010-11-11T23:59:59.000Z

    On-site inspection (OSI) is one of the four verification provisions of the Comprehensive Nuclear Test Ban Treaty (CTBT). Under the provisions of the CTBT, once the Treaty has entered into force, any signatory party can request an on-site inspection, which can then be carried out after approval (by majority voting) of the Executive Council. Once an OSI is approved, a team of 40 inspectors will be assembled to carry out an inspection to ''clarify whether a nuclear weapon test explosion or any other nuclear explosion has been carried out in violation of Article I''. One challenging aspect of carrying out an on-site inspection (OSI) in the case of a purported underground nuclear explosion is to detect and locate the underground effects of an explosion, which may include an explosion cavity, a zone of damaged rock, and/or a rubble zone associated with an underground collapsed cavity. The CTBT (Protocol, Section II part D, paragraph 69) prescribes several types of geophysical investigations that can be carried out for this purpose. One of the methods allowed by the CTBT for geophysical investigation is referred to in the Treaty Protocol as ''resonance seismometry''. This method, which was proposed and strongly promoted by Russia during the Treaty negotiations, is not described in the Treaty. Some clarification about the nature of the resonance method can be gained from OSI workshop presentations by Russian experts in the late 1990s. Our understanding is that resonance seismometry is a passive method that relies on seismic reverberations set up in an underground cavity by the passage of waves from regional and teleseismic sources. Only a few examples of the use of this method for detection of underground cavities have been presented, and those were done in cases where the existence and precise location of an underground cavity was known. As is the case with many of the geophysical methods allowed during an OSI under the Treaty, how resonance seismology really works and its effectiveness for OSI purposes has yet to be determined. For this experiment, we took a broad approach to the definition of ''resonance seismometry''; stretching it to include any means that employs passive seismic methods to infer the character of underground materials. In recent years there have been a number of advances in the use of correlation and noise analysis methods in seismology to obtain information about the subsurface. Our objective in this experiment was to use noise analysis and correlation analysis to evaluate these techniques for detecting and characterizing the underground damage zone from a nuclear explosion. The site that was chosen for the experiment was the Mackerel test in Area 4 of the former Nevada Test Site (now named the Nevada National Security Site, or NNSS). Mackerel was an underground nuclear test of less than 20 kT conducted in February of 1964 (DOENV-209-REV 15). The reason we chose this site is because there was a known apical cavity occurring at about 50 m depth above a rubble zone, and that the site had been investigated by the US Geological Survey with active seismic methods in 1965 (Watkins et al., 1967). Note that the time delay between detonation of the explosion (1964) and the time of the present survey (2010) is nearly 46 years - this would not be typical of an expected OSI under the CTBT.

  18. Spent nuclear fuel integrity during dry storage - performance tests and demonstrations

    SciTech Connect (OSTI)

    McKinnon, M.A.; Doherty, A.L.

    1997-06-01T23:59:59.000Z

    This report summarizes the results of fuel integrity surveillance determined from gas sampling during and after performance tests and demonstrations conducted from 1983 through 1996 by or in cooperation with the US DOE Office of Commercial Radioactive Waste Management (OCRWM). The cask performance tests were conducted at Idaho National Engineering Laboratory (INEL) between 1984 and 1991 and included visual observation and ultrasonic examination of the condition of the cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of fuel, and a qualitative determination of the effects of dry storage and fuel consolidation on fission gas release from the spent fuel rods. The performance tests consisted of 6 to 14 runs involving one or two loading, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the end of each performance test, periodic gas sampling was conducted on each cask. A spent fuel behavior project (i.e., enhanced surveillance, monitoring, and gas sampling activities) was initiated by DOE in 1994 for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are included in this report. Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at INEL offers significant opportunities for confirmation of the benign nature of long-term dry storage. Supporting cask demonstration included licensing and operation of an independent spent fuel storage installation (ISFSI) at the Virginia Power (VP) Surry reactor site. A CASTOR V/21, an MC-10, and a Nuclear Assurance NAC-I28 have been loaded and placed at the VP ISFSI as part of the demonstration program. 13 refs., 14 figs., 9 tabs.

  19. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    SciTech Connect (OSTI)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

  20. Characterization of microbial communities in subsurface nuclear blast cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Duane P. Moser; Ken Czerwinski; Charles E. Russell; Mavrik Zavarin

    2010-07-13T23:59:59.000Z

    This US Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this programâ??s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

  1. Characterization of Microbial Communities in Subsurface Nuclear Blast Cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Duane P. Moser, Jim Bruckner, Jen Fisher, Ken Czerwinski, Charles E. Russell, and Mavrik Zavarin

    2010-09-01T23:59:59.000Z

    This U.S. Department of Energy (DOE) Environmental Remediation Sciences Project (ERSP) was designed to test fundamental hypotheses concerning the existence and nature of indigenous microbial populations of Nevada Test Site subsurface nuclear test/detonation cavities. Now called Subsurface Biogeochemical Research (SBR), this program’s Exploratory Research (ER) element, which funded this research, is designed to support high risk, high potential reward projects. Here, five cavities (GASCON, CHANCELLOR, NASH, ALEMAN, and ALMENDRO) and one tunnel (U12N) were sampled using bailers or pumps. Molecular and cultivation-based techniques revealed bacterial signatures at five sites (CHANCELLOR may be lifeless). SSU rRNA gene libraries contained diverse and divergent microbial sequences affiliated with known metal- and sulfur-cycling microorganisms, organic compound degraders, microorganisms from deep mines, and bacteria involved in selenate reduction and arsenite oxidation. Close relatives of Desulforudis audaxviator, a microorganism thought to subsist in the terrestrial deep subsurface on H2 and SO42- produced by radiochemical reactions, was detected in the tunnel waters. NTS-specific media formulations were used to culture and quantify nitrate-, sulfate-, iron-reducing, fermentative, and methanogenic microorganisms. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, our results should have implications for management strategies at this and other DOE sites.

  2. A Validation Process for the Groundwater Flow and Transport Model of the Faultless Nuclear Test at Central Nevada Test Area

    SciTech Connect (OSTI)

    Ahmed Hassan

    2003-01-01T23:59:59.000Z

    Many sites of groundwater contamination rely heavily on complex numerical models of flow and transport to develop closure plans. This has created a need for tools and approaches that can be used to build confidence in model predictions and make it apparent to regulators, policy makers, and the public that these models are sufficient for decision making. This confidence building is a long-term iterative process and it is this process that should be termed ''model validation.'' Model validation is a process not an end result. That is, the process of model validation cannot always assure acceptable prediction or quality of the model. Rather, it provides safeguard against faulty models or inadequately developed and tested models. Therefore, development of a systematic approach for evaluating and validating subsurface predictive models and guiding field activities for data collection and long-term monitoring is strongly needed. This report presents a review of model validation studies that pertain to groundwater flow and transport modeling. Definitions, literature debates, previously proposed validation strategies, and conferences and symposia that focused on subsurface model validation are reviewed and discussed. The review is general in nature, but the focus of the discussion is on site-specific, predictive groundwater models that are used for making decisions regarding remediation activities and site closure. An attempt is made to compile most of the published studies on groundwater model validation and assemble what has been proposed or used for validating subsurface models. The aim is to provide a reasonable starting point to aid the development of the validation plan for the groundwater flow and transport model of the Faultless nuclear test conducted at the Central Nevada Test Area (CNTA). The review of previous studies on model validation shows that there does not exist a set of specific procedures and tests that can be easily adapted and applied to determine the validity of site-specific groundwater models. This is true for both deterministic and stochastic models, with the latter posing a more difficult and challenging problem when it comes to validation. This report then proposes a general validation approach for the CNTA model, which addresses some of the important issues recognized in previous validation studies, conferences, and symposia as crucial to the process. The proposed approach links model building, model calibration, model predictions, data collection, model evaluations, and model validation in an iterative loop. The approach focuses on use of collected validation data to reduce model uncertainty and narrow the range of possible outcomes of stochastic numerical models. It accounts for the stochastic nature of the numerical CNTA model, which used Monte Carlo simulation approach. The proposed methodology relies on the premise that absolute validity is not even a theoretical possibility and is not a regulatory requirement. Rather, it highlights the importance of testing as many aspects of the model as possible and using as many diverse statistical tools as possible for rigorous checking and confidence building in the model and its predictions. It is this confidence that will eventually allow for regulator and public acceptance of decisions based on the model predictions.

  3. Underground Corrosion of Activated Metals in an Arid Vadose Zone Environment

    SciTech Connect (OSTI)

    Adler Flitton, Mariana Kay; Mizia, Ronald Eugene; Bishop, Carolyn Wagoner

    2002-04-01T23:59:59.000Z

    The subsurface radioactive disposal site located at the Idaho National Engineering and Environmental Laboratory contains neutron-activated metals from nonfuel nuclear-reactor- core components. A long-term corrosion test is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in an arid vadose zone environment. The tests use nonradioactive metal coupons representing the prominent neutron-activated material buried at the disposal location, namely, Type 304L stainless steel, Type 315L stainless steel, nickel-chromium alloy (UNS NO7718), beryllium, aluminum 6061-T6, and a zirconium alloy, (UNS R60804). In addition, carbon steel (the material presently used in the cask disposal liners and other disposal containers) and a duplex stainless steel (UNS S32550) (the proposed material for the high- integrity disposal containers) are also included in the test program. This paper briefly describes the test program and presents the early corrosion rate results after 1 year and 3 years of underground exposure.

  4. Underground Corrosion of Activated Metals in an Arid Vadose Zone Environment

    SciTech Connect (OSTI)

    Adler Flitton, M.K; Mizia, R.E.; Bishop, C.W.

    2001-10-24T23:59:59.000Z

    The subsurface radioactive disposal site located at the Idaho National Engineering and Environmental Laboratory contains neutron-activated metals from nonfuel nuclear-reactor- core components. A long-term corrosion test is being conducted to obtain site-specific corrosion rates to support efforts to more accurately estimate the transfer of activated elements in an arid vadose zone environment. The tests use nonradioactive metal coupons representing the prominent neutron-activated material buried at the disposal location, namely, Type 304L stainless steel, Type 315L stainless steel, nickel-chromium alloy (UNS NO7718), beryllium, aluminum 6061-T6, and a zirconium alloy, (UNS R60804). In addition, carbon steel (the material presently used in the cask disposal liners and other disposal containers) and a duplex stainless steel (UNS S32550) (the proposed material for the high- integrity disposal containers) are also included in the test program. This paper briefly describes the test program and presents the early corrosion rate results after 1 year and 3 years of underground exposure.

  5. Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    1999-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade uranium dioxide powders and pellets to determine compliance with specifications. 1.2 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear-grade uranium dioxide powder and pellets. 1.4 This test method covers the determination of chlorine and fluorine in nuclear-grade uranium dioxide. With a 1 to 10-g sample, concentrations of 5 to 200 g/g of chlorine and 1 to 200 ?g/g of fluorine are determined without interference. 1.5 This test method covers the determination of moisture in uranium dioxide samples. Detection limits are as low as 10 ?g. 1.6 This test method covers the determination of nitride nitrogen in uranium dioxide in the range from 10 to 250 ?g. 1.7 This test method covers the spectrographic analysis of nuclear-grade UO2 for the 26 elements in the ranges indicated in Table 2. 1.8 For simultaneous determination of trace ele...

  6. Twenty Years of Underground Research at Canada's URL

    SciTech Connect (OSTI)

    Chandler, N. A.

    2003-02-27T23:59:59.000Z

    Construction of Atomic Energy of Canada Limited's (AECL's) Underground Research Laboratory (URL) began in 1982. The URL was designed to address the needs of the Canadian nuclear fuel waste management program. Over the years, a comprehensive program of geologic characterization and underground hydrogeologic, geotechnical and geomechanical projects have been performed, many of which are ongoing. The scientific work at the URL has evolved through a number of different phases to meet the changing needs of Canada's waste management program. The various phases of the URL have included siting, site evaluation, construction and operation. Collaboration with international organizations is encouraged at the URL, with the facility being a centre of excellence in an International Atomic Energy Agency (IAEA) network of underground facilities. One of AECL's major achievements of the past 20 year program has been the preparation and public defense of a ten-volume Environmental Impact Statement (EIS) for a conceptual deep geologic repository. Completion of this dissertation on the characterization, construction and performance modeling of a conceptual repository in the granite rock of the Canadian Shield was largely based on work conducted at the URL. Work conducted over the seven years since public defense of the EIS has been directed towards developing those engineering and performance assessment tools that would be required for implementation of a deep geologic repository. The URL continues to be a very active facility with ongoing experiments and demonstrations performed for a variety of Canadian and international radioactive waste management organizations.

  7. Underground storage tank management plan

    SciTech Connect (OSTI)

    NONE

    1994-09-01T23:59:59.000Z

    The Underground Storage Tank (UST) Management Program at the Oak Ridge Y-12 Plant was established to locate UST systems in operation at the facility, to ensure that all operating UST systems are free of leaks, and to establish a program for the removal of unnecessary UST systems and upgrade of UST systems that continue to be needed. The program implements an integrated approach to the management of UST systems, with each system evaluated against the same requirements and regulations. A common approach is employed, in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance, when corrective action is mandated. This Management Plan outlines the compliance issues that must be addressed by the UST Management Program, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Management Plan provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. (There are no underground radioactive waste UST systems located at Y-12.) The plan is divided into four major sections: (1) regulatory requirements, (2) implementation requirements, (3) Y-12 Plant UST Program inventory sites, and (4) UST waste management practices. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Management Program, and the procedures and guidance used for compliance with applicable regulations.

  8. Assessment of the facilities on Jackass Flats and other Nevada test site facilities for the new nuclear rocket program

    SciTech Connect (OSTI)

    Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D. (Field Test Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States))

    1993-01-15T23:59:59.000Z

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. In particular we have assumed that the program goal will be to certify a full engine system design as flight test ready. All nuclear and non-nuclear components will be individually certified as ready for such a test at sites remote from the NRDA facilities, the components transported to NRDA, and the engine assembled. We also assume that engines of 25,000--100,000 lb thrust levels will be tested with burn times of 1 hour or longer. After a test, the engine will be disassembled, time critical inspections will be executed, and a selection of components will be transported to remote inspection sites. The majority of the components will be stored for future inspection at Jackass Flats. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad.

  9. An Empirical Study on Ultrasonic Testing in Lieu of Radiography for Nuclear Power Plants

    SciTech Connect (OSTI)

    Moran, Traci L.; Pardini, Allan F.; Ramuhalli, Pradeep; Prowant, Matthew S.; Mathews, Royce

    2012-09-01T23:59:59.000Z

    Research is being conducted for the U.S. Nuclear Regulatory Commission (NRC) at the Pacific Northwest National Laboratory (PNNL) to assess the capability, effectiveness, and reliability of ultrasonic testing (UT) as a replacement method for radiographic testing (RT) for inspecting nuclear power plant (NPP) components. A primary objective of this work is to evaluate UT techniques to assess their ability to detect, locate, size, and characterize fabrication flaws in typical NPP weldments. This particular study focused on the evaluation of four carbon steel pipe-to-pipe welds on specimens that ranged in thicknesses from 19.05 mm (0.75 in.) to 27.8 mm (1.094 in.) and were 355.6 mm (14.0 in.) or 406.4 mm (16.0 in.) in diameter. The pipe welds contained both implanted (intentional) fabrication flaws as well as bonus (unintentional) flaws throughout the entire thickness of the weld and the adjacent base material. The fabrication flaws were a combination of planar and volumetric flaw types, including incomplete fusion, incomplete penetration, cracks, porosity, and slag inclusions. The examinations were conducted using phased-array UT (PA UT) techniques applied primarily for detection and length sizing of the flaws. Radiographic examinations were also conducted on the specimens with RT detection and length sizing results being used to establish true state. This paper will discuss the comparison of UT and RT (true state) detection results conducted to date along with a discussion on the technical gaps that need to be addressed before these methods can be used interchangeably for repair and replacement activities for NPP components.

  10. UNDERGROUND MUONS IN SUPER-KAMIOKANDE

    E-Print Network [OSTI]

    Tokyo, University of

    HE 4.1.23 UNDERGROUND MUONS IN SUPER-KAMIOKANDE The Super-Kamiokande Collaboration, presented by J The largest underground neutrino observatory, Super-Kamiokande, located near Kamioka, Japan has been for muons ver- sus zenith angle in Super-Kamiokande. The lled region is for muons with more than 1.7 Ge

  11. Carbon Allocation in Underground Storage Organs

    E-Print Network [OSTI]

    Carbon Allocation in Underground Storage Organs Studies on Accumulation of Starch, Sugars and Oil Cover: Starch granules in cells of fresh potato tuber visualised by iodine staining. #12;Carbon By increasing knowledge of carbon allocation in underground storage organs and using the knowledge to improve

  12. Results from NNWSI [Nevada Nuclear Waste Storage Investigations] Series 2 bare fuel dissolution tests

    SciTech Connect (OSTI)

    Wilson, C.N.

    1990-09-01T23:59:59.000Z

    The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Two bare spent fuel specimens plus the empty cladding hulls were tested in NNWSI J-13 well water in unsealed fused silica vessels under ambient hot cell air conditions (25{degree}C) in the currently reported tests. One of the specimens was prepared from a rod irradiated in the H. B. Robinson Unit 2 reactor and the other from a rod irradiated in the Turkey Point Unit 3 reactor. Results indicate that most radionuclides of interest fall into three groups for release modeling. The first group principally includes the actinides (U, Np, Pu, Am, and Cm), all of which reached solubility-limited concentrations that were orders of magnitude below those necessary to meet the NRC 10 CFR 60.113 release limits for any realistic water flux predicted for the Yucca Mountain repository site. The second group is nuclides of soluble elements such as Cs, Tc, and I, for which release rates do not appear to be solubility-limited and may depend on the dissolution rate of fuel. In later test cycles, {sup 137}Cs, {sup 90}Sr, {sup 99}Tc, and {sup 129}I were continuously released at rates between about 5 {times} 10{sup {minus}5} and 1 {times} 10{sup {minus}4} of inventory per year. The third group is radionuclides that may be transported in the vapor phase, of which {sup 14}C is of primary concern. Detailed test results are presented and discussed. 17 refs., 15 figs., 21 tabs.

  13. DOE - Office of Legacy Management -- Hoe Creek Underground Coal...

    Office of Legacy Management (LM)

    Hoe Creek Underground Coal Gasification Site - 045 FUSRAP Considered Sites Site: Hoe Creek Underground Coal Gasification Site (045) Designated Name: Alternate Name: Location:...

  14. Emissions and Durability of Underground Mining Diesel Particulate...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Durability of Underground Mining Diesel Particulate Filter Applications Emissions and Durability of Underground Mining Diesel Particulate Filter Applications Presentation given at...

  15. EA-1943: Long Baseline Neutrino Facility/Deep Underground Neutrino...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DUNE) at Fermilab, Batavia, Illinois and the Sanford Underground Research Facility, Lead, South Dakota EA-1943: Long Baseline Neutrino FacilityDeep Underground Neutrino...

  16. Standard test methods for determining chemical durability of nuclear, hazardous, and mixed waste glasses and multiphase glass ceramics: The product consistency test (PCT)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2002-01-01T23:59:59.000Z

    1.1 These product consistency test methods A and B evaluate the chemical durability of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, and/or multiphase glass ceramic waste forms hereafter collectively referred to as “glass waste forms” by measuring the concentrations of the chemical species released to a test solution. 1.1.1 Test Method A is a seven-day chemical durability test performed at 90 ± 2°C in a leachant of ASTM-Type I water. The test method is static and conducted in stainless steel vessels. Test Method A can specifically be used to evaluate whether the chemical durability and elemental release characteristics of nuclear, hazardous, and mixed glass waste forms have been consistently controlled during production. This test method is applicable to radioactive and simulated glass waste forms as defined above. 1.1.2 Test Method B is a durability test that allows testing at various test durations, test temperatures, mesh size, mass of sample, leachant volume, a...

  17. In-pile testing on thermionic space nuclear power fuel using a TRIGA reactor

    SciTech Connect (OSTI)

    Razvi, J.; Whittemore, W.L. [General Atomics, San Diego, CA (United States)

    1988-07-01T23:59:59.000Z

    The U. S. Department of Energy is sponsoring a thermionic technology development program at General Atomics (GA) to address the feasibility issues associated with the use of thermionic fuel elements (TFE) for space based nuclear power systems. The technology program being carried out at GA during the 1980s is aimed at investigating lifetime issues of the fuelled emitter and insulator materials proposed for use in thermionic reactor based space power systems, both experimentally and analytically, with a goal towards developing a TFE with a lifetime of at least seven years. The experimental investigations of TFE lifetime issues consist of performing in-pile irradiations on prototype units using the 1.5 Mw TRIGA Mark F research reactor to validate TFE emitter deformation models and to measure the amount of emitter deformation as a function of fuel burnup, temperature and emitter thickness. To this end, nine thermionic emitters, fueled with uranium oxide and contained in three irradiation capsules, have been designed and fabricated to date, and are being tested in-core in the Mark F to study emitter materials integrity under irradiation conditions. In addition, a capsule consisting of only insulator test articles has also been irradiated in the Mark F to study insulator materials integrity under irradiation and applied voltage.

  18. VNS: A volumetric neutron source for fusion nuclear technology testing and development

    SciTech Connect (OSTI)

    Abdou, M.A.; Peng, Y.K.; Ying, A.Y. [Univ. of California, Los Angeles, CA (United States)] [and others

    1994-12-31T23:59:59.000Z

    Recent progress in fusion plasma research and the initiation of the Engineering Design Activity for ITER provide incentives to seriously explore technically sound and logically consistent pathways toward development of fusion as a practical and attractive energy source. A critical goal is the successful construction and operation of a fusion power demonstration plant (DEMO). Major world program strategies call for DEMO operation by the year 2025. Such a date is important in order for fusion to play a significant role in the energy supply market in the second half of the twenty-first century. Without such a DEMO goal, it will be very hard to justify major financial commitments in the near term for major projects such as ITER. The major question is whether a DEMO goal by the year 2025 is attainable from a technical standpoint. This has been the central question being addressed in a study, called VENUS. Results to date show that a DEMO by the year 2025 can be realized if three major facilities begin operation in parallel by the year 2005. These facilities are: (1) ITER, (2) VNS, and (3) IFMIF. Results show that VNS is a necessary element toward DEMO in a strategy consistent with present world program plans. The key requirements to test and develop fusion nuclear components (e.g. blanket) are 1 MW/m{sup 2} neutron wall load, >10 m{sup 2} of test area at the first wall, steady state or long burn plasma operation, fluence of {approx}6MWy/m{sup 2} at the first wall in {approx}10-12 year period, and duty cycle x availability factor of {approx}0.3. Results of the study show that an attractive design envelope for VNS that satisfies the nuclear testing and development requirements exists. Within this design envelope, the most attractive design points for VNS appear to be driven plasma (Q{approx}1) in tokamak configuration with normal toroidal-field copper coils, major radius 1.5-2.0m, fusion power {approx}100MW, and neutron wall load {approx}1.5MW/m{sup 2}.

  19. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    SciTech Connect (OSTI)

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01T23:59:59.000Z

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

  20. Underground Storage Tank Regulations for the Certification of Persons Who Install, Alter, and Remove Underground Storage Tanks (Mississippi)

    Broader source: Energy.gov [DOE]

    The Underground Storage Tank Regulations for the Certification of Persons who Install, Alter, and Remove Underground Storage Tanks applies to any project that will install, alter or remove...

  1. LLNL Capabilities in Underground Coal Gasification

    SciTech Connect (OSTI)

    Friedmann, S J; Burton, E; Upadhye, R

    2006-06-07T23:59:59.000Z

    Underground coal gasification (UCG) has received renewed interest as a potential technology for producing hydrogen at a competitive price particularly in Europe and China. The Lawrence Livermore National Laboratory (LLNL) played a leading role in this field and continues to do so. It conducted UCG field tests in the nineteen-seventies and -eighties resulting in a number of publications culminating in a UCG model published in 1989. LLNL successfully employed the ''Controlled Retraction Injection Point'' (CRIP) method in some of the Rocky Mountain field tests near Hanna, Wyoming. This method, shown schematically in Fig.1, uses a horizontally-drilled lined injection well where the lining can be penetrated at different locations for injection of the O{sub 2}/steam mixture. The cavity in the coal seam therefore gets longer as the injection point is retracted as well as wider due to reaction of the coal wall with the hot gases. Rubble generated from the collapsing wall is an important mechanism studied by Britten and Thorsness.

  2. Seismic fragility evaluation of a piping system in a nuclear power plant by shaking table test and numerical analysis

    SciTech Connect (OSTI)

    Kim, M. K.; Kim, J. H.; Choi, I. K. [Korea Atomic Energy Research Inst., Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    In this study, a seismic fragility evaluation of the piping system in a nuclear power plant was performed. For the evaluation of seismic fragility of the piping system, this research was progressed as three steps. At first, several piping element capacity tests were performed. The monotonic and cyclic loading tests were conducted under the same internal pressure level of actual nuclear power plants to evaluate the performance. The cracks and wall thinning were considered as degradation factors of the piping system. Second, a shaking tale test was performed for an evaluation of seismic capacity of a selected piping system. The multi-support seismic excitation was performed for the considering a difference of an elevation of support. Finally, a numerical analysis was performed for the assessment of seismic fragility of piping system. As a result, a seismic fragility for piping system of NPP in Korea by using a shaking table test and numerical analysis. (authors)

  3. Toxic hazards of underground excavation

    SciTech Connect (OSTI)

    Smith, R.; Chitnis, V.; Damasian, M.; Lemm, M.; Popplesdorf, N.; Ryan, T.; Saban, C.; Cohen, J.; Smith, C.; Ciminesi, F.

    1982-09-01T23:59:59.000Z

    Inadvertent intrusion into natural or man-made toxic or hazardous material deposits as a consequence of activities such as mining, excavation or tunnelling has resulted in numerous deaths and injuries in this country. This study is a preliminary investigation to identify and document instances of such fatal or injurious intrusion. An objective is to provide useful insights and information related to potential hazards due to future intrusion into underground radioactive-waste-disposal facilities. The methodology used in this study includes literature review and correspondence with appropriate government agencies and organizations. Key categories of intrusion hazards are asphyxiation, methane, hydrogen sulfide, silica and asbestos, naturally occurring radionuclides, and various mine or waste dump related hazards.

  4. Cultural Resource Investigations for the Resumption of Transient Testing of Nuclear Fuels and Material at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Brenda R. Pace; Julie B. Williams

    2013-11-01T23:59:59.000Z

    The U. S. Department of Energy (DOE) has a need to test nuclear fuels under conditions that subject them to short bursts of intense, high-power radiation called ‘transient testing’ in order to gain important information necessary for licensing new nuclear fuels for use in U.S. nuclear power plants, for developing information to help improve current nuclear power plant performance and sustainability, for improving the affordability of new generation reactors, for developing recyclable nuclear fuels, and for developing fuels that inhibit any repurposing into nuclear weapons. To meet this mission need, DOE is considering alternatives for re-use and modification of existing nuclear reactor facilities to support a renewed transient testing program. One alternative under consideration involves restarting the Transient Reactor Test (TREAT) reactor located at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL) site in southeastern Idaho. This report summarizes cultural resource investigations conducted by the INL Cultural Resource Management Office in 2013 to support environmental review of activities associated with restarting the TREAT reactor at the INL. These investigations were completed in order to identify and assess the significance of cultural resources within areas of potential effect associated with the proposed action and determine if the TREAT alternative would affect significant cultural resources or historic properties that are eligible for nomination to the National Register of Historic Places. No archaeological resources were identified in the direct area of potential effects for the project, but four of the buildings proposed for modifications are evaluated as historic properties, potentially eligible for nomination to the National Register of Historic Places. This includes the TREAT reactor (building #), control building (building #), guardhouse (building #), and warehouse (building #). The proposed re-use of these historic properties is consistent with original missions related to nuclear reactor testing and is expected to result in no adverse effects to their historic significance. Cultural resource investigations also involved communication with representatives from the Shoshone-Bannock Tribes to characterize cultural resources of potential tribal concern. This report provides a summary of the cultural resources inventoried and assessed within the defined areas of potential effect for the resumption of transient testing at the INL. Based on these analyses, proposed activities would have no adverse effects on historic properties within the APEs that have been defined. Other archaeological resources and cultural resources of potential concern to the Shoshone-Bannock Tribes and others that are located near the APEs are also discussed with regard to potential indirect impacts. The report concludes with general recommendations for measures to reduce impacts to all identified resources.

  5. Nuclear waste: our radioactive hot potato

    SciTech Connect (OSTI)

    Conselman, F.B.

    1984-01-01T23:59:59.000Z

    Nuclear industry inevitably produces nuclear waste, whose prudent, prompt and economic disposal is important to the national welfare. Technological problems of containment and isolation have apparently been solved. Underground or geologic disposal sites have the potential form permanent isolation, with salt, basalt, granite, shale, and tuff currently receiving principal attention as repository host rocks. Bedded salt deposits may offer the principal mechanical advantages, but in the northwestern United States the abundance of basalt at existing test sites has made it the subject of experimentation. However, psychological, political, and allegedly environmental obstructionism have stalled the process and virtually immobilized current construction. A program is suggested with the purpose of satisfying technical requirements for public protection while allaying the exaggerated fears of anti-nuclear factions.

  6. Characterization of Microbial Communities in Subsurface Nuclear Blast Cavities of the Nevada Test Site

    SciTech Connect (OSTI)

    Moser, Duane; Russell, Chuck; Marshall, Matthew; Czerwinski, Ken; Daly, Michael J; Zavarin, Mavrik

    2008-02-08T23:59:59.000Z

    This exploratory research project is designed to test fundamental hypotheses concerning the possible existence and nature of indigenous microbial populations in Nevada Test Site (NTS) subsurface nuclear blast cavities. Although subsurface microbiological studies have been performed at the NTS in the past, radioactive zones have yet to be addressed. Nuclear blast zone microbiology is a completely new field and our team is well-positioned to collect and analyze samples that have never before been available to microbiologists. Relevant samples are now being obtained by incorporating microbiological collections into an ongoing annual hot well sampling program being conducted by other agencies. A combination of cultivation-based and molecular microbial detection protocols is being utilized at multiple locations to survey for uncultivable microorganisms and to develop a culture collection which will be characterized for radionuclide- and metal-reduction capabilities. Given that redox manipulations mediated by microorganisms can impact the mobility of DOE contaminants, a positive outcome from this work would have significant implications for management strategies at this and other DOE sites. A primary objective of the project has been the establishment of the regulatory and technical framework necessary to enable our acquisition of samples. Thus, much of our activity in the first phase of this work has involved the development an approved Field Area Work Plan (FAWP), Radiological Work Permit (RWP), and other documentation required for radiological work at the NTS. We have also invested significant time into ensuring that all personnel possess the required training (e.g. Radworker II and 40 hr. HAZWOPER) for access to the hot well sampling sites. Laboratory facilities, required for field processing of radioactive samples as well as DNA extraction and other manipulations, have been secured both the NTS (Mercury, NV) and UNLV. Although our year-1 field work was delayed due to non-availability of samples, an aggressive sampling campaign is now underway and our first hot well samples were collected on Feb 5th, 2008. The unique nature of this site, coupled with the combined expertise of the collaborating laboratories (DRI, LLNL, PNNL, and the Harry Reid Center) makes the likelihood of our achieving discoveries of value to DOE, the individual researchers, and society high. As the selective pressures at atomic blast sites are probably different from those of production and disposal sites, these habitats may contain novel organisms of utility for bioremediation. Such organisms will have had to develop physiological mechanisms to survive high doses of ionizing radiation over the variety of rock types and hydrologic environments present at the NTS.

  7. Probing New Physics with Underground Accelerators and Radioactive Sources

    E-Print Network [OSTI]

    Eder Izaguirre; Gordan Krnjaic; Maxim Pospelov

    2014-05-19T23:59:59.000Z

    New light, weakly coupled particles can be efficiently produced at existing and future high-intensity accelerators and radioactive sources in deep underground laboratories. Once produced, these particles can scatter or decay in large neutrino detectors (e.g Super-K and Borexino) housed in the same facilities. We discuss the production of weakly coupled scalars $\\phi$ via nuclear de-excitation of an excited element into the ground state in two viable concrete reactions: the decay of the $0^+$ excited state of $^{16}$O populated via a $(p,\\alpha)$ reaction on fluorine and from radioactive $^{144}$Ce decay where the scalar is produced in the de-excitation of $^{144}$Nd$^*$, which occurs along the decay chain. Subsequent scattering on electrons, $e(\\phi,\\gamma)e$, yields a mono-energetic signal that is observable in neutrino detectors. We show that this proposed experimental set-up can cover new territory for masses $250\\, {\\rm keV}\\leq m_\\phi \\leq 2 m_e$ and couplings to protons and electrons, $10^{-11} new physics component to the neutrino and nuclear astrophysics programs at underground facilities.

  8. Underground cosmic-ray experiment EMMA T. Enqvista

    E-Print Network [OSTI]

    Usoskin, Ilya G.

    Authority ­ STUK, Helsinki, Finland d Centre for Underground Physics at Pyh¨asalmi (CUPP), University

  9. Proceedings of the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear Test-Ban Treaty

    SciTech Connect (OSTI)

    Warren, N. Jill [Editor

    1999-09-21T23:59:59.000Z

    These proceedings contain papers prepared for the 21st Seismic Research Symposium: Technologies for Monitoring The Comprehensive Nuclear-Test-Ban Treaty, held 21-24 September 1999 in Las Vegas, Nevada. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Technical Applications Center (AFTAC), Department of Defense (DoD), the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO), and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  10. Modeling of contaminant transport in underground coal gasification

    SciTech Connect (OSTI)

    Lanhe Yang; Xing Zhang [China University of Mining and Technology, Xuzhou (China). College of Resources and Geosciences

    2009-01-15T23:59:59.000Z

    In order to study and discuss the impact of contaminants produced from underground coal gasification on groundwater, a coupled seepage-thermodynamics-transport model for underground gasification was developed on the basis of mass and energy conservation and pollutant-transport mechanisms, the mathematical model was solved by the upstream weighted multisell balance method, and the model was calibrated and verified against the experimental site data. The experiment showed that because of the effects of temperature on the surrounding rock of the gasification panel the measured pore-water-pressure was higher than the simulated one; except for in the high temperature zone where the simulation errors of temperature, pore water pressure, and contaminant concentration were relatively high, the simulation values of the overall gasification panel were well fitted with the measured values. As the gasification experiment progressed, the influence range of temperature field expanded, the gradient of groundwater pressure decreased, and the migration velocity of pollutant increased. Eleven months and twenty months after the test, the differences between maximum and minimum water pressure were 2.4 and 1.8 MPa, respectively, and the migration velocities of contaminants were 0.24-0.38 m/d and 0.27-0.46 m/d, respectively. It was concluded that the numerical simulation of the transport process for pollutants from underground coal gasification was valid. 42 refs., 13 figs., 1 tab.

  11. Bikini, Enewetak, and Rongelap Marshallese, and United States nuclear weapons testing in the Marshall Islands: A bibliography

    SciTech Connect (OSTI)

    Robison, W.L. (ed.) (Lawrence Livermore National Lab., CA (USA)); Schultz, V. (Washington State Univ., Pullman, WA (USA)); Schultz, S.C. (Oregon Univ., Eugene, OR (USA))

    1991-04-01T23:59:59.000Z

    A considerable literature exists on the Bikini, Enewetak, and Rongelap Marshallese and their atolls; however, this literature consists of a large number of governmental documents that are relatively unknown and difficult to locate. This is particularly true of the documents of the Trust Territory of the Pacific Islands and those related to nuclear weapons testing in the Marshall Islands. Because a comprehensive bibliography on the impact of nuclear weapons testing on the Marshallese and their atolls does not exist, the preparation of a bibliography that includes sufficient information to locate all types of reports seems justified. Primary sources of information in preparing this bibliography were bibliographies on Oceania, citations in published papers, CIS Index and Abstracts, Monthly Catalog of United States Government Publications, Nuclear Science Abstracts, Energy Research Abstracts, numerous bibliographies on radiation ecology, and suggestions by many individuals whom we contacted. One goal in this bibliography is to include complete documentation of the source of congressional reports and other government-related publications. In addition, page numbers for material in this bibliography are provided in parentheses when the subject matter of a book or document is not restricted to nuclear weapons testing in the Marshall Islands.

  12. Advanced underground Vehicle Power and Control: The locomotive Research Platform

    SciTech Connect (OSTI)

    Vehicle Projects LLC

    2003-01-28T23:59:59.000Z

    Develop a fuelcell mine locomotive with metal-hydride hydrogen storage. Test the locomotive for fundamental limitations preventing successful commercialization of hydride fuelcells in underground mining. During Phase 1 of the DOE-EERE sponsored project, FPI and its partner SNL, completed work on the development of a 14.4 kW fuelcell power plant and metal-hydride energy storage. An existing battery-electric locomotive with similar power requirements, minus the battery module, was used as the base vehicle. In March 2001, Atlas Copco Wagner of Portland, OR, installed the fuelcell power plant into the base vehicle and initiated integration of the system into the vehicle. The entire vehicle returned to Sandia in May 2001 for further development and integration. Initial system power-up took place in December 2001. A revision to the original contract, Phase 2, at the request of DOE Golden Field Office, established Vehicle Projects LLC as the new prime contractor,. Phase 2 allowed industry partners to conduct surface tests, incorporate enhancements to the original design by SNL, perform an extensive risk and safety analysis, and test the fuelcell locomotive underground under representative production mine conditions. During the surface tests one of the fuelcell stacks exhibited reduced power output resulting in having to replace both fuelcell stacks. The new stacks were manufactured with new and improved technology resulting in an increase of the gross power output from 14.4 kW to 17 kW. Further work by CANMET and Hatch Associates, an engineering consulting firm specializing in safety analysis for the mining industry, both under subcontract to Vehicle Projects LLC, established minimum requirements for underground testing. CANMET upgraded the Programmable Logic Control (PLC) software used to monitor and control the fuelcell power plant, taking into account locomotive operator's needs. Battery Electric, a South Africa manufacturer, designed and manufactured (at no cost to the project) a new motor controller capable of operating the higher rpm motor and different power characteristics of the fuelcells. In early August 2002, CANMET, with the technical assistance of Nuvera Fuel Cells and Battery Electric, installed the new PLC software, installed the new motor controller, and installed the new fuelcell stacks. After minor adjustments, the fuelcell locomotive pulled its first fully loaded ore cars on a surface track. The fuelcell-powered locomotive easily matched the battery powered equivalent in its ability to pull tonnage and equaled the battery-powered locomotive in acceleration. The final task of Phase 2, testing the locomotive underground in a production environment, occurred in early October 2002 in a gold mine. All regulatory requirements to allow the locomotive underground were completed and signed off by Hatch Associates prior to going underground. During the production tests, the locomotive performed flawlessly with no failures or downtime. The actual tests occurred during a 2-week period and involved moving both gold ore and waste rock over a 1,000 meter track. Refueling, or recharging, of the metal-hydride storage took place on the surface. After each shift, the metal-hydride storage module was removed from the locomotive, transported to surface, and filled with hydrogen from high-pressure tanks. The beginning of each shift started with taking the fully recharged metal-hydride storage module down into the mine and re-installing it onto the locomotive. Each 8 hour shift consumed approximately one half to two thirds of the onboard hydrogen. This indicates that the fuelcell-powered locomotive can work longer than a similar battery-powered locomotive, which operates about 6 hours, before needing a recharge.

  13. New details on nuclear weapons program bared

    SciTech Connect (OSTI)

    Hileman, B.

    1994-07-11T23:59:59.000Z

    In a continuing effort to be more candid about Department of Energy nuclear weapons programs, Energy Secretary Hazel R. O'Leary recently declassified a substantial amount of information. On June 27, she revealed details about total US weapons-grade uranium production, testing of a bomb made of reactor-grade plutonium, radiation experiments conducted on humans since the 1920s, and underground and atmospheric nuclear weapons tests. O'Leary explains the new revelations by saying thousands of people in meetings across the country this year have told her that openness in government is very important. DOE is responding today in a manner that both satisfies the strong public interest and respects critical national security requirements.

  14. Underground Injection Control Fee Schedule (West Virginia)

    Broader source: Energy.gov [DOE]

    This rule establishes schedules of permit fees for state under?ground injection control permits issued by the Chief of the Office of Water Resources. This rule applies to any person who is...

  15. Underground Gas Storage Reservoirs (West Virginia)

    Broader source: Energy.gov [DOE]

    Lays out guidelines for the conditions under which coal mining operations must notify state authorities of intentions to mine where underground gas is stored as well as map and data requirements,...

  16. Underground Storage of Natural Gas (Kansas)

    Broader source: Energy.gov [DOE]

    Any natural gas public utility may appropriate for its use for the underground storage of natural gas any subsurface stratum or formation in any land which the commission shall have found to be...

  17. Prince George's County Underground Storage Act (Maryland)

    Broader source: Energy.gov [DOE]

    A gas storage company may invoke eminent domain to acquire property in Prince George's County for underground gas storage purposes. The area acquired must lie not less than 800 feet below the...

  18. Arkansas Underground Injection Control Code (Arkansas)

    Broader source: Energy.gov [DOE]

    The Arkansas Underground Injection Control Code (UIC code) is adopted pursuant to the provisions of the Arkansas Water and Air Pollution Control Act (Arkansas Code Annotated 8-5-11). It is the...

  19. The Department of Energy`s Comprehensive Test Bank Treaty Research and Development Program

    SciTech Connect (OSTI)

    Simons, D.; Stump, B. [Los Alamos National Lab., NM (United States); Breding, D.; Casey, L. [Dept. of Energy, Washington, DC (United States); Walker, L. [Sandia National Labs., Albuquerque, NM (United States); Zucca, J.; Harris, D.; Hannon, J.; Denny, M.; Patton, H. [Lawrence Livermore National Lab., CA (United States)] [and others

    1995-12-31T23:59:59.000Z

    The U.S. DOE sponsored research investigating atmospheric infrasound as a means of detecting both atmospheric and underground nuclear tests. Various detection schemes were examined and were found to be effective for different situations. It has been discovered that an enhanced sensitivity is realizable for the very lowest frequency disturbances by detecting the infrasound at the top of the atmosphere using radio sound techniques. These techniques are compared to more traditional measurement schemes.

  20. Viewing Systems for Large Underground Storage Tanks.

    SciTech Connect (OSTI)

    Heckendorn, F.M., Robinson, C.W., Anderson, E.K. [Westinghouse Savannah River Co., Aiken, SC (United States)], Pardini, A.F. [Westinghouse Hanford Co., Richland, WA (United States)

    1996-12-31T23:59:59.000Z

    Specialized remote video systems have been successfully developed and deployed in a number of large radiological Underground Storage Tanks (USTs)that tolerate the hostile tank interior, while providing high resolution video to a remotely located operator. The deployment is through 100 mm (4 in) tank openings, while incorporating full video functions of the camera, lights, and zoom lens. The usage of remote video minimizes the potential for personnel exposure to radiological and hazardous conditions, and maximizes the quality of the visual data used to assess the interior conditions of both tank and contents. The robustness of this type of remote system has a direct effect on the potential for radiological exposure that personnel may encounter. The USTs typical of the Savannah River and Hanford Department Of Energy - (DOE) sites are typically 4.5 million liter (1.2 million gal) units under earth. or concrete overburden with limited openings to the surface. The interior is both highly contaminated and radioactive with a wide variety of nuclear processing waste material. Some of the tanks are -flammable rated -to Class 1, Division 1,and personnel presence at or near the openings should be minimized. The interior of these USTs must be assessed periodically as part of the ongoing management of the tanks and as a step towards tank remediation. The systems are unique in their deployment technology, which virtually eliminates the potential for entrapment in a tank, and their ability to withstand flammable environments. A multiplicity of components used within a common packaging allow for cost effective and appropriate levels of technology, with radiation hardened components on some units and lesser requirements on other units. All units are completely self contained for video, zoom lens, lighting, deployment,as well as being self purging, and modular in construction.

  1. Nuclear polarization study: New frontiers for tests of QED in heavy highly charged ions

    E-Print Network [OSTI]

    Volotka, Andrey V

    2015-01-01T23:59:59.000Z

    A systematic investigation of the nuclear-polarization effects in one- and few-electron heavy ions is presented. The nuclear-polarization corrections in the zeroth and first orders in $1/Z$ are evaluated to the binding energies, the hyperfine splitting, and the bound-electron g factor. It is shown, that the nuclear-polarization contributions can be substantially canceled simultaneously with the rigid nuclear corrections. This allows for new prospects for probing the QED effects in strong electromagnetic field and the determination of fundamental constants.

  2. Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

    SciTech Connect (OSTI)

    Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

    1992-12-01T23:59:59.000Z

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation.

  3. Comprehensive Nuclear-Test-Ban Treaty seismic monitoring: 2012 USNAS report and recent explosions, earthquakes, and other seismic sources

    SciTech Connect (OSTI)

    Richards, Paul G. [Lamont-Doherty Earth Observatory of Columbia University, 61 Route 9W, Palisades, NY 10964 (United States)

    2014-05-09T23:59:59.000Z

    A comprehensive ban on nuclear explosive testing is briefly characterized as an arms control initiative related to the Non-Proliferation Treaty. The work of monitoring for nuclear explosions uses several technologies of which the most important is seismology-a physics discipline that draws upon extensive and ever-growing assets to monitor for earthquakes and other ground-motion phenomena as well as for explosions. This paper outlines the basic methods of seismic monitoring within that wider context, and lists web-based and other resources for learning details. It also summarizes the main conclusions, concerning capability to monitor for test-ban treaty compliance, contained in a major study published in March 2012 by the US National Academy of Sciences.

  4. Fundamental investigations of underground coal gasification. Annual report Mar 82-Mar 83

    SciTech Connect (OSTI)

    Dunn, R.D.

    1983-03-01T23:59:59.000Z

    Coal deposits in the Appalachian and Midwest Coal Regions consist primarily of thin relatively deep seams of swelling bituminous coal, but little scientific effort in the United States has been directed toward underground coal gasification in these important industrial areas. In Europe, however, major work is under way on underground coal gasification in thin, deep seams of swelling coal. The principal investigator and a graduate student are participating in field tests in Belgium and supporting laboratory experiments in Germany. Mathematical models are being developed to interpret these experimental data, and a better understanding of the underground coal gasification process is emerging. This understanding is essential for evaluating potential problems, for devising solutions to such problems and for designing field tests.

  5. On-site inspection: A brief overview and bibliography of techniques pertinent to assessing suspected nuclear test sites

    SciTech Connect (OSTI)

    Carrigan, C.R.

    1993-03-01T23:59:59.000Z

    The purpose of this report is to provide a brief overview and bibliography of those techniques that may have application for the evaluation of a site to determine if a high energy release event is nuclear in nature. This effort is motivated by recognition of the changing world political climate and the perception that low yield and non-proliferation issues will grow in importance as countries become increasingly involved as signators to treaties that are intended to limit the development and testing of nuclear weapons. Along with an increasing interest in such issues is the awareness of the need to implement improved capabilities for treaty monitoring programs that must deal with assessing suspicious occurrences of high energy release events. In preparing this report, it is recognized that monitoring can take two main forms. The first involves the resolution of unidentified events detected by seismic and satellite National Technical Means. Events of an indeterminate nature could occur world-wide and could induce tension in neighboring countries. If an on-site measurement capability were available, a monitoring team could be sent to the suspected site of an event to take measurements that could confirm or disprove the occurrence of a clandestine nuclear test. The second monitoring form is the confirmation that a clandestine event is not masked by a declared event. For example, a large mining explosion could mask a decoupled nuclear explosion. On-site measurements before and during the test could confirm that a clandestine event did not occur and could provide assurance that the party carrying out the explosion is not taking advantage of clandestine testing opportunities. 48 refs.

  6. Lawrence Livermore National Laboratory Underground Coal Gasification project

    SciTech Connect (OSTI)

    Thorsness, C.B.; Britten, J.A.

    1989-10-15T23:59:59.000Z

    The Lawrence Livermore National Laboratory (LLNL) has been actively developing Underground Coal Gasification (UCG) technology for 15 years. The goal of the project has been to develop a fundamental technological understanding of UCG and foster the commercialization of the process. In striving to achieve this goal the LLNL project has carried out laboratory experiments, developed mathematical models, actively participated in technology transfer programs, and conducted field test experiments. As a result of this work the Controlled Retracting Injection Point (CRIP) concept was developed which helps insure optimum performance of an underground gasifier in a flat seam, and provides a means to produce multiple gasification cavities. The LLNL field work culminated in the Rocky Mountain I field test in which a gasifier using the CRIP technology generated gas of a quality equal to that of surface gasifiers. This last test and others preceding it have demonstrated beyond any reasonable doubt, that UCG is technically feasible in moderately thick coal seams at modest depths. 2 refs., 2 tabs.

  7. Test and evaluation of computerized nuclear material accounting methods. Final report

    SciTech Connect (OSTI)

    NONE

    1995-12-31T23:59:59.000Z

    In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

  8. Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-05-01T23:59:59.000Z

    The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

  9. Simulation of Seismic Waves from Underground Explosions in Geologic Media: FY2009 Progress Report

    SciTech Connect (OSTI)

    Rodgers, A; Vorobiev, O; Sjogreen, B; Petersson, N A

    2009-11-09T23:59:59.000Z

    This report summarizes work done after one year on project LL09-Sim-NDD-02 entitled 'Exploratory Research: Advanced Simulation of Low Yield Underground Nuclear Explosions To Improve Seismic Yield Estimation and Source Identification'. Work on this effort proceeded in two thrusts: (1) parametric studies of underground explosion generated motions with GEODYN; and (2) coupling of GEODYN to WPP. GEODYN is a code for modeling hydrodynamic (shock-wave) motions in a wide variety of materials, including earth materials. WPP is an anelastic finite difference code for modeling seismic motions. The sensitivity of seismic motions to emplacement conditions was investigated with a series of parametric studies of low-yield (0.2-4 kiloton) chemical high-explosive shots at a range of burial depths in four canonical geologic media (granite, limestone, tuff and alluvium). Results indicate that the material has a strong impact on the seismic motions consistent with previous reports. Motions computed with GEODYN in realistically complex material models are very consistent with reported motions from nuclear tests by Perret and Bass (1975). The amplitude, frequency content and cavity size resulting from explosions are all strongly sensitive to the material strength. Explosions in high-strength (granite) resulted in the highest amplitude, shortest duration pulse and smallest cavities, whereas explosions in low-strength material (alluvium) resulted in the lowest amplitudes, longest duration pulse and larger cavities. The corner frequencies of P-wave motions at take-off angles corresponding to propagation to teleseismic distances show corresponding behavior, with high-strength materials having the highest corner frequency and low-strength materials having low corner frequency. Gravity has an important effect on the cavity size and outgoing motions due work done against lithostatic stress. In fact without gravity the cavity radius and elastic motions are largely insensitive to depth of burial. We investigated the effects of depth of burial for a given yield and material model in the presence of gravity and found that the cavity radius is slightly smaller for deeper shots and the resulting motions have shorter duration and higher corner frequency compared to shallower shots. On the second thrust, progress has been made on one-way coupling of GEODYN to WPP. Early in the project we demonstrated this capability from one-dimensional (1D) GEODYN calculations. We have now completed the capability to pass motions computed in 2D or 3D with GEODYN to WPP and propagated (in 3D) to large distances.

  10. Method for making generally cylindrical underground openings

    DOE Patents [OSTI]

    Routh, J.W.

    1983-05-26T23:59:59.000Z

    A rapid, economical and safe method for making a generally cylindrical underground opening such as a shaft or a tunnel is described. A borehole is formed along the approximate center line of where it is desired to make the underground opening. The borehole is loaded with an explodable material and the explodable material is detonated. An enlarged cavity is formed by the explosive action of the detonated explodable material forcing outward and compacting the original walls of the borehole. The enlarged cavity may be increased in size by loading it with a second explodable material, and detonating the second explodable material. The process may be repeated as required until the desired underground opening is made. The explodable material used in the method may be free-flowing, and it may be contained in a pipe.

  11. Application of a Virtual Reactivity Feedback Control Loop in Non-Nuclear Testing of a Fast Spectrum Reactor

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon M. [NASA Marshall Space Flight Center, Huntsville, Al, 35812 (United States); Forsbacka, Matthew [NASA Headquarters, 300 E St. S, Washington, DC 20465 (United States)

    2004-07-01T23:59:59.000Z

    For a compact, fast-spectrum reactor, reactivity feedback is dominated by core deformation at elevated temperature. Given the use of accurate deformation measurement techniques, it is possible to simulate nuclear feedback in non-nuclear electrically heated reactor tests. Implementation of simulated reactivity feedback in response to measured deflection is being tested at the Nasa Marshall Space Flight Center Early Flight Fission Test Facility (EFF-TF). During tests of the SAFE-100 reactor prototype, core deflection was monitored using a high resolution camera. 'Virtual' reactivity feedback was accomplished by applying the results of Monte Carlo calculations (MCNPX) to core deflection measurements; the computational analysis was used to establish the reactivity worth of various core deformations. The power delivered to the SAFE-100 prototype was then adjusted accordingly via kinetics calculations. The work presented in this paper will demonstrate virtual reactivity feedback as core power was increased from 1 kWt to 10 kWt, held approximately constant at 10 kWt, and then allowed to decrease based on the negative thermal reactivity coefficient. (authors)

  12. MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT

    SciTech Connect (OSTI)

    Vinson, D.

    2010-07-11T23:59:59.000Z

    The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe transportation/receipt and interim storage of aluminum research reactor spent fuel and reviews the comprehensive strategy for its management. The U.S. Department of Energy uses the Appendix A, Spent Nuclear Fuel Acceptance Criteria, to identify the physical, chemical, and isotopic characteristics of spent nuclear fuel to be returned to the United States under the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The fuel is further evaluated for acceptance through assessments of the fuel at the foreign sites that include corrosion damage and handleability. Transport involves use of commercial shipping casks with defined leakage rates that can provide containment of the fuel, some of which are breached. Options for safe storage include wet storage and dry storage. Both options must fully address potential degradation of the aluminum during the storage period. This paper focuses on the various options for safe transport and storage with respect to technology maturity and application.

  13. Potential underground risks associated with CAES.

    SciTech Connect (OSTI)

    Kirk, Matthew F.; Webb, Stephen Walter; Broome, Scott Thomas; Pfeifle, Thomas W.; Grubelich, Mark Charles; Bauer, Stephen J.

    2010-10-01T23:59:59.000Z

    CAES in geologic media has been proposed to help 'firm' renewable energy sources (wind and solar) by providing a means to store energy when excess energy was available, and to provide an energy source during non-productive renewable energy time periods. Such a storage media may experience hourly (perhaps small) pressure swings. Salt caverns represent the only proven underground storage used for CAES, but not in a mode where renewable energy sources are supported. Reservoirs, both depleted natural gas and aquifers represent other potential underground storage vessels for CAES, however, neither has yet to be demonstrated as a functional/operational storage media for CAES.

  14. Forced cooling of underground electric power transmission lines : design manual

    E-Print Network [OSTI]

    Brown, Jay A.

    1978-01-01T23:59:59.000Z

    The methodology utilized for the design of a forced-cooled pipe-type underground transmission system is presented. The material is divided into three major parts: (1) The Forced-cooled Pipe-Type Underground Transmission ...

  15. Underground Natural Gas Storage Wells in Bedded Salt (Kansas)

    Broader source: Energy.gov [DOE]

    These regulations apply to natural gas underground storage and associated brine ponds, and includes the permit application for each new underground storage tank near surface water bodies and springs.

  16. Visit to the Deep Underground Science and Engineering Laboratory

    ScienceCinema (OSTI)

    None

    2010-01-08T23:59:59.000Z

    U.S. Department of Energy scientists and administrators join members of the National Science Foundation and South Dakotas Sanford Underground Laboratory for the deepest journey yet to the proposed site of the Deep Underground Science and Engineering Laboratory (DUSEL).

  17. Accident Investigation of the February 5, 2014, Underground Salt...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the...

  18. Assessment of a 40-kilowatt stirling engine for underground mining applications

    SciTech Connect (OSTI)

    Cairelli, J.E.; Kelm, G.G.; Slaby, J.G.

    1982-06-01T23:59:59.000Z

    An assessment of alternative power souces for underground mining applications was performed. A 40-kW Stirling research engine was tested to evaluate its performance and emission characteristics when operated with helium working gas and diesel fuel. The engine, the test facility, and the test procedures are described. Performance and emission data for the engine operating with helium working gas and diesel fuel are reported and compared with data obtained with hydrogen working gas and unleaded gasoline fuel. Helium diesel test results are compared with the characteristics of current diesel engines and other Stirling engines. External surface temperature data are also presented. Emission and temperature results are compared with the Federal requirements for diesel underground mine engines. The durability potential of Stirling engines is discussed on the basis of the experience gaind during the engine tests.

  19. Appendix E: Underground Storage Annual Site Environmental Report

    E-Print Network [OSTI]

    Pennycook, Steve

    Appendix E: Underground Storage Tank Data #12;Annual Site Environmental Report Appendix E: Underground Storage Tank Data E-3 Table E.1. Underground storage tanks (USTs) at the Y-12 Plant Location/95) NA Closure approval 3/95 (6/96) 9714 2334-U 1987 In use 6,000 Gasoline Full Site check NA NA

  20. Appendix C: Underground Storage Annual Site Environmental Report

    E-Print Network [OSTI]

    Pennycook, Steve

    Appendix C: Underground Storage Tank Data #12;#12;Annual Site Environmental Report Appendix C: Underground Storage Tank Data C-3 Table C.1. Underground storage tanks (USTs) at the Y-12 Plant Location/95) NA Closure approval 3/95 (6/96) 9714 2334-U 1987 In use 6,000 Gasoline Full Site check NA Case closed

  1. Appendix C: Underground Storage Annual Site Environmental Report

    E-Print Network [OSTI]

    Pennycook, Steve

    Appendix C: Underground Storage Tank Data #12;#12;Annual Site Environmental Report Appendix C: Underground Storage Tank Data C-3 Table C.1. Underground storage tanks (USTs) at the Y-12 Complex Location/95) NA Closure approval 3/95 (6/96) 9714 2334-U 1987 In use 6,000 Gasoline Full Site check NA Case closed

  2. The Public Perceptions of Underground Coal Gasification (UCG)

    E-Print Network [OSTI]

    Watson, Andrew

    The Public Perceptions of Underground Coal Gasification (UCG): A Pilot Study Simon Shackley #12;The Public Perceptions of Underground Coal Gasification (UCG): A Pilot Study Dr Simon Shackley of Underground Coal Gasification (UCG) in the United Kingdom. The objectives were to identify the main dangers

  3. On-line testing of calibration of process instrumentation channels in nuclear power plants. Phase 2, Final report

    SciTech Connect (OSTI)

    Hashemian, H.M. [Analysis and Measurement Services Corp., Knoxville, TN (United States)

    1995-11-01T23:59:59.000Z

    The nuclear industry is interested in automating the calibration of process instrumentation channels; this report provides key results of one of the sponsored projects to determine the validity of automated calibrations. Conclusion is that the normal outputs of instrument channels in nuclear plants can be monitored over a fuel cycle while the plant is operating to determine calibration drift in the field sensors and associated signal conversion and signal conditioning equipment. The procedure for on-line calibration tests involving calculating the deviation of each instrument channel from the best estimate of the process parameter that the instrument is measuring. Methods were evaluated for determining the best estimate. Deviation of each signal from the best estimate is updated frequently while the plant is operating and plotted vs time for entire fuel cycle, thereby providing time history plots that can reveal channel drift and other anomalies. Any instrument channel that exceeds allowable drift or channel accuracy band is then scheduled for calibration during a refueling outage or sooner. This provides calibration test results at the process operating point, one of the most critical points of the channel operation. This should suffice for most narrow-range instruments, although the calibration of some instruments can be verified at other points throughout their range. It should be pointed out that the calibration of some process signals such as the high pressure coolant injection flow in BWRs, which are normally off- scale during plant operation, can not be tested on-line.

  4. Underground coal gasification simulation. Final report

    SciTech Connect (OSTI)

    Gunn, R.D.

    1984-07-01T23:59:59.000Z

    The underground coal gasification (UCG) process - both forward gasification and reverse combustion linkage - was mathematically modeled. The models were validated with field and laboratory data. They were then used to explain some important UCG phenomena that had not been predictable with other methods. Some views on the UCG technology status are also presented. 3 references, 25 figures, 10 tables.

  5. Minimize environmental impacts when replacing underground pipe

    SciTech Connect (OSTI)

    Miller, L.R. [Ashland Petroleum Co., Catlettsburg, KY (United States); Kroll, T.R. [Insituform Technologies, Inc., Memphis, TN (United States)

    1997-02-01T23:59:59.000Z

    A US refiner urgently needed to repair a 40-year-old oily-water sewer system without disrupting processing operations. Equally important, the refiner wanted to minimize soil and groundwater contamination. In this case history, the refiner elected to use an alternative method--trenchless rehabilitation--to make required underground repairs.

  6. Corrective Action Investigation Plan for Corrective Action Unit 406: Area 3 Building 03-74 and Building 03-58 Under ground Discharge Points and Corrective Action Unit 429: Area 3 Building 03-55 and Area 9 Building 09-52 Underground Discharge Points, Tonopah Test Range, Nevada

    SciTech Connect (OSTI)

    DOE/NV

    1999-05-20T23:59:59.000Z

    This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. Corrective Action Units consist of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the Underground Discharge Points (UDPs) included in both CAU 406 and CAU 429. The CAUs are located in Area 3 and Area 9 of the Tonopah Test Range (TTR). The TTR, included in the Nellis Air Force Range, is approximately 255 kilometers (km) (140 miles [mi]) northwest of Las Vegas, Nevada.

  7. Phase II Documentation Overview of Corrective Action Unit 98: Frenchman Flat, Nevada Test Site, Nye County, Nevada, Revision 1

    SciTech Connect (OSTI)

    Greg Ruskauff

    2010-04-01T23:59:59.000Z

    The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) initiated the Underground Test Area (UGTA) Subproject to assess and evaluate radiologic groundwater contamination resulting from underground nuclear testing at the NTS. These activities are overseen by the Federal Facility Agreement and Consent Order (FFACO) (1996, as amended March 2010). For Frenchman Flat, the UGTA Subproject addresses media contaminated by the underground nuclear tests, which is limited to geologic formations within the saturated zone or 100 meters (m) or less above the water table. Transport in groundwater is judged to be the primary mechanism of migration for the subsurface contamination away from the Frenchman Flat underground nuclear tests. The intent of the UGTA Subproject is to assess the risk to the public from the groundwater contamination produced as a result of nuclear testing. The primary method used to assess this risk is the development of models of flow and contaminant transport to forecast the extent of potentially contaminated groundwater for the next 1,000 years, establish restrictions to groundwater usage, and implement a monitoring program to verify protectiveness. For the UGTA Subproject, contaminated groundwater is that which exceeds the radiological standards of the Safe Drinking Water Act (CFR, 2009) the State of Nevada’s groundwater quality standard to protect human health and the environment. Contaminant forecasts are expected to be uncertain, and groundwater monitoring will be used in combination with land-use control to build confidence in model results and reduce risk to the public. Modeling forecasts of contaminant transport will provide the basis for negotiating a compliance boundary for the Frenchman Flat Corrective Action Unit (CAU). This compliance boundary represents a regulatory-based distinction between groundwater contaminated or not contaminated by underground testing. Transport modeling simulations are used to compute radionuclide concentrations in time and space within the CAU for the 1,000-year contaminant boundary. These three-dimensional (3-D) concentration simulations are integrated into probabilistic forecasts of the likelihood of groundwater exceeding or remaining below the radiological standards of the Safe Drinking Water Act (CFR, 2009) defined as the contaminant boundary. Contaminant boundaries are not discrete predictions of the location or concentration of contaminants, but instead are spatial representations of the probability of exceeding Safe Drinking Water Act radiological standards. The forecasts provide planning tools to facilitate regulatory decisions designed to protect the health and safety of the public.

  8. Arco's research and development efforts in underground coal gasification

    SciTech Connect (OSTI)

    Bell, G.J.; Bailey, D.W.; Brandenburg, C.F.

    1983-01-01T23:59:59.000Z

    Arco has studied underground coal gasification (UCG) since the mid-1970's in an attempt to advance the technology. This paper is a review of past and present UCG research and development efforts, starting with Arco's Rocky Hill No. 1 test. Although this first experiment gave Arco invaluable experience for conducting UCG in the deep, wet, thick coal resources of the Powder River Basin in Wyoming, many formidable questions remain to be addressed with the operation of a larger-scale, multi-well test. Unresolved issues include such items as site selection, well design, well linking, overburden subsidence, ground water protection, surface treatment of product gas, and the interaction of simultaneously operating modules.

  9. Proceedings of the ninth annual underground coal gasification symposium

    SciTech Connect (OSTI)

    Wieber, P.R.; Martin, J.W.; Byrer, C.W. (eds.)

    1983-12-01T23:59:59.000Z

    The Ninth Underground Coal Gasification Symposium was held August 7 to 10, 1983 at the Indian Lakes Resort and Conference Center in Bloomingdale, Illinois. Over one-hundred attendees from industry, academia, National Laboratories, State Government, and the US Government participated in the exchange of ideas, results and future research plans. Representatives from six countries including France, Belgium, United Kingdom, The Netherlands, West Germany, and Brazil also participated by presenting papers. Fifty papers were presented and discussed in four formal sessions and two informal poster sessions. The presentations described current and future field testing plans, interpretation of field test data, environmental research, laboratory studies, modeling, and economics. All papers were processed for inclusion in the Energy Data Base.

  10. Large-block experiments in underground coal gasification

    SciTech Connect (OSTI)

    Not Available

    1982-11-01T23:59:59.000Z

    A major objective of the nation's energy program is to develop processes for cleanly producing fuels from coal. One of the more promising of these is underground coal gasification (UCG). If successful, UCG would quadruple recoverable U.S. coal reserves. Under the sponsorship of the Department of Energy (DOE), Lawrence Livermore National Laboratory (LLNL) performed an early series of UCG field experiments from 1976 through 1979. The Hoe Creek series of tests were designed to develop the basic technology of UCG at low cost. The experiments were conducted in a 7.6-m thick subbituminous coal seam at a relatively shallow depth of 48 m at a site near Gillette, Wyoming. On the basis of the Hoe Creek results, more extensive field experiments were designed to establish the feasibility of UCG for commercial gas production under a variety of gasification conditions. Concepts and practices in UCG are described, and results of the field tests are summarized.

  11. A sweep efficiency model for underground coal gasification

    SciTech Connect (OSTI)

    Chang, H.L.; Edgar, T.F.; Himmelblau, D.M.

    1985-01-01T23:59:59.000Z

    A new model to predict sweep efficiency for underground coal gasification (UCG) has been developed. The model is based on flow through rubble in the cavity as well as through the open channel and uses a tanks-in-series model for the flow characteristics. The model can predict cavity growth and product gas composition given the rate of water influx, roof collapse, and spalling. Self-gasification of coal is taken into account in the model, and the coal consumption rate and the location of the flame front are determined by material and energy balances at the char surface. The model has been used to predict the results of the Hoe Creek III field tests (for the air gasification period). Predictions made by the model such as cavity shape, product gas composition, temperature profile, and overall reaction stoichiometry between the injected oxygen and the coal show reasonable agreement with the field test results.

  12. Coalbed methane production enhancement by underground coal gasification

    SciTech Connect (OSTI)

    Hettema, M.H.H.; Wolf, K.H.A.A.; Neumann, B.V.

    1997-12-31T23:59:59.000Z

    The sub-surface of the Netherlands is generally underlain by coal-bearing Carboniferous strata at greater depths (at many places over 1,500 m). These coal seams are generally thinner than 3 meter, occur in groups (5--15) within several hundred meters and are often fairly continuous over many square kilometers. In many cases they have endured complex burial history, influencing their methane saturation. In certain particular geological settings, a high, maximum coalbed methane saturation, may be expected. Carboniferous/Permian coals in the Tianjin-region (China) show many similarities concerning geological settings, rank and composition. Economical coalbed methane production at greater depths is often obstructed by the (very) low permeabilities of the coal seams as with increasing depth the deformation of the coal reduces both its macro-porosity (the cleat system) and microporosity. Experiments in abandoned underground mines, as well as after underground coal gasification tests indicate ways to improve the prospects for coalbed methane production in originally tight coal reservoirs. High permeability areas can be created by the application of underground coal gasification of one of the coal seams of a multi-seam cycle with some 200 meter of coal bearing strata. The gasification of one of the coal seams transforms that seam over a certain area into a highly permeable bed, consisting of coal residues, ash and (thermally altered) roof rubble. Additionally, roof collapse and subsidence will destabilize the overburden. In conjunction this will permit a better coalbed methane production from the remaining surrounding parts of the coal seams. Moreover, the effects of subsidence will influence the stress patterns around the gasified seam and this improves the permeability over certain distances in the coal seams above and below. In this paper the effects of the combined underground coal gasification and coalbed methane production technique are regarded for a single injection well. Known geotechnical aspects are combined with results from laboratory experiments on compaction of thermally treated rubble. An axi-symmetric numerical model is used to determine the effects induced by the gasified coal seam. The calculation includes the rubble formation, rubble compaction and induced stress effects in the overlying strata. Subsequently the stress effects are related to changes in coal permeability, based on experimental results of McKee et al.

  13. INTEGRAL BENCHMARK DATA FOR NUCLEAR DATA TESTING THROUGH THE ICSBEP AND THE NEWLY ORGANIZED IRPHEP

    SciTech Connect (OSTI)

    J. Blair Briggs; Lori Scott; Yolanda Rugama; Enrico Satori

    2007-04-01T23:59:59.000Z

    The status of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) was last reported in a nuclear data conference at the International Conference on Nuclear Data for Science and Technology, ND-2004, in Santa Fe, New Mexico. Since that time the number and type of integral benchmarks have increased significantly. Included in the ICSBEP Handbook are criticality-alarm / shielding and fundamental physic benchmarks in addition to the traditional critical / subcritical benchmark data. Since ND 2004, a reactor physics counterpart to the ICSBEP, the International Reactor Physics Experiment Evaluation Project (IRPhEP) was initiated. The IRPhEP is patterned after the ICSBEP, but focuses on other integral measurements, such as buckling, spectral characteristics, reactivity effects, reactivity coefficients, kinetics measurements, reaction-rate and power distributions, nuclide compositions, and other miscellaneous-type measurements in addition to the critical configuration. The status of these two projects is discussed and selected benchmarks highlighted in this paper.

  14. Direct Test of the Time-Independence of Fundamental Nuclear Constants Using the Oklo Natural Reactor

    E-Print Network [OSTI]

    Alexander I. Shlyakhter

    2003-08-06T23:59:59.000Z

    [NOTE: This 1983 preprint is being uploaded to arXiv.org after the death of its author, who supported online distribution of his work. Contact info of the submitter is at http://ilya.cc .] The positions of neutron resonances have been shown to be highly sensitive to the variation of fundamental nuclear constants. The analysis of the measured isotopic shifts in the natural fossil reactor at Oklo gives the following restrictions on the possible rates of the interaction constants variation: strong ~2x10^-19 yr^-1, electromagnetic ~5x10^-18 yr^-1, weak ~10^-12 yr^-1. These limits permit to exclude all the versions of nuclear constants contemporary variation discussed in the literature. URL: http://alexonline.info >. For more recent analyses see hep-ph/9606486, hep-ph/0205206 and astro-ph/0204069 .

  15. Progress Letter Report on Bending Fatigue Test System Development for Spent Nuclear Fuel Vibration Integrity Study (Out-of-cell fatigue testing development - Task 2.4)

    SciTech Connect (OSTI)

    Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Cox, Thomas S [ORNL; Baldwin, Charles A [ORNL; Bevard, Bruce Balkcom [ORNL

    2013-08-01T23:59:59.000Z

    Vibration integrity of high burn-up spent nuclear fuel in transportation remains to be a critical component of US nuclear waste management system. The structural evaluation of package for spent fuel transportation eventually will need to see if the content or spent fuel is in a subcritical condition. However, a system for testing and characterizing such spent fuel is still lacking mainly due to the complication involved with dealing radioactive specimens in a hot cell environment. Apparently, the current state-of-the-art in spent fuel research and development is quite far away from the delivery of reliable mechanical property data for the assessment of spent fuels in the transport package evaluation. Under the sponsorship of US NRC, ORNL has taken the challenge in developing a robust testing system for spent fuel in hot cell. An extensive literature survey was carried out and unique requirements of such testing system were identified. The U-frame setup has come to the top among various designs examined for reverse bending fatigue test of spent fuel rod. The U-frame has many features that deserve mentioned here: Easy to install spent fuel rod in test; Less linkages than in conventional bending test setup such as three-point or four-point bending; Target the failure mode relevant to the fracture of spent fuel rod in transportation by focusing on pure bending; The continuous calibrations and modifications resulted in the third generation (3G) U-frame testing setup. Rigid arms are split along the LBB axis at rod sample ends. For each arm, this results in a large arm body and an end piece. Mating halves of bushings were modified into two V-shaped surfaces on which linear roller bearings (LRB) are embedded. The rod specimen is installed into the test fixture through opening and closing slide end-pieces. The 3G apparently has addressed major issues of setup identified in the previous stage and been proven to be eligible to be further pursued in this project. On the other hand, the purchase of universal testing machine or Bose dual LM2 TB was completed and the testing system was delivered to ORNL in August 2012. The preliminary confirmation of the system and on-site training were given by Bose field engineer and regional manager on 8/1-8/2/2012. The calibration of Bose testing system has been performed by ORNL because the integration of ORNL setup into the Bose TestBench occurred after the installation. Major challenge with this process arose from two aspects: 1) the load control involves two load cells, and 2) U-frame setup itself is a non-standard specimen. ORNL has been able to implement the load control through Cycle Indirect along with pinning the U-frame setup. Two meetings with ORNL hot-cell group (November 2012 and January 2013) were held to discuss the potential issues with both epoxy mounting of rigid sleeve and U-frame setup. Many suggestions were provided to make the procedure friendlier to the manipulator in hot cell. Addressing of these suggestions resulted in another cycle of modifications of both vise mold and setup. The initial meeting with ORNL I&C group occurred in November 2012 with regard to the Bose cable modification and design of central panel to integrate the cables and wires. The first round of cable modification and central panel fabrication was completed in February 2012. The testing with the modified cables exhibited substantial noises and the testing system was not shown to be stable. It was believed the cross talk was responsible to the noise, and a central panel with a better grounding and shielding was highly recommended. The central panel has been re-designed and fabricated in March 2013. In the subsequent period, the ORNL made substantial effort to debug the noises with the load cell channel, and to resolve the noises and nonlinearity with RDP LVDTs related to the integration of RDP LVDTs to Bose system. At the same time, ORNL has completed the verification tests of Bose test system, including cycle tests under reversal bending in load control, bending tests under monotonic load, and cycle test

  16. Nuclear systems and testing programs for ITER. Progress report for FY 1998

    SciTech Connect (OSTI)

    NONE

    1998-12-31T23:59:59.000Z

    The effort during this performance period focused on a number of TBWG activities (including test module design and analysis) that were identified and agreed upon (in the presence of the ITER Director and Deputy Director) at TBWG-4. These include: (a) DEMO test module design and performance analysis under pulsed operation; (b) Test program operation plan; (c) Test port design and analysis; (d) Decay heat calculations and safety analysis; (e) Further discussion among the parties to define collaboratory on R and D for the test program as well as possible collaboration on the construction and operation of test articles; (f) Remote handling and ancillary equipment; (g) Criteria for qualifying a blanket module or submodule for actual insertion and testing in ITER; (h) Definition of test module instrumentation and verification of capability to perform in the ITER fusion environment (magnetic field, radiation, heating, etc.); and (i) Analysis to show that the results to be obtained from the test modules as designed can be extrapolated to DEMO and reactor conditions (e.g., higher wall loads and the need to demonstrate tritium self-sufficiency). The main achievements during this performance period include: (1) updating and finalizing the US DDDs for the ITER Blanket Program to form part of the ITER Final Design Report (FDR). Specific revisions were in response to the minimal lithium volume test blanket design requirements and safety impact and (2) evaluating the feasibility of the US test program, including instrumentation and the benefits of the ITER test program. Details of this assessment, including solid breeder and liquid breeder blanket test plans, are documented in UCLA-IFNT-13 (attached). In addition, dose mapping calculations were performed for the ITER Building, including equipment and layout of coolant pipes/heat exchangers. A report on ITER Building dose calculations was sent to UD ITER management and to the Garching Task Coordinator in April, 1998. The report entitled Three-Dimensional Calculations of ITER Building Dose Rate Profiles and Assessment of Accessibility Inside the Building During Operation and After Shutdown of ITER can be located through ITER Reference Number of ITER Task S 62 TD 12, ID No: D325 ITER/US/98/S62TD12-D325 UCLA-FNT-100 UCLA-ENG-98-190.

  17. Sandia National Laboratories: Nuclear Energy Systems Laboratory...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory (NESL) Transient Nuclear Fuels Testing Radiation Effects Sciences Solar Electric Propulsion Nuclear Energy Safety Technologies Experimental Testing...

  18. Sandia National Laboratories: Nuclear Energy Systems Laboratory...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laboratory (NESL) Transient Nuclear Fuels Testing Radiation Effects Sciences Solar Electric Propulsion Nuclear Energy Safety Technologies Experimental Testing Phenomenological...

  19. Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

    SciTech Connect (OSTI)

    West, K.A.

    1988-11-01T23:59:59.000Z

    The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

  20. Lead Test Assembly Irradiation and Analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts associated with the U.S. Department of Energy proposed action to conduct a lead test assembly program to confirm the viability of using a commercial...

  1. Standard test method for nondestructive analysis of special nuclear materials in homogeneous solutions by Gamma-Ray spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This test method covers the determination of the concentration of gamma-ray emitting special nuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the solution and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)). 1.2 Two solution geometries, slab and cylinder, are considered. The solution container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to solution containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass. 1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the solution container, counting equip...

  2. The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2009-09-01T23:59:59.000Z

    The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

  3. Dynamic underground stripping. Innovative technology summary report

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    Dynamic Underground Stripping (DUS) is a combination of technologies targeted to remediate soil and ground water contaminated with organic compounds. DUS is effective both above and below the water table and is especially well suited for sites with interbedded sand and clay layers. The main technologies comprising DUS are steam injection at the periphery of a contaminated area to heat permeable subsurface areas, vaporize volatile compounds bound to the soil, and drive contaminants to centrally located vacuum extraction wells; electrical heating of less permeable sediments to vaporize contaminants and drive them into the steam zone; and underground imaging such as Electrical Resistance Tomography to delineate heated areas to ensure total cleanup and process control. A full-scale demonstration was conducted on a gasoline spill site at Lawrence Livermore National Laboratory in Livermore, California from November 1992 through December 1993.

  4. Rotary steerable motor system for underground drilling

    DOE Patents [OSTI]

    Turner, William E. (Durham, CT); Perry, Carl A. (Middletown, CT); Wassell, Mark E. (Kingwood, TX); Barbely, Jason R. (Middletown, CT); Burgess, Daniel E. (Middletown, CT); Cobern, Martin E. (Cheshire, CT)

    2010-07-27T23:59:59.000Z

    A preferred embodiment of a system for rotating and guiding a drill bit in an underground bore includes a drilling motor and a drive shaft coupled to drilling motor so that drill bit can be rotated by the drilling motor. The system further includes a guidance module having an actuating arm movable between an extended position wherein the actuating arm can contact a surface of the bore and thereby exert a force on the housing of the guidance module, and a retracted position.

  5. Rotary steerable motor system for underground drilling

    DOE Patents [OSTI]

    Turner, William E. (Durham, CT); Perry, Carl A. (Middletown, CT); Wassell, Mark E. (Kingwood, TX); Barbely, Jason R. (Middletown, CT); Burgess, Daniel E. (Middletown, CT); Cobern, Martin E. (Cheshire, CT)

    2008-06-24T23:59:59.000Z

    A preferred embodiment of a system for rotating and guiding a drill bit in an underground bore includes a drilling motor and a drive shaft coupled to drilling motor so that drill bit can be rotated by the drilling motor. The system further includes a guidance module having an actuating arm movable between an extended position wherein the actuating arm can contact a surface of the bore and thereby exert a force on the housing of the guidance module, and a retracted position.

  6. Legislation pertaining to underground storage tanks

    SciTech Connect (OSTI)

    Goth, W. (Ventura County Environmental Health Division, CA (United States))

    1994-04-01T23:59:59.000Z

    Statutory authority in California for cleanup of contaminated soil and groundwater to protect water quality is the Porter Cologne Water Quality Control Act (Water Code 1967). Two state laws regulating underground hazardous material storage tanks, passed in late 1983 and effective on January 1, 1984, were AB-2013 (Cortese) and AB-1362 (Sher). Both require specific actions by the tank owners. AB-2013 requires all tank owners to register them with the state Water Resources Control Board (SWCB) and to pay a registration fee. AB-1362, Health and Safety Code Section 25280 et seq., requires tank owners to obtain a Permit to Operate, pay a fee to the local agency, and to install a leak detection system on all existing tanks. New tanks installation requires a Permit to install and provide provide secondary containment for the tank and piping. For tank closures, a permit must be obtained from the local agency to clean out the tank, remove it from the ground, and collect samples from beneath the tank for evidence of contamination. In 1988, state law AB-853 appropriated state funds to be combined with federal EPA money to allow SWRCB to initiate rapid cleanups of leaks from underground tank sites by contracting with local agencies to oversee assessment and cleanup of underground tank releases. Locally, in Ventura County, there are more than 400 leaking underground tank sites in which petroleum products have entered the groundwater. To date, no public water supplies have been contaminated; however, action in necessary to prevent any future contamination to our water supply. Over 250 leaking tank sites have completed cleanup.

  7. Radiation monitoring around United States nuclear test areas, calendar year 1989

    SciTech Connect (OSTI)

    Not Available

    1990-05-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program conducted during 1989 by the Environmental Protection Agency's (EPA's) Environmental Monitoring Systems Laboratory-Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels, and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether the testing is in compliance with existing radiation protection standards, and to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of both animals and humans. To implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any release of radioactivity, personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each test. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to NTS activities. Trends were evaluated in the Noble Gas and Tritium, Milk Surveillance, TLD, and PIC networks, and the Long-Term Hydrological Monitoring Program. 35 refs., 68 figs., 32 tabs.

  8. Precision physics of simple atoms: QED tests, nuclear structure and fundamental constants

    E-Print Network [OSTI]

    Savely G. Karshenboim

    2005-09-01T23:59:59.000Z

    Quantum electrodynamics is the first successful and still the most successful quantum field theory. Simple atoms, being essentially QED systems, allow highly accurate theoretical predictions. Because of their simple spectra, such atoms have been also efficiently studied experimentally frequently offering the most precisely measured quantities. Our review is devoted to comparison of theory and experiment in the field of precision physics of light simple atoms. In particular, we consider the Lamb shift in the hydrogen atom, the hyperfine structure in hydrogen, deuterium, helium-3 ion, muonium and positronium, as well as a number of other transitions in positronium. Additionally to a spectrum of unperturbed atoms, we consider annihilation decay of positronium and the g factor of bound particles in various two-body atoms. Special attention is paid to the uncertainty of the QED calculations due to the uncalculated higher-order corrections and effects of the nuclear structure. We also discuss applications of simple atoms to determination of several fundamental constants.

  9. Effects of temperature and radiation on the nuclear waste glass product consistency leach test

    SciTech Connect (OSTI)

    Crawford, C.L.; Bibler, N.E.

    1993-01-01T23:59:59.000Z

    Previous leach studies carried out with monolithic glass samples have shown that glass dissolution rates increase with increasing temperature and may or may not increase on exposure to external gamma radiolysis. In this study we have investigated the effects of temperature (70--1200[degrees]C) and radiation on the dissolution of simulated radioactive waste glasses using the Product Consistency Test (PCT). The PCT is a seven day, crushed glass leach test in deionized water that is carried out at 9OO[degrees]C. To date our results indicate no significant effect of external Co--60 gamma radiation when testing various simulated waste glasses at 90[degrees]C in a wellinsulated compartment within a Gammacell 220 irradiation unit. The temperature dependence for glass dissolution clearly exhibits Arrheniustype behavior for two of the three glasses tested. For the third glass the dissolution decreases at the higher temperatures, probably due to saturation effects. Actual radioactive waste glasses will be investigated later as part of this study.

  10. Effects of temperature and radiation on the nuclear waste glass product consistency leach test

    SciTech Connect (OSTI)

    Crawford, C.L.; Bibler, N.E.

    1993-04-01T23:59:59.000Z

    Previous leach studies carried out with monolithic glass samples have shown that glass dissolution rates increase with increasing temperature and may or may not increase on exposure to external gamma radiolysis. In this study we have investigated the effects of temperature (70--1200{degrees}C) and radiation on the dissolution of simulated radioactive waste glasses using the Product Consistency Test (PCT). The PCT is a seven day, crushed glass leach test in deionized water that is carried out at 9OO{degrees}C. To date our results indicate no significant effect of external Co--60 gamma radiation when testing various simulated waste glasses at 90{degrees}C in a wellinsulated compartment within a Gammacell 220 irradiation unit. The temperature dependence for glass dissolution clearly exhibits Arrheniustype behavior for two of the three glasses tested. For the third glass the dissolution decreases at the higher temperatures, probably due to saturation effects. Actual radioactive waste glasses will be investigated later as part of this study.

  11. System Upgrades at the Advanced Test Reactor Help Ensure that Nuclear Energy Research Continues at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Craig Wise

    2011-12-01T23:59:59.000Z

    Fully operational in 1967, the Advanced Test Reactor (ATR) is a first-of-its-kind materials test reactor. Located on the Idaho National Laboratory’s desert site, this reactor remains at the forefront of nuclear science, producing extremely high neutron irradiation in a relatively short time span. The Advanced Test Reactor is also the only U.S. reactor that can replicate multiple reactor environments concurrently. The Idaho National Laboratory and the Department of Energy recently invested over 13 million dollars to replace three of ATR’s instrumentation and control systems. The new systems offer the latest software and technology advancements, ensuring the availability of the reactor for future energy research. Engineers and project managers successfully completed the four year project in March while the ATR was in a scheduled maintenance outage. “These new systems represent state-of-the-art monitoring and annunciation capabilities,” said Don Feldman, ATR Station Manager. “They are comparable to systems currently used for advanced reactor designs planned for construction in the U.S. and in operation in some foreign countries.”

  12. Standard test methods for chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade plutonium dioxide powders and pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade plutonium dioxide powders and pellets to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium Sample Handling 8 to 10 Plutonium by Controlled-Potential Coulometry Plutonium by Ceric Sulfate Titration Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Nitrogen by Distillation Spectrophotometry Using Nessler Reagent 11 to 18 Carbon (Total) by Direct Combustion–Thermal Conductivity 19 to 30 Total Chlorine and Fluorine by Pyrohydrolysis 31 to 38 Sulfur by Distillation Spectrophotometry 39 to 47 Plutonium Isotopic Analysis by Mass Spectrometry Rare Earth Elements by Spectroscopy 48 to 55 Trace Elements by Carrier–Distillation Spectroscopy 56 to 63 Impurities by ICP-AES Impurity Elements by Spark-Source Mass Spectrography 64 to 70 Moisture by the Coulomet...

  13. A review of the factors influencing the physicochemical characteristics of underground coal gasification

    SciTech Connect (OSTI)

    Yang, L.H. [China University of Mining and Technology, Jiangsu (China)

    2008-07-01T23:59:59.000Z

    In this article, the physicochemical characteristics of the oxidation zone, the reduction zone, and the destructive distillation and dry zone in the process of underground coal gasification (UCG) were explained. The effect of such major factors as temperature, coal type, water-inrush or -intake rate, the quantity and quality of wind blasting, the thickness of coal seams, operational pressure, the length, and the section of gasification gallery on the quality of the underground gas and their interrelationship were discussed. Research showed that the temperature conditions determined the underground gas compositions; the appropriate water-inrush or -intake rate was conducive to the improvement in gas heat value; the properties of the gasification agent had an obvious effect on the compositions and heat value of the product gas. Under the cyclically changing pressure, heat losses decreased by 60%, with the heat efficiency and gasification efficiency being 1.4 times and 2 times those of constant pressure, respectively. The test research further proved that the underground gasifier with a long channel and a big cross-section, to a large extent, improved the combustion-gasification conditions.

  14. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1997

    SciTech Connect (OSTI)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01T23:59:59.000Z

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency`s (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods.

  15. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    SciTech Connect (OSTI)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G. [and others

    1996-06-01T23:59:59.000Z

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans.

  16. Study on the colloids generated from testing of high-level nuclear waste glasses

    SciTech Connect (OSTI)

    Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.J.

    1993-03-01T23:59:59.000Z

    The generation of colloids in the interaction of high-level nuclear waste glasses with groundwater at 90{degrees}C has been investigated. The stability of the colloidal suspensions has been characterized with respect to salt concentration, pH time, particle size, and zeta potential. The compositions and the morphology of the colloids have also been determined with transmission electron microscopy (TEM). From ourtest results combined with earlier ones, we conclude that the waste glass may contribute to the colloid formation by increasing ion concentration in groundwater, which causes nucleation of colloids; by releasing radionuclides that adsorb onto existing groundwater colloids; and by spalling colloidal-size fragments from the surface layer of the reacted glass. The colloids are silicon-rich particles, such as smectites and uranium silicates. When the salt concentration in the solution is high the colloidal suspensions agglomerate. However, the agglomerated particles can be resuspended if the salt concentration is lowered by dilution with groundwater. The colloids agglomerate quickly after the leachate is cooled to room temperature. Most of the colloids settle out of the solution within a few days at ambient temperature. The isoelectric point is at a pH of approximately 1.0. Between pH 1 and 10.5, the colloids are negatively charged, which suggests that they will deposit readily on, positively charged surfaces. The average particle size islargest at the isoelectric point and is smallest around pH 6.

  17. Study on the colloids generated from testing of high-level nuclear waste glasses

    SciTech Connect (OSTI)

    Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.J.

    1993-01-01T23:59:59.000Z

    The generation of colloids in the interaction of high-level nuclear waste glasses with groundwater at 90[degrees]C has been investigated. The stability of the colloidal suspensions has been characterized with respect to salt concentration, pH time, particle size, and zeta potential. The compositions and the morphology of the colloids have also been determined with transmission electron microscopy (TEM). From ourtest results combined with earlier ones, we conclude that the waste glass may contribute to the colloid formation by increasing ion concentration in groundwater, which causes nucleation of colloids; by releasing radionuclides that adsorb onto existing groundwater colloids; and by spalling colloidal-size fragments from the surface layer of the reacted glass. The colloids are silicon-rich particles, such as smectites and uranium silicates. When the salt concentration in the solution is high the colloidal suspensions agglomerate. However, the agglomerated particles can be resuspended if the salt concentration is lowered by dilution with groundwater. The colloids agglomerate quickly after the leachate is cooled to room temperature. Most of the colloids settle out of the solution within a few days at ambient temperature. The isoelectric point is at a pH of approximately 1.0. Between pH 1 and 10.5, the colloids are negatively charged, which suggests that they will deposit readily on, positively charged surfaces. The average particle size islargest at the isoelectric point and is smallest around pH 6.

  18. Rawlins UCG (underground coal gasification) Demonstration Project site characterization report

    SciTech Connect (OSTI)

    Not Available

    1989-04-01T23:59:59.000Z

    The United States Department of Energy and Energy International, Inc. have entered into a Cooperative Agreement to conduct a cost-shared UCG field test demonstrating the operation of commercial scale Underground Coal Gasification (UCG) on steeply dipping bed modules to provide synthesis gas for a small scale commercial ammonia plant. The field test and the commercial ammonia plant will be located at the North Knobs site near Rawlins, Wyoming. During this demonstration test, two or more UCG modules will be operated simultaneously until one module is completely consumed and an additional module is brought on line. During this period, the average coal gasification rate will be between 500 and 1200 tons per day. A portion of the raw UCG product gas will be cleaned and converted into a synthesis gas, which will be used as feedstock to a 400--500 ton per day ammonia plant. The UCG facility will continue to operate subsequent to the test demonstration to provide feedstock for the commercial plant. The objective of the hydrologic site characterization program is to provide an accurate representation of the hydrologic environment within the area to be gasified. This information will aid in the placement and operation of the process wells in relation to the ground water source. 21 refs., 14 figs., 6 tabs.

  19. Rawlins UCG (underground coal gasification) Demonstration Project site characterization report

    SciTech Connect (OSTI)

    Not Available

    1989-04-01T23:59:59.000Z

    The US Department of Energy and Energy International, Inc. have entered into a Cooperative Agreement to conduct a cost-shared UCG field test demonstrating the operation of commercial scale underground coal gasification (UCG) on steeply dipping bed modules to provide synthesis gas for a small scale commercial ammonia plant. The field test and the commercial ammonia plant will be located at the North Knobs site near Rawlins, Wyoming. During this demonstration test, two or more UCG modules will be operated simultaneously until one module is completely consumed and an additional module is brought on line. During this period, the average coal gasification rate will be between 500 and 1200 tons per day. A portion of the raw UCG product gas will be cleaned and converted into a synthesis gas, which will be used as feedstock to a 400--500 ton per day ammonia plant. The UCG facility will continue to operate subsequent to the test demonstration to provide feedstock for the commercial plant. The objective of the geologic site characterization program is to provide a descriptive model that accurately represents the geologic environment of the coal resource that is to be gasified. This model is to be used as an aid in understanding the hydrology of the coal bearing sequence, as a framework for installation of the process wells and the subsequent exploitation of the coal resources. 3 figs., 3 tabs.

  20. Analysis of mathematical models of underground coal gasification

    SciTech Connect (OSTI)

    Fausett, L.V.

    1984-01-01T23:59:59.000Z

    Results are reported of a survey and comparison of forward combustion underground coal gasification (UCG) models that are available in the public domain. The six models obtained for study were mathematically analyzed to determine their conceptual completeness and computational complexity. The computer code for each model was implemented on the University of Wyoming CDC CYBER 730/760 computer system. Computed analyses were made with each of the programs using data to simulate six representative UCG field tests. Four of the field tests were air injection experiments and two were oxygen/steam. Modifications were necessary to two models in order for them to simulate oxygen/steam injection experiments. A mistake in the computer code for one model was discovered and corrected; this enabled the code to execute with data from one field test for which the original version had failed. An alternate numerical solution technique for one mdoel was studied, and improved correlations for the model were developed. An approximate analytical solution to the model was obtained that is valid over the region where difficulties were encountered, using both multiple shooting and collocation numerical solutions. The applicability of each model to the various conditions occurring in the different field tests was determined.

  1. EPA - Ground Water Discharges (EPA's Underground Injection Control...

    Open Energy Info (EERE)

    Discharges (EPA's Underground Injection Control Program) webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: EPA - Ground Water Discharges (EPA's...

  2. Utah Division of Environmental Response and Remediation Underground...

    Open Energy Info (EERE)

    Environmental Response and Remediation Underground Storage Tank Branch Webpage Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Utah Division of...

  3. Alabama Underground Storage Tank And Wellhead Protection Act...

    Broader source: Energy.gov (indexed) [DOE]

    commission, is authorized to promulgate rules and regulations governing underground storage tanks and is authorized to seek the approval of the United States Environmental...

  4. ,"Lower 48 States Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  5. ,"AGA Producing Region Underground Natural Gas Storage - All...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  6. ,"AGA Western Consuming Region Underground Natural Gas Storage...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  7. ,"West Virginia Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  8. ,"AGA Eastern Consuming Region Underground Natural Gas Storage...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  9. ,"New York Underground Natural Gas Storage - All Operators"

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  10. ,"New Mexico Underground Natural Gas Storage - All Operators...

    U.S. Energy Information Administration (EIA) Indexed Site

    Underground Natural Gas Storage - All Operators" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for"...

  11. EA-1943: Long Baseline Neutrino Facility/Deep Underground Neutrino...

    Broader source: Energy.gov (indexed) [DOE]

    and at a "far detector," at the Sanford Underground Research Facility (SURF) in Lead, South Dakota. NOTE: This Project was previously designated (DOEEA-1799). Further...

  12. Progress Continues Toward Closure of Two Underground Waste Tanks...

    Broader source: Energy.gov (indexed) [DOE]

    fiscal year 2013, which ended Sept. 30, SRR reached contract milestones in the Interim Salt Disposition Process, which treats salt waste from the underground storage tanks. Salt...

  13. Pore Models Track Reactions in Underground Carbon Capture

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    want to model what happens to the crystals' geochemistry when the greenhouse gas carbon dioxide is injected underground for sequestration. Image courtesy of David...

  14. Comparative tests of isospin-symmetry-breaking corrections to superallowed 0(+) -> 0(+) nuclear beta decay

    E-Print Network [OSTI]

    Towner, I. S.; Hardy, John C.

    2010-01-01T23:59:59.000Z

    it is influenced by the Coulomb interaction with all 065501-2 COMPARATIVE TESTS OF ISOSPIN-SYMMETRY- . . . PHYSICAL REVIEW C 82, 065501 (2010) the other protons in the nucleus. If the other protons present a uniform charge distribution of radius R..., then the Coulomb interaction for a proton at r < R is Vc(r) = ?Ze 2 R3 A? i=1 ( 1 2 r2i ? 3 2 R2 )[ 1 2 ? tz(i) ] ?(r ? ri), (6) where tz(i) = ? 12 if nucleon i is a proton and + 12 if it is a neutron. Using an oscillator model as a basis...

  15. Nuclear Physics: Campaigns

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Free-Electron Laser (FEL) Medical Imaging Physics Topics Campaigns The Structure of the Nuclear Building Blocks The Structure of Nuclei Symmetry Tests in Nuclear Physics Meetings...

  16. LLNL Underground Coal Gasification Project annual report - fiscal year 1984

    SciTech Connect (OSTI)

    Stephens, D.R.; O'Neal, E.M. (eds.)

    1985-06-15T23:59:59.000Z

    The Laboratory has been conducting an interdisciplinary underground coal gasification program since 1974 under the sponsorship of DOE and its predecessors. We completed three UCG tests at the Hoe Creek site near Gillette, Wyoming, during the period 1975 to 1979. Five small field experiments, the large-block tests, were completed from 1981 to 1982 at the exposed coal face in the WIDCO coal mine near Centralia, Washington. A larger test at the same location, the partial-seam CRIP test, was completed during fiscal year 1984. In conjunction with the DOE and an industrial group lead by the Gas Research Institute, we have prepared a preliminary design for a large-scale test at the WIDCO site. The planned test features dual injection and production wells, module interaction, and consumption of 20,000 tons of coal during a hundred-day steam-oxygen gasification. During fiscal year 1984, we documented the large-block excavations. The cavities were elongated, the cavity cross sections were elliptical, and the cavities contained ash and slag at the bottom, char and dried coal above that, and a void at the top. The results from the large-block tests provided enough data to allow us to construct a composite model, CAVSM. Preliminary results from the model agree well with the product-gas chemistry and cavity shape observed in the large-block tests. Other models and techniques developed during the year include a transient, moving-front code, a two-dimensional, reactive-flow code using the method of lines, and a wall-recession-rate model. In addition, we measured the rate of methane decomposition in the hot char bed and developed an engineering rate expression to estimate the magnitude of the methane-decomposition reaction. 16 refs., 30 figs., 1 tab.

  17. High resolution seismic survey (of the) Rawlins, Wyoming underground coal gasification area. Final report

    SciTech Connect (OSTI)

    Youngberg, A.D.; Berkman, E.; Orange, A.S.

    1983-01-01T23:59:59.000Z

    In October 1982, a high resolution seismic survey was conducted at the Gulf Research and Development Company's underground coal gasification test site near Rawlins, Wyoming. The objectives of the survey were to utilize high resolution seismic technology to locate and characterize two underground coal burn zones. Seismic data acquisition and processing parameters were specifically designed to emphasize reflections at the shallow depths of interest. A three-dimensional grid of data was obtained over the Rawlins burn zones. Processing included time varying filters, trace composition, and two-dimensional areal stacking of the data in order to identify burn zone anomalies. An anomaly was discernable resulting from the rubble-collapse cavity associated with the burn zone which was studied in detail at the Rawlins 1 and 2 test sites. 21 refs., 20 figs.

  18. COST AND SCHEDULE FOR DRILLING AND MINING UNDERGROUND TEST FACILITIES

    E-Print Network [OSTI]

    Lamb, D.W.

    2013-01-01T23:59:59.000Z

    SHAFT SINKING IN-MINE DRILLiNG NEW MINE - 1500 M SURFACEORILUNG SHAFT SINKiNG FACIUTY DEVELOPMENT IN-MINE DRILLINGSURFACE DRILLING FACIUTY DEVELOPMENT IN-MINE DRILLING ~~NGM!

  19. Underground Flow Measurement and Particle Release Test | Department of

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium TransferonUS-India Energy Dialogue: CoalBiofuelsUncle Sam

  20. Nevada National Security Site Underground Test Area (UGTA) Flow and

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSAR - T en Y ear R enewable E nergyEnergyNeed fortoStreams

  1. Nevada National Security Site Underground Test Area (UGTA) Tour |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSAR - T en Y ear R enewable E nergyEnergyNeed

  2. Nevada National Security Site Underground Test Area (UGTA) Tour |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked QuestionsDepartment of EnergyofPROTECTINGofNavy'sNet-Zero Campus|Department

  3. Direct containment heating experiments in Zion Nuclear Power Plant Geometry using prototypic core materials, the U2 test

    SciTech Connect (OSTI)

    Binder, J.L.; McUmber, L.M.; Spencer, B.W.

    1993-05-01T23:59:59.000Z

    A third Direct Containment Heating (DCH) experiments has been completed which utilizes prototypic core materials. The reactor material tests are a follow on to the Integral Effects Testing (IET) DCH program. The IET series of tests primarily addressed the effect of scale on DCH phenomena. This was accomplished by completing a series of counterpart tests in 1/40 and 1/10th linear scale DCH facilities at Argonne National Laboratory (ANL) and Sandia National Laboratories (SNL), respectively. The IET experiments modeled the Zion Nuclear Power Plant Geometry. The scale models included representations of the primary system volume, RPV lower head, cavity and instrument tunnel, and the lower containment structures. The experiments were steam driven at nominally 6.2 MPa. Iron-alumina thermite with chromium was used as a core melt simulant in the IET experiments. While the IET experiments at ANL and SNL provided useful data on the effect of scale on DCH phenomena, a significant question concerns the potential experiment distortions introduced by the use of non-prototypic iron/alumina thermite. Therefore, further testing with prototypic materials has been carried out at ANL. A prototypic core melt was produced for the experiment by first mixing powders of uranium, zirconium, iron oxide (Fe{sub 2}O{sub 3}), and chromium trioxide (CrO{sub 3}). When ignited the powders react exothermically to produce a molten mixture. The amounts of each powder were selected to produce the anticipated composition for a core melt following a station blackout: 57.8 mass% UO{sub 2} 10.5 mass% ZrO{sub 2} 14.3 mass% Fe, 13.7 mass% Zr, and 3.7 mass% Cr. Development tests measured the initial melt temperature to be in the range of 2600 - 2700 K. The total thermal specific energy content of the melt at 2700 K is 1.2 MJ/kg compared to 2.25 MJ/kg for the iron-alumina simulant at its measured initial temperature of 2500 K.

  4. Flow Components in a NaK Test Loop Designed to Simulate Conditions in a Nuclear Surface Power Reactor

    SciTech Connect (OSTI)

    Polzin, Kurt A.; Godfroy, Thomas J. [NASA Marshall Space Flight Center Propulsion Research and Technology Applications Branch/ER24, MSFC, AL 35812 (United States)

    2008-01-21T23:59:59.000Z

    A test loop using NaK as the working fluid is presently in use to study material compatibility effects on various components that comprise a possible nuclear reactor design for use on the lunar surface. A DC electromagnetic (EM) pump has been designed and implemented as a means of actively controlling the NaK flow rate through the system and an EM flow sensor is employed to monitor the developed flow rate. These components allow for the matching of the flow rate conditions in test loops with those that would be found in a full-scale surface-power reactor. The design and operating characteristics of the EM pump and flow sensor are presented. In the EM pump, current is applied to a set of electrodes to produce a Lorentz body force in the fluid. A measurement of the induced voltage (back-EMF) in the flow sensor provides the means of monitoring flow rate. Both components are compact, employing high magnetic field strength neodymium magnets thermally coupled to a water-cooled housing. A vacuum gap limits the heat transferred from the high temperature NaK tube to the magnets and a magnetically-permeable material completes the magnetic circuit. The pump is designed to produce a pressure rise of 34.5 kPa, and the flow sensor's predicted output is roughly 20 mV at the loop's nominal flow rate of 0.114 m{sup 3}/hr.

  5. Standard test method for determination of impurities in nuclear grade uranium compounds by inductively coupled plasma mass spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This test method covers the determination of 67 elements in uranium dioxide samples and nuclear grade uranium compounds and solutions without matrix separation by inductively coupled plasma mass spectrometry (ICP-MS). The elements are listed in Table 1. These elements can also be determined in uranyl nitrate hexahydrate (UNH), uranium hexafluoride (UF6), triuranium octoxide (U3O8) and uranium trioxide (UO3) if these compounds are treated and converted to the same uranium concentration solution. 1.2 The elements boron, sodium, silicon, phosphorus, potassium, calcium and iron can be determined using different techniques. The analyst's instrumentation will determine which procedure is chosen for the analysis. 1.3 The test method for technetium-99 is given in Annex A1. 1.4 The values stated in SI units are to be regarded as standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish ...

  6. Water pollution control for underground coal gasification

    SciTech Connect (OSTI)

    Humenick, M.J.

    1984-06-01T23:59:59.000Z

    Water pollution arising from underground gasification of coal is one of the important considerations in the eventual commercialization of the process. Because many coal seams which are amenable to in situ gasification are also ground-water aquifers, contaminants may be released to these ground waters during and after gasification. Also, when product gas is processed above ground for use, wastewater streams are generated which are too polluted to be discharged. The purpose of this paper is to characterize the nature of the groundwater and above-ground pollutants, discuss the potential long and short-term effects on ground water, propose control and restoration strategies, and to identify potential wastewater treatment schemes.

  7. Method of locating underground mines fires

    DOE Patents [OSTI]

    Laage, Linneas (Eagam, MN); Pomroy, William (St. Paul, MN)

    1992-01-01T23:59:59.000Z

    An improved method of locating an underground mine fire by comparing the pattern of measured combustion product arrival times at detector locations with a real time computer-generated array of simulated patterns. A number of electronic fire detection devices are linked thru telemetry to a control station on the surface. The mine's ventilation is modeled on a digital computer using network analysis software. The time reguired to locate a fire consists of the time required to model the mines' ventilation, generate the arrival time array, scan the array, and to match measured arrival time patterns to the simulated patterns.

  8. 100-N Area underground storage tank closures

    SciTech Connect (OSTI)

    Rowley, C.A.

    1993-08-01T23:59:59.000Z

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D.

  9. 3He- and 4He-induced nuclear fission - a test of the transition state method

    E-Print Network [OSTI]

    Th. Rubehn; K. X. Jing; L. G. Moretto; L. Phair; K. Tso; G. J. Wozniak

    1997-04-18T23:59:59.000Z

    Fission in 3He and 4He induced reactions at excitation energies between the fission barrier and 140 MeV has been investigated. Twentythree fission excitation functions of various compound nuclei in different mass regions are shown to scale exactly according to the transition state prediction once the shell effects are accounted for. New precise measurements of excitation functions in a mass region where shell effects are very strong, allow one to test the predictions with an even higher accuracy. The fact that no deviations from the transition state method have been observed within the experimentally investigated excitation energy regime allows one to assign limits for the fission transient time. The precise measurement of fission excitation functions of neighboring isotopes enables us to experimentally estimate the first chance fission probability. Even if only first chance fission is investigated, no evidence for fission transient times larger than 30 zs can be found.

  10. Standard test method for the determination of uranium by ignition and the oxygen to uranium (O/U) atomic ratio of nuclear grade uranium dioxide powders and pellets

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2000-01-01T23:59:59.000Z

    1.1 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear grade uranium dioxide powder and pellets. 1.2 This test method does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this test method does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.4 This test method also is applicable to UO3 and U3O8 powder.

  11. Iron oxide aerosol experiments in steam-air atmospheres: NSPP (Nuclear Safety Pilot Plant) tests 501-505 and 511: Data record report

    SciTech Connect (OSTI)

    Adams, R.E.; Tobias, M.L.

    1987-02-01T23:59:59.000Z

    This data record report summarizes the results from five tests involving Fe/sub 2/O/sub 3/ test aerosol in a steam-air environment and one test in a dry air environment. This research sponsored by the US Nuclear Regulatory Commission was conducted in the Nuclear Safety Pilot Plant at the Oak Ridge National Laboratory. The purpose of this project is to provide a data base on the behavior of aerosols in containment under conditions assumed to occur in postulated LWR accident sequences; this data base will provide experimental validation of aerosol behavioral codes under development. In the report a brief description is given of each test together with the results in the form of tables and graphs. Included are data on aerosol mass concentration, aerosol fallout and plateout rates, total mass fallout and plateout, aerosol particle size, vessel atmosphere pressure, vessel atmosphere temperatures, temperature gradients near the vessel wall, and steam condensation rates on the vessel wall.

  12. Limestone concrete aerosol experiments in steam-air atmospheres: NSPP (Nuclear Safety Pilot Plant) Tests 521, 522, and 531: Data record report

    SciTech Connect (OSTI)

    Tobias, M.L.; Adams, R.E.

    1987-10-01T23:59:59.000Z

    This data record report summarizes the results from two tests involving limestone concrete test aerosol in a steam-air environment and one test in a dry air environment. This research sponsored by the US Nuclear Regulatory Commission was conducted in the Nuclear Safety Pilot Plant at the Oak Ridge National Laboratory. The purpose of this project is to provide a data base on the behavior of aerosols in containment under conditions assumed to occur in postulated LWR accident sequences; this data base will provide experimental validation of aerosol behavioral codes under development. In the report a brief description is given of each test together with the results in the form of tables and graphs. Included are data on aerosol mass concentration, aerosol fallout and plateout rates, total mass fallout and plateout, aerosol particle size, vessel atmosphere pressure, vessel atmosphere temperatures, temperature gradients near the vessel wall, and steam condensation rates on the vessel wall.

  13. Development and experimental validation of a calculation scheme for nuclear heating evaluation in the core of the OSIRIS material testing reactor

    SciTech Connect (OSTI)

    Malouch, F. [Saclay Center CEA, DEN/DANS/DM2S/SERMA, F-91191 Gif-sur-Yvette Cedex (France)

    2011-07-01T23:59:59.000Z

    The control of the temperature in material samples irradiated in a material testing reactor requires the knowledge of the nuclear heating caused by the energy deposition by neutrons and photons interacting in the irradiation device structures. Thus, a neutron-photonic three-dimensional calculation scheme has been developed to evaluate the nuclear heating in experimental devices irradiated in the core of the OSIRIS MTR reactor (CEA/Saclay Center). The aim is to obtain a predictive tool for the nuclear heating estimation in irradiation devices. This calculation scheme is mainly based on the TRIPOLI-4 three-dimensional continuous-energy Monte Carlo transport code, developed by CEA (Saclay Center). An experimental validation has been carried out on the basis of nuclear heating measurements performed in the OSIRIS core. After an overview of the experimental devices irradiated in the OSIRIS reactor, we present the calculation scheme and the first results of the experimental validation. (authors)

  14. Radiation Testing of a Low Voltage Silicone Nuclear Power Plant Cable.

    SciTech Connect (OSTI)

    White II, Gregory Von; Schroeder, John Lee.; Sawyer, Patricia Sue.; Wichhart, Derek; Mata, Guillermo Adrian; Zorrilla, Jorge; Bernstein, Robert

    2014-09-01T23:59:59.000Z

    This report summarizes the results generated in FY13 for cable insulation in support of the Department of Energy's Light Water Reactor Sustainability (LWRS) Program, in collaboration with the US-Argentine Binational Energy Working Group (BEWG). A silicone (SiR) cable, which was stored in benign conditions for ~30 years, was obtained from Comision Nacional de Energia Atomica (CNEA) in Argentina with the approval of NA-SA (Nucleoelectrica Argentina Sociedad Anonima). Physical property testing was performed on the as-received cable. This cable was artificially aged to assess behavior with additional analysis. SNL observed appreciable tensile elongation values for all cable insulations received, indicative of good mechanical performance. Of particular note, the work presented here provides correlations between measured tensile elongation and other physical properties that may be potentially leveraged as a form of condition monitoring (CM) for actual service cables. It is recognized at this point that the polymer aging community is still lacking the number and types of field returned materials that are desired, but Sandia National Laboratories (SNL) -- along with the help of others -- is continuing to work towards that goal. This work is an initial study that should be complimented with location-mapping of environmental conditions of Argentinean plant conditions (dose and temperature) as well as retrieval, analysis, and comparison with in- service cables.

  15. Radiation Testing of a Low Voltage Silicone Nuclear Power Plant Cable.

    SciTech Connect (OSTI)

    Bernstein, Robert

    2014-08-01T23:59:59.000Z

    This report summarizes the results generated in FY13 for cable insulation in support of DOE's Light Water Reactor Sustainability (LWRS) Program, in collaboration with the US- Argentine Binational Energy Working Group (BEWG). A silicone (SiR) cable, which was stored in benign conditions for ~30 years, was obtained from Comision Nacional de Energia Atomica (CNEA) in Argentina. Physical property testing was performed on the as-received cable. This cable was artificially aged to assess behavior with additional analysis. SNL observed appreciable tensile elongation values for all cable insulations received, indicative of good mechanical performance. Of particular note, the work presented here provides correlations between measured tensile elongation and other physical properties that may be potentially leveraged as a form of condition monitoring (CM) for actual service cables. It is recognized at this point that the polymer aging community is still lacking the number and types of field returned materials that are desired, but SNL -- along with the help of others -- is continuing to work towards that goal. This work is an initial study that should be complimented with location- mapping of environmental conditions of CNEA plant conditions (dose and temperature) as well as retrieval, analysis, and comparison with in-service cables.

  16. J. H. Scofield and D. M. Fleetwood, IEEE Transactions on Nuclear Science NS-38, 1567-77 (December 1991). PHYSICAL BASIS FOR NONDESTRUCTIVE TESTS OF MOS RADIATION HARDNESS*

    E-Print Network [OSTI]

    Scofield, John H.

    J. H. Scofield and D. M. Fleetwood, IEEE Transactions on Nuclear Science NS-38, 1567-77 (December 1991). PHYSICAL BASIS FOR NONDESTRUCTIVE TESTS OF MOS RADIATION HARDNESS* John H. Scofield Department techniques that improve the radiation hardness of MOS devices at room temperature can greatly reduce the 1/f

  17. Simulation of neutrons produced by high-energy muons underground

    E-Print Network [OSTI]

    A. Lindote; H. M. Araujo; V. A. Kudryavtsev; M. Robinson

    2009-02-12T23:59:59.000Z

    This article describes the Monte Carlo simulation used to interpret the measurement of the muon-induced neutron flux in the Boulby Underground Laboratory (North Yorkshire, UK), recently performed using a large scintillator veto deployed around the ZEPLIN-II WIMP detector. Version 8.2 of the GEANT4 toolkit was used after relevant benchmarking and validation of neutron production models. In the direct comparison between Monte Carlo and experimental data, we find that the simulation produces a 1.8 times higher neutron rate, which we interpret as over-production in lead by GEANT4. The dominance of this material in neutron production allows us to estimate the absolute neutron yield in lead as (1.31 +/- 0.06) x 10^(-3) neutrons/muon/(g/cm^2) for a mean muon energy of 260 GeV. Simulated nuclear recoils due to muon-induced neutrons in the ZEPLIN-II target volume (~1 year exposure) showed that, although a small rate of events is expected from this source of background in the energy range of interest for dark matter searches, no event survives an anti-coincidence cut with the veto.

  18. Permanent Closure of the TAN-664 Underground Storage Tank

    SciTech Connect (OSTI)

    Bradley K. Griffith

    2011-12-01T23:59:59.000Z

    This closure package documents the site assessment and permanent closure of the TAN-664 gasoline underground storage tank in accordance with the regulatory requirements established in 40 CFR 280.71, 'Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.'

  19. Management of dry flue gas desulfurization by-products in underground mines. Topical report, April 1, 1996--April 30, 1997

    SciTech Connect (OSTI)

    Chugh, Y.P.; Brackebusch, F.; Carpenter, J. [and others

    1998-12-31T23:59:59.000Z

    This report represents the Final Technical Progress Report for Phase II of the overall program for a cooperative research agreement between the U.S. Department of Energy - MORGANTOWN Energy Technology Center (DOE-METC) and Southern Illinois University at Carbondale (SIUC). Under the agreement, SIUC will develop and demonstrate technologies for the handling, transport, and placement in abandoned underground coal mines of dry flue gas desulfurization by-products, such as fly ash, scrubber sludge, fluidized bed combustion by-products, and will assess the environmental impact of such underground placement. The overall program is divided into three (3) phases. Phase II of the program is primarily concerned with developing and testing the hardware for the actual underground placement demonstrations. Two technologies have been identified and hardware procured for full-scale demonstrations: (1) hydraulic placement, where coal combustion by-products (CCBs) will be placed underground as a past-like mixture containing about 70 to 75 percent solids; and (2) pneumatic placement, where CCBs will be placed underground as a relatively dry material using compressed air. 42 refs., 36 figs., 36 tabs.

  20. Initial comparison of leach behavior between fully radioactive and simulated nuclear waste glasses through long-term testing

    SciTech Connect (OSTI)

    Feng, Xiangdong; Bates, J.K.

    1992-01-01T23:59:59.000Z

    A comparison of glass reactivity between radioactive sludge based and simulated nuclear waste glasses has been made through long-term testing of both glass types for SRL 165, SRL 131, and SRL 200 frit compositions. The data demonstrate that for time periods through 280 days, differences in elemental release to solution up to 400% are observed. However, in general, differences in glass reactivity as measured by the release of boron, lithium, and sodium are less than a factor of two. The differences in reactivity are not large enough to alter the order of glass durability for the different compositions or to change the controlling glass dissolution mechanism. A radiation effect exists, mainly in the influence on the leachate pH, which in turn affects the glass reaction mechanism and rate. The differences in reactivity between fully radioactive and the simulated glasses can be reasonably explained if the controlling reaction mechanism is accounted for. Those differences are glass composition and leaching mechanism dependent. Lithium is found to have the highest elemental release in an ion-exchange dominated glass reaction process, while lithium has a lower release than boron and sodium in a matrix dissolution dominated process, where boron and sodium are usually among the most concentrated solution species.

  1. Results from the third LLL underground coal gasification experiment at Hoe Creek

    SciTech Connect (OSTI)

    Hill, R.W.; Thorsness, C.B.; Cena, R.J.; Aiman, W.R.; Stephens, D.R.

    1980-05-20T23:59:59.000Z

    A major objective of the US Energy Program is the development of processes to produce clean fuels from coal. Underground coal gasification is one of the most promising of these processes. If successful, underground coal gasification (UCG) would quadruple the proven reserves of the US coal. Cost for products produced from UCG are projected to be 65 to 75% of those from conventional coal conversion. Finally, UCG appears to possess environmental advantages since no mining is involved and there are less solid wastes produced. In this paper we describe results from the Hoe Creek No. 3 underground coal gasification test. The experiment employed a drilled channel between process wells spaced 130' apart. The drilled channel was enlarged by reverse combustion prior to forward gasification. The first week of forward gasification was carried out using air injection, during which 250 tons of coal were consumed yielding an average dry product gas heating value of 114 Btu/scf. Following this phase, steam and oxygen were injected (generally a 50-50 mixture) for 47 days, during which 3945 tons of coal were consumed at an average rate of 84 tons of coal per day and an average dry gas heating value of 217 Btu/scf. The average gas composition during the steam-oxygen phase was 37% H/sub 2/, 5% CH/sub 4/, 11% CO, and 44% CO/sub 2/. Gas recovery was approximately 82% during the test, and the average thermochemical efficiency was near 65%.

  2. Analysis of forward combustion underground coal gasification models

    SciTech Connect (OSTI)

    Fausett, L.K.; Fausett, D.W.

    1984-01-01T23:59:59.000Z

    A survey has been made of forward combustion gasification models that are available in the public domain. The six models obtained for study have been mathematically analyzed to determine their conceptual completeness and computational complexity. The models range in scope of generality from a simple constrained mass balance model to a two-dimensional unsteady-state model. The computer code for each model has been implemented on the University of Wyoming CDC CYBER 730/760 computer system. Computed analyses with each of the programs are compared using data (taken primarily from the Lawrence Livermore National Laboratory (LLNL) Underground Coal Gasification (UCG) Data Base) corresponding to six representative DOE sponsored field experiments at Hanna, Hoe Creek, Rawlins, and Pricetown. Four of the field tests were air injection experiments and two were oxygen/steam injection experiments. This study provides a direct comparison of input data requirements and computer resource requirements of the six computer codes. It furnishes an indication of the applicability of each model to the various operating conditions in the different field tests. Computational capabilities and limitations of each model are discussed in detail. 20 references, 47 figures, 13 tables.

  3. Biological treatment of underground coal gasification wastewaters

    SciTech Connect (OSTI)

    Bryant, C.W. Jr.; Humenick, M.J.; Cawein, C.C.; Nolan, B.T. III

    1985-05-01T23:59:59.000Z

    Biotreatability studies using underground coal gasification (UCG) wastewaters were performed by the University of Arizona and the University of Wyoming. The University of Arizona researchers found that UCG condensate could be effectively treated by activated sludge, using feed wastewaters of up to 50% strength. Total organic carbon (TOC) and chemical oxygen demand (COD) removals approached 90% during this research. The University of Wyoming researchers found that solvent extraction and hot-gas stripping were effective pretreatments for undiluted UCG condensate and that addition of powdered activated carbon enhanced the biotreatment process. TOC and COD removals resulting from the combination of pretreatments and biotreatment were 91% and 95%, respectively. The yield, decay, and substrate removal rate coefficients were greater in the University of Wyoming study than in the University of Arizona study. This was possibly caused by removing bioinhibitory substances, such as ammonia, with pretreatment. 18 refs., 25 figs., 6 tabs.

  4. The Large Underground Xenon (LUX) Experiment

    E-Print Network [OSTI]

    D. S. Akerib; X. Bai; S. Bedikian; E. Bernard; A. Bernstein; A. Bolozdynya; A. Bradley; D. Byram; S. B. Cahn; C. Camp; M. C. Carmona-Benitez; D. Carr; J. J. Chapman; A. Chiller; C. Chiller; K. Clark; T. Classen; T. Coffey; A. Curioni; E. Dahl; S. Dazeley; L. de Viveiros; A. Dobi; E. Dragowsky; E. Druszkiewicz; B. Edwards; C. H. Faham; S. Fiorucci; R. J. Gaitskell; K. R. Gibson; M. Gilchriese; C. Hall; M. Hanhardt; B. Holbrook; M. Ihm; R. G. Jacobsen; L. Kastens; K. Kazkaz; R. Knoche; S. Kyre; J. Kwong; R. Lander; N. A. Larsen; C. Lee; D. S. Leonard; K. T. Lesko; A. Lindote; M. I. Lopes; A. Lyashenko; D. C. Malling; R. Mannino; Z. Marquez; D. N. McKinsey; D. -M. Mei; J. Mock; M. Moongweluwan; M. Morii; H. Nelson; F. Neves; J. A. Nikkel; M. Pangilinan; P. D. Parker; E. K. Pease; K. Pech; P. Phelps; A. Rodionov; P. Roberts; A. Shei; T. Shutt; C. Silva; W. Skulski; V. N. Solovov; C. J. Sofka; P. Sorensen; J. Spaans; T. Stiegler; D. Stolp; R. Svoboda; M. Sweany; M. Szydagis; D. Taylor; J. Thomson; M. Tripathi; S. Uvarov; J. R. Verbus; N. Walsh; R. Webb; D. White; J. T. White; T. J. Whitis; M. Wlasenko; F. L. H. Wolfs; M. Woods; C. Zhang

    2012-11-21T23:59:59.000Z

    The Large Underground Xenon (LUX) collaboration has designed and constructed a dual-phase xenon detector, in order to conduct a search for Weakly Interacting Massive Particles(WIMPs), a leading dark matter candidate. The goal of the LUX detector is to clearly detect (or exclude) WIMPS with a spin independent cross section per nucleon of $2\\times 10^{-46}$ cm$^{2}$, equivalent to $\\sim$1 event/100 kg/month in the inner 100-kg fiducial volume (FV) of the 370-kg detector. The overall background goals are set to have $<$1 background events characterized as possible WIMPs in the FV in 300 days of running. This paper describes the design and construction of the LUX detector.

  5. The Large Underground Xenon (LUX) Experiment

    E-Print Network [OSTI]

    Akerib, D S; Bedikian, S; Bernard, E; Bernstein, A; Bolozdynya, A; Bradley, A; Byram, D; Cahn, S B; Camp, C; Carmona-Benitez, M C; Carr, D; Chapman, J J; Chiller, A; Chiller, C; Clark, K; Classen, T; Coffey, T; Curioni, A; Dahl, E; Dazeley, S; de Viveiros, L; Dobi, A; Dragowsky, E; Druszkiewicz, E; Edwards, B; Faham, C H; Fiorucci, S; Gaitskell, R J; Gibson, K R; Gilchriese, M; Hall, C; Hanhardt, M; Holbrook, B; Ihm, M; Jacobsen, R G; Kastens, L; Kazkaz, K; Knoche, R; Kyre, S; Kwong, J; Lander, R; Larsen, N A; Lee, C; Leonard, D S; Lesko, K T; Lindote, A; Lopes, M I; Lyashenko, A; Malling, D C; Mannino, R; Marquez, Z; McKinsey, D N; Mei, D -M; Mock, J; Moongweluwan, M; Morii, M; Nelson, H; Neves, F; Nikkel, J A; Pangilinan, M; Parker, P D; Pease, E K; Pech, K; Phelps, P; Rodionov, A; Roberts, P; Shei, A; Shutt, T; Silva, C; Skulski, W; Solovov, V N; Sofka, C J; Sorensen, P; Spaans, J; Stiegler, T; Stolp, D; Svoboda, R; Sweany, M; Szydagis, M; Taylor, D; Thomson, J; Tripathi, M; Uvarov, S; Verbus, J R; Walsh, N; Webb, R; White, D; White, J T; Whitis, T J; Wlasenko, M; Wolfs, F L H; Woods, M; Zhang, C

    2012-01-01T23:59:59.000Z

    The Large Underground Xenon (LUX) collaboration has designed and constructed a dual-phase xenon detector, in order to conduct a search for Weakly Interacting Massive Particles(WIMPs), a leading dark matter candidate. The goal of the LUX detector is to clearly detect (or exclude) WIMPS with a spin independent cross section per nucleon of $2\\times 10^{-46}$ cm$^{2}$, equivalent to $\\sim$1 event/100 kg/month in the inner 100-kg fiducial volume (FV) of the 370-kg detector. The overall background goals are set to have $<$1 background events characterized as possible WIMPs in the FV in 300 days of running. This paper describes the design and construction of the LUX detector.

  6. Wiener filtering with a seismic underground array at the Sanford Underground Research Facility

    E-Print Network [OSTI]

    Michael Coughlin; Jan Harms; Nelson Christensen; Vladimir Dergachev; Riccardo DeSalvo; Shivaraj Kandhasamy; Vuk Mandic

    2014-08-19T23:59:59.000Z

    A seismic array has been deployed at the Sanford Underground Research Facility in the former Homestake mine, South Dakota, to study the underground seismic environment. This includes exploring the advantages of constructing a third-generation gravitational-wave detector underground. A major noise source for these detectors would be Newtonian noise, which is induced by fluctuations in the local gravitational field. The hope is that a combination of a low-noise seismic environment and coherent noise subtraction using seismometers in the vicinity of the detector could suppress the Newtonian noise to below the projected noise floor for future gravitational-wave detectors. In this paper, we use Wiener filtering techniques to subtract coherent noise in a seismic array in the frequency band 0.05 -- 1\\,Hz. This achieves more than an order of magnitude noise cancellation over a majority of this band. We show how this subtraction would benefit proposed future low-frequency gravitational wave detectors. The variation in the Wiener filter coefficients over the course of the day, including how local activities impact the filter, is analyzed. We also study the variation in coefficients over the course of a month, showing the stability of the filter with time. How varying the filter order affects the subtraction performance is also explored. It is shown that optimizing filter order can significantly improve subtraction of seismic noise, which gives hope for future gravitational-wave detectors to address Newtonian noise.

  7. Nuclear testing continues

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    week we noted that many of the Special Engineer Detachment stayed at the sites when the war was over and continued working, however, most of them who had been drafted out of...

  8. Nuclear test experimental science

    SciTech Connect (OSTI)

    Struble, G.L.; Middleton, C.; Bucciarelli, G.; Carter, J.; Cherniak, J.; Donohue, M.L.; Kirvel, R.D.; MacGregor, P.; Reid, S. (eds.)

    1989-01-01T23:59:59.000Z

    This report discusses research being conducted at Lawrence Livermore Laboratory under the following topics: prompt diagnostics; experimental modeling, design, and analysis; detector development; streak-camera data systems; weapons supporting research.

  9. Muon simulation codes MUSIC and MUSUN for underground physics

    E-Print Network [OSTI]

    V. A. Kudryavtsev

    2008-10-25T23:59:59.000Z

    The paper describes two Monte Carlo codes dedicated to muon simulations: MUSIC (MUon SImulation Code) and MUSUN (MUon Simulations UNderground). MUSIC is a package for muon transport through matter. It is particularly useful for propagating muons through large thickness of rock or water, for instance from the surface down to underground/underwater laboratory. MUSUN is designed to use the results of muon transport through rock/water to generate muons in or around underground laboratory taking into account their energy spectrum and angular distribution.

  10. Geochemical and Isotopic Evaluation of Groundwater Movement in Corrective Action Unit 97: Yucca Flat/Climax Mine, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    Farnham, Irene

    2006-02-01T23:59:59.000Z

    This report describes the results of a comprehensive geochemical evaluation of the groundwater flow system in the Yucca Flat/Climax Mine Corrective Action Unit (CAU). The main objectives of this study are to identify probable pathways for groundwater flow within the study area and to develop constraints on groundwater transit times between selected data collection sites. This work provides an independent means of testing and verifying predictive flow models being developed for this CAU using finite element methods. The Yucca Flat/Climax Mine CAU constitutes the largest of six underground test areas on the Nevada Test Site (NTS) specified for remedial action in the ''Federal Facility Agreement and Consent Order''. A total of 747 underground nuclear detonations were conducted in this CAU. Approximately 23 percent of these detonations were conducted below or near the water table, resulting in groundwater contamination in the vicinity and possibly downgradient of these underground test locations. Therefore, a rigorous evaluation of the groundwater flow system in this CAU is necessary to assess potential long-term risks to the public water supply at downgradient locations.

  11. Spent Fuel Test-Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Final report

    SciTech Connect (OSTI)

    Patrick, W.C. (comp.)

    1986-03-30T23:59:59.000Z

    In the Climax stock granite on the Nevada Test Site, eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized. When test data indicated that the test objectives were met during the 3-year storage phase, the spent-fuel canisters were retrieved and the thermal sources were de-energized. The project demonstrated the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner. In addition to emplacement and retrieval operations, three exchanges of spent-fuel assemblies between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. The test led to development of a technical measurements program. To meet these objectives, nearly 1000 instruments and a computer-based data acquisition system were deployed. Geotechnical, seismological, and test status data were recorded on a continuing basis for the three-year storage phase and six-month monitored cool-down of the test. This report summarizes the engineering and scientific endeavors which led to successful design and execution of the test. The design, fabrication, and construction of all facilities and handling systems are discussed, in the context of test objectives and a safety assessment. The discussion progresses from site characterization and experiment design through data acquisition and analysis of test data in the context of design calculations. 117 refs., 52 figs., 81 tabs.

  12. High resolution seismic survey of the Hanna, Wyoming underground coal gasification area

    SciTech Connect (OSTI)

    Not Available

    1983-08-01T23:59:59.000Z

    In June 1983 a high resolution seismic survey was conducted at the Department of Energy, Laramie Energy Technology Center's underground coal gasification test site near Hanna, Wyoming. The objectives of the survey were to locate and characterize underground burn zones and to identify shallow geologic faults at the test site. Seismic data acquisition and processing parameters were based upon prior work in the area, and were specifically designed to emphasize reflections at the shallow, 61 to 91 meter (200 to 300 ft) depths of interest. Data were obtained on two north-south lines along the test site boundary in addition to a three-dimensional grid over the Hanna IV experiment area. Processing included time varying filters, deconvolution, trace composition, and three-dimensional areal stacking of the data in order to identify burn zone anomalies. Anomalies were discernable resulting from the rubble-collapse void above the burn zones in the vicinity of the injection wells at the Hanna IV experiment area. The fault studies disclosed faults at the Hanna IV experiment area which may be responsible for the unexpected problems experienced in the early in-site gasification tests. For the test site the fault system was found to be a generally arcuate east-west trending graben complex with numerous antithetic faults. 15 references, 33 figures, 6 tables.

  13. Closure Report for Corrective Action Unit 130: Storage Tanks Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2009-03-01T23:59:59.000Z

    This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 130: Storage Tanks, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 130 are located within Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site. Corrective Action Unit 130 is comprised of the following CASs: • 01-02-01, Underground Storage Tank • 07-02-01, Underground Storage Tanks • 10-02-01, Underground Storage Tank • 20-02-03, Underground Storage Tank • 20-99-05, Tar Residue • 22-02-02, Buried UST Piping • 23-02-07, Underground Storage Tank This CR provides documentation supporting the completed corrective action investigations and provides data confirming that the closure objectives for CASs within CAU 130 were met. To achieve this, the following actions were performed: • Reviewed the current site conditions, including the concentration and extent of contamination. • Implemented any corrective actions necessary to protect human health and the environment. • Properly disposed of corrective action and investigation-derived wastes. From August 4 through September 30, 2008, closure activities were performed as set forth in the Streamlined Approach for Environmental Restoration Plan for CAU 130, Storage Tanks, Nevada Test Site, Nevada. The purposes of the activities as defined during the data quality objectives process were: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent, implement appropriate corrective actions, confirm that no residual contamination is present, and properly dispose of wastes. Constituents detected during the closure activities were evaluated against final action levels to identify COCs for CAU 130. Assessment of the data generated from closure activities indicates that no further action is necessary because no COCs were identified at any CAU 130 CAS. Debris removal from these CASs was considered a best management practice because no contamination was detected. The DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • No further corrective action is required at all CAU 130 CASs. • A Notice of Completion to DOE, National Nuclear Security Administration Nevada Site Office, is requested from the Nevada Division of Environmental Protection for closure of CAU 130. • Corrective Action Unit 130 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order.

  14. Industrial hygiene aspects of underground oil shale mining

    SciTech Connect (OSTI)

    Hargis, K.M.; Jackson, J.O.

    1982-01-01T23:59:59.000Z

    Health hazards associated with underground oil shale mining are summarized in this report. Commercial oil shale mining will be conducted on a very large scale. Conventional mining techniques of drilling, blasting, mucking, loading, scaling, and roof bolting will be employed. Room-and-pillar mining will be utilized in most mines, but mining in support of MIS retorting may also be conducted. Potential health hazards to miners may include exposure to oil shale dusts, diesel exhaust, blasting products, gases released from the oil shale or mine water, noise and vibration, and poor environmental conditions. Mining in support of MIS retorting may in addition include potential exposure to oil shale retort offgases and retort liquid products. Based upon the very limited industrial hygiene surveys and sampling in experimental oil shale mines, it does not appear that oil shale mining will result in special or unique health hazards. Further animal toxicity testing data could result in reassessment if findings are unusual. Sufficient information is available to indicate that controls for dust will be required in most mining activities, ventilation will be necessary to carry away gases and vapors from blasting and diesel equipment, and a combination of engineering controls and personal protection will likely be required for control of noise. Recommendations for future research are included.

  15. ANALYSIS OF METHANE PRODUCING COMMUNITIES WITHIN UNDERGROUND COAL BEDS

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    ANALYSIS OF METHANE PRODUCING COMMUNITIES WITHIN UNDERGROUND COAL BEDS by Elliott Paul Barnhart.........................................................................................8 Coal and Metabolite Enrichment Studies ..................................................................................14 Ability of the Consortium to Produce Methane from Coal and Metabolites ................16

  16. Underground barrier construction apparatus with soil-retaining shield

    DOE Patents [OSTI]

    Gardner, Bradley M. (Idaho Falls, ID); Smith, Ann Marie (Pocatello, ID); Hanson, Richard W. (Spokane, WA); Hodges, Richard T. (Deer Park, WA)

    1998-01-01T23:59:59.000Z

    An apparatus for building a horizontal underground barrier by cutting through soil and depositing a slurry, preferably one which cures into a hardened material. The apparatus includes a digging means for cutting and removing soil to create a void under the surface of the ground, a shield means for maintaining the void, and injection means for inserting barrier-forming material into the void. In one embodiment, the digging means is a continuous cutting chain. Mounted on the continuous cutting chain are cutter teeth for cutting through soil and discharge paddles for removing the loosened soil. This invention includes a barrier placement machine, a method for building an underground horizontal containment barrier using the barrier placement machine, and the underground containment system. Preferably the underground containment barrier goes underneath and around the site to be contained in a bathtub-type containment.

  17. Underground barrier construction apparatus with soil-retaining shield

    DOE Patents [OSTI]

    Gardner, B.M.; Smith, A.M.; Hanson, R.W.; Hodges, R.T.

    1998-08-04T23:59:59.000Z

    An apparatus is described for building a horizontal underground barrier by cutting through soil and depositing a slurry, preferably one which cures into a hardened material. The apparatus includes a digging means for cutting and removing soil to create a void under the surface of the ground, a shield means for maintaining the void, and injection means for inserting barrier-forming material into the void. In one embodiment, the digging means is a continuous cutting chain. Mounted on the continuous cutting chain are cutter teeth for cutting through soil and discharge paddles for removing the loosened soil. This invention includes a barrier placement machine, a method for building an underground horizontal containment barrier using the barrier placement machine, and the underground containment system. Preferably the underground containment barrier goes underneath and around the site to be contained in a bathtub-type containment. 17 figs.

  18. advanced underground vehicle: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and radiogenic 40Ar production in situ and from external sources, we can derive the ratio of 39Ar to 40Ar in underground sources. We show for the first time that...

  19. aging underground reinforced: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and geo-neutrinos, and perform exotic searches, with a 20 kiloton liquid scintillator detector of unprecedented 3% energy resolution (at 1 MeV) at 700-meter deep underground...

  20. ,"New Mexico Natural Gas Underground Storage Net Withdrawals...

    U.S. Energy Information Administration (EIA) Indexed Site

    ,,"(202) 586-8800",,,"3292015 10:08:54 PM" "Back to Contents","Data 1: New Mexico Natural Gas Underground Storage Net Withdrawals (MMcf)" "Sourcekey","N5070NM2"...