Powered by Deep Web Technologies
Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Nuclear waste storage bill passes Congress  

Science Journals Connector (OSTI)

Nuclear waste storage bill passes Congress ... The law sets up provisions to evaluate ways to store spent nuclear fuel and wastes. ...

1983-01-03T23:59:59.000Z

2

Long-term nuclear waste storage urged  

Science Journals Connector (OSTI)

Long-term nuclear waste storage urged ... Nuclear waste should be stored for at least 100 years before being disposed of permanently, says a multinational committee from the International Council of Scientific Unions (ICSU). ... The recommendations of the ICSU Committee on Terrestrial Disposal of Nuclear Wastes, headed by geochemistry professor William S. Fyfe of the University of Western Ontario, were published in ... ...

1984-08-27T23:59:59.000Z

3

States want say in nuclear waste storage  

Science Journals Connector (OSTI)

The states have put Congress and the executive branch on notice that they want a very active role in deciding where and how the nation's nuclear wastes will be stored. ... The 19-member State Planning Council on Radioactive Waste Management, appointed by President Carter in February 1980, in its interim report says that it is seeking a middle ground between giving states or Indian tribes a veto over the siting of long-term nuclear waste storage facilities and pre-emptive imposition of federal will. ...

1981-04-06T23:59:59.000Z

4

Nevada nuclear waste storage investigations: briefing book  

SciTech Connect (OSTI)

The Nevada Nuclear Waste Storage Investigations (NNWSI) are discussed briefly. The tuff in Yucca mountains being investigated as a possible repository host for radioactive wastes. The Spent Fuel Test-Climax began in the spring of 1980 in the northeastern Nevada Test Site about 1400 ft below the desert surface. The test has provided significant scientific and technical contributions in the following areas: heat impact on a large underground facility in a hard, brittle rock, impact of ventilation designs on repository heat removal, suitability and operational characteristics of instrumentation in a repository, impact of the mining procedures on underground openings and the surrounding rock, and heat and radiation effects on the physical, mechanical, and chemical properties of granite.

NONE

1983-03-01T23:59:59.000Z

5

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network [OSTI]

The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the ...

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

6

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents [OSTI]

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

7

Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste  

Science Journals Connector (OSTI)

......an interim storage facility for nuclear waste Burkhard Heuel-Fabianek Ralf...Research Centre Julich, Germany, nuclear waste is stored in drums and other vessels...Research Centre Julich (FZJ) nuclear waste is generated, which has to be......

Burkhard Heuel-Fabianek; Ralf Hille

2005-12-20T23:59:59.000Z

8

An Adaptive, Consent-Based Path to Nuclear Waste Storage and...  

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

An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions February 12, 2014 -...

9

Seismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain, Nevada  

E-Print Network [OSTI]

was heated to replicate the effects of long-term storage of decaying nuclear waste and to study the effects for the long- term storage of high-level nuclear waste from reactors and decom- missioned atomic weaponsSeismic modeling and analysis of a prototype heated nuclear waste storage tunnel, Yucca Mountain

Snieder, Roel

10

Nuclear Waste Storage in Gel-Derived Materials  

Science Journals Connector (OSTI)

For long life nuclear wastes (essentially actinides) research is in progress ... a process to prepare silica glass embedding the nuclear waste. Porous silica (gel) is used as a host matrix for nuclear waste. Neod...

T. Woignier; J. Reynes; J. Phalippou…

2000-12-01T23:59:59.000Z

11

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities  

E-Print Network [OSTI]

SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities Ron Fulbright Inspector (SWAMI) is a prototype mobile robot designed to perform autonomous inspection of nuclear waste user interface building tool called UIM/X. Introduction Safe disposal of nuclear waste is a difficult

Stephens, Larry M.

12

Comparison of carbon dioxide and nuclear waste storage costs in Lithuania  

Science Journals Connector (OSTI)

Nuclear power and carbon capture and storage (CCS) are key greenhouse gas mitigation options under consideration across the world. Both technologies imply long-term waste management challenge. Geological storage of carbon dioxide (CO2) and nuclear waste has much in common, and valuable lessons can be learnt from a comparison. Seeking to compare these technologies economic, social and environmental criteria need to be selected and expressed in terms of indicators. Very important issue is costs and economics of geological storage of carbon dioxide and nuclear waste. The costs of storage are one of the main indicators for assessment of technologies in terms of economic criteria. The paper defines the costs of the geological storage of CO2 and nuclear waste in Lithuania, drawing also on insights from other parts of the world. The costs of carbon dioxide and nuclear waste storage are evaluated in UScnt/kWh and compared. The paper critically compares the characteristics and location of the both sources of and storage options for CO2 and nuclear waste in Lithuania. It discusses the main costs categories for carbon dioxide and nuclear waste storage. The full range of potential geological storage options is considered and the most reliable options for carbon dioxide and nuclear waste are selected for the comparative costs assessment.

Dalia Streimikiene

2012-01-01T23:59:59.000Z

13

SORPTION OF URANIUM, PLUTONIUM AND NEPTUNIUM ONTO SOLIDS PRESENT IN HIGH CAUSTIC NUCLEAR WASTE STORAGE TANKS  

SciTech Connect (OSTI)

Solids such as granular activated carbon, hematite and sodium phosphates, if present as sludge components in nuclear waste storage tanks, have been found to be capable of precipitating/sorbing actinides like plutonium, neptunium and uranium from nuclear waste storage tank supernatant liqueur. Thus, the potential may exists for the accumulation of fissile materials in such nuclear waste storage tanks during lengthy nuclear waste storage and processing. To evaluate the nuclear criticality safety in a typical nuclear waste storage tank, a study was initiated to measure the affinity of granular activated carbon, hematite and anhydrous sodium phosphate to sorb plutonium, neptunium and uranium from alkaline salt solutions. Tests with simulated and actual nuclear waste solutions established the affinity of the solids for plutonium, neptunium and uranium upon contact of the solutions with each of the solids. The removal of plutonium and neptunium from the synthetic salt solution by nuclear waste storage tank solids may be due largely to the presence of the granular activated carbon and transition metal oxides in these storage tank solids or sludge. Granular activated carbon and hematite also showed measurable affinity for both plutonium and neptunium. Sodium phosphate, used here as a reference sorbent for uranium, as expected, exhibited high affinity for uranium and neptunium, but did not show any measurable affinity for plutonium.

Oji, L; Bill Wilmarth, B; David Hobbs, D

2008-05-30T23:59:59.000Z

14

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

M. D. Staiger

2007-06-01T23:59:59.000Z

15

Radiation Damage of Glasses for Nuclear Waste Storage: Optical and Microstructural Aspects  

Science Journals Connector (OSTI)

A possible way to achieve a stable nuclear waste form consists of incorporating the different radionuclides ... actinides, radiation damage is produced in the storage matrix, which may potentially affect its long-term

M. Antonini; P. Camagni; A. Manara; M. Sacchi

1985-01-01T23:59:59.000Z

16

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.

M. D. Staiger

1999-06-01T23:59:59.000Z

17

Radioactive waste storage issues  

SciTech Connect (OSTI)

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

18

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect (OSTI)

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I. [Los Alamos Technical Associates, Inc., NM (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

19

Assessing the Feasibility of Interrogating Nuclear Waste Storage Silos using Cosmic-ray Muons  

E-Print Network [OSTI]

Muon radiography is a fast growing field in applied scientific research. In recent years, many detector technologies and imaging techniques using the Coulomb scattering and absorption properties of cosmic-ray muons have been developed for the non-destructive assay of various structures across a wide range of applications. This work presents the first results that assess the feasibility of using muons to interrogate waste silos within the UK Nuclear Industry. Two such approaches, using different techniques that exploit each of these properties, have previously been published, and show promising results from both simulation and experimental data for the detection of shielded high-Z materials and density variations from volcanic assay. Both detector systems are based on scintillator and photomultiplier technologies. Results from dedicated simulation studies using both these technologies and image reconstruction techniques are presented for an intermediate-sized nuclear waste storage facility filled with concrete...

Ambrosino, F; Cimmino, L; D'Alessandro, R; Ireland, D G; Kaiser, R; Mahon, D F; Mori, N; Noli, P; Saracino, G; Shearer, C; Viliani, L; Yang, G

2014-01-01T23:59:59.000Z

20

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect (OSTI)

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect (OSTI)

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

22

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a “nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

23

REGIONAL BINNING FOR CONTINUED STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTES  

SciTech Connect (OSTI)

In the Continued Storage Analysis Report (CSAR) (Reference 1), DOE decided to analyze the environmental consequences of continuing to store the commercial spent nuclear fuel (SNF) at 72 commercial nuclear power sites and DOE-owned spent nuclear fuel and high-level waste at five Department of Energy sites by region rather than by individual site. This analysis assumes that three commercial facilities pairs--Salem and Hope Creek, Fitzpatrick and Nine-Mile Point, and Dresden and Moms--share common storage due to their proximity to each other. The five regions selected for this analysis are shown on Figure 1. Regions 1, 2, and 3 are the same as those used by the Nuclear Regulatory Commission in their regulatory oversight of commercial power reactors. NRC Region 4 was subdivided into two regions to more appropriately define the two different climates that exist in NRC Region 4. A single hypothetical site in each region was assumed to store all the SNF and HLW in that region. Such a site does not exist and has no geographic location but is a mathematical construct for analytical purposes. To ensure that the calculated results for the regional analyses reflect appropriate inventory, facility and material degradation, and radionuclide transport, the waste inventories, engineered barriers, and environmental conditions for the hypothetical sites were developed from data for each of the existing sites within the given region. Weighting criteria to account for the amount and types of SNF and HLW at each site were used in the development of the environmental data for the regional site, such that the results of the analyses for the hypothetical site were representative of the sum of the results of each actual site if they had been modeled independently. This report defines the actual site data used in development of this hypothetical site, shows how the individual site data was weighted to develop the regional site, and provides the weighted data used in the CSAR analysis. It is divided into Part 1 that defines time-dependent releases from each regional site, Part 2 that defines transport conditions through the groundwater, and Part 3 that defines transport through surface water and populations using the surface waters for drinking.

W. Lee Poe, Jr

1998-10-01T23:59:59.000Z

24

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

25

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

SciTech Connect (OSTI)

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.

Wilson, C.N.

1990-09-01T23:59:59.000Z

26

Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility  

SciTech Connect (OSTI)

As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to overpressure--external to T Plant, was included for completeness but is not within the scope of the hazards evaluation. Container failures external to T Plant will be addressed as part of the transportation analysis. This document describes the HazOp analysis performed for the activities associated with the storage of SNF sludge in the T Plant.

SCHULTZ, M.V.

2000-08-22T23:59:59.000Z

27

Nuclear materials management storage study  

SciTech Connect (OSTI)

The Office of Weapons and Materials Planning (DP-27) requested the Planning Support Group (PSG) at the Savannah River Site to help coordinate a Departmental complex-wide nuclear materials storage study. This study will support the development of management strategies and plans until Defense Programs` Complex 21 is operational by DOE organizations that have direct interest/concerns about or responsibilities for nuclear material storage. They include the Materials Planning Division (DP-273) of DP-27, the Office of the Deputy Assistant Secretary for Facilities (DP-60), the Office of Weapons Complex Reconfiguration (DP-40), and other program areas, including Environmental Restoration and Waste Management (EM). To facilitate data collection, a questionnaire was developed and issued to nuclear materials custodian sites soliciting information on nuclear materials characteristics, storage plans, issues, etc. Sites were asked to functionally group materials identified in DOE Order 5660.1A (Management of Nuclear Materials) based on common physical and chemical characteristics and common material management strategies and to relate these groupings to Nuclear Materials Management Safeguards and Security (NMMSS) records. A database was constructed using 843 storage records from 70 responding sites. The database and an initial report summarizing storage issues were issued to participating Field Offices and DP-27 for comment. This report presents the background for the Storage Study and an initial, unclassified summary of storage issues and concerns identified by the sites.

Becker, G.W. Jr.

1994-02-01T23:59:59.000Z

28

Repository sealing plan for the Nevada Nuclear Waste Storage Investigations Project, fiscal years 1984 through 1990  

SciTech Connect (OSTI)

This report presents a plan to develop acceptable sealing methods for a prospective nuclear waste repository in unsaturated tuff in Yucca Mountain, which is on and adjacent to the Nevada Test Site. Sealing is the permanent closure of the underground facility, shafts, ramps, and boreholes. Questiona associated with the performance of the sealing system form the basis for this plan. Tasks that contribute to the resolution of these questions and support the documentation required for the construction authorization application are proposed. The approach to answering the performance-related questions is divided into six steps: (1) assess the need for sealing, (2) define the design requirements, (3) measure the material properties, (4) assess the performance of sealing designs, (5) perform laboratory analyses and field testing, and (6) reassess the performance of sealing designs. Organization of the tasks supporting each step is illustrated by detailed work-flow diagrams.

Fernandez, J.A.

1985-02-01T23:59:59.000Z

29

Statement of position of the United States Department of Energy in the matter of proposed rulemaking on the storage and disposal of nuclear waste (waste confidence rulemaking)  

SciTech Connect (OSTI)

Purpose of this proceeding is to assess generically the degree of assurance that the radioactive waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to determine whether wastes can be safely stored on-site past license expiration until off-site disposal/storage is available. (DLC)

None

1980-04-15T23:59:59.000Z

30

Nuclear Waste Repository Plan Approved by Senate  

Science Journals Connector (OSTI)

Bill calls for selection of permanent repository site by 1989, building of a retrievable waste facility, cash payments states with storage sites ... After considerable debate, the Senate has approved a plan aimed at getting the federal government's effort to find a long-term storage site for spent nuclear fuel and highlevel nuclear wastes off dead center and out of the political crossfire. ...

JANICE LONG

1987-12-07T23:59:59.000Z

31

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

32

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

33

Nuclear waste bill dead for this year  

Science Journals Connector (OSTI)

Nuclear waste bill dead for this year ... "Politics pure and simple" killed compromise legislation to create an interim storage facility in Nevada for commercial high-level nuclear waste, say bill proponents in Congress and in the nuclear power industry. ... Last year, bills passed both the House and Senate that would have required the government to, among other things, temporarily store nuclear waste until a permanent facility could be built. ...

JEFF JOHNSON

1998-06-08T23:59:59.000Z

34

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...4). Although disposal of HLW remains...for long-term disposal is through deep...successful waste-disposal program has eluded...geologic repository at Yucca Mountain, Nevada. Authorized...Administration withdrew funding for Yucca Mountain...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

35

Dedicated-site, interim storage of high-level nuclear waste as part of the management system  

Science Journals Connector (OSTI)

...develop permanent repositories. A systems approach...reprocessed nuclear wastes from fuel rods...In- teragency Review Group (1) and...high-level wastes, including both...mined geologic repositories for permanent...Under current plans for mined geologic...and performance standards of permanent...

E-an Zen

1980-01-01T23:59:59.000Z

36

Site characterization plan: Conceptual design report: Volume 6, Drawing portfolio: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect (OSTI)

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 6 contains drawings. 114 figs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

37

Hazard Evaluation for Storage of Spent Nuclear Fuel at the Solid Waste Treatment Facility  

SciTech Connect (OSTI)

This report is prepared as the initial step in the safety assurance process described in 10 CFR 830 Subpart B, Nuclear Safety Management, and HNF-PRO-700, Safety Basis Development.

ERPENBECK, E.G.

2002-11-12T23:59:59.000Z

38

The Ethics of Nuclear Waste in Canada: Risks, Harms and Unfairness.  

E-Print Network [OSTI]

??The Nuclear Waste Management Organization (NWMO)  – the crown corporation responsible for the long-term storage of nuclear fuel waste in Canada  – seeks to bury… (more)

Wilding, Ethan

2010-01-01T23:59:59.000Z

39

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

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

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

40

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Preparing Class B and C Waste for Long Term Storage  

SciTech Connect (OSTI)

Commercial Nuclear Generating Stations outside of the Atlantic Compact will lose access to the Barnwell Disposal Facility in July of 2008. Many generators have constructed Interim On-Site Storage Buildings (IOSB) in which to store class B and C waste in the future as other permanent disposal options are developed. Until such time it is important for these generators to ensure class B and C waste generation is minimized and waste generated is packaged to facilitate long term storage. (authors)

Snyder, M.W. [Sacramento Municipal Utility District - Rancho Seco (United States)

2008-07-01T23:59:59.000Z

42

Chapter 19 - Nuclear Waste Fund  

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

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

43

High level nuclear waste  

SciTech Connect (OSTI)

The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immobilization plant is to be the Defense Waste Processing Facility at Savannah River, scheduled for 1983 project submission to Congress and 1989 operation. Waste forms are still being selected for this plant. Borosilicate glass is currently the reference form, but alternate candidates include concretes, calcines, other glasses, ceramics, and matrix forms.

Crandall, J L

1980-01-01T23:59:59.000Z

44

Nuclear waste solutions  

DOE Patents [OSTI]

High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

45

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect (OSTI)

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

46

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

47

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

When did man discover nuclear waste? To answer this question, we first have to ask if nuclear waste really is something that could be called ... Prize in physics. In early writings within nuclear energy research ...

Göran Sundqvist

2002-01-01T23:59:59.000Z

48

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

49

Nuclear Fuels Storage & Transportation Planning Project Documents |  

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

Fuel Cycle Technologies » Nuclear Fuels Storage & Fuel Cycle Technologies » Nuclear Fuels Storage & Transportation Planning Project » Nuclear Fuels Storage & Transportation Planning Project Documents Nuclear Fuels Storage & Transportation Planning Project Documents September 30, 2013 Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. February 22, 2013 Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal This report provides findings from a set of social science studies

50

Pioneering Nuclear Waste Disposal  

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

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

51

Independent regulatory examination of radiation situation in the areas of spent nuclear fuel and radioactive wastes storage in the Russian far east  

Science Journals Connector (OSTI)

......submarines performing reception and storage of spent nuclear fuel (SNF...as well as for temporary storage and reloading of SNF after...seaweeds, bottom sediments, seawater, sea fish, mushrooms, local...for LRW treatment, the LRW storage facility, SRW storage facility......

N. K. Shandala; S. M. Kiselev; A. I. Lucyanec; A. V. Titov; V. A. Seregin; D. V. Isaev; S. V. Akhromeev

2011-07-01T23:59:59.000Z

52

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

Glasses Developed for Nuclear Waste Immobilization," 91[12],solubility in borosilicate nuclear waste glass Ashutoshfor the researchers in nuclear waste community around the

McCloy, John S.

2014-01-01T23:59:59.000Z

53

Nuclear Fuels Storage & Transportation Planning Project | Department of  

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

Nuclear Fuels Storage & Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut Yankee (http://www.connyankee.com/html/fuel_storage.html). Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel

54

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

The term nuclear waste...embraces all residues from the use of radioactive materials, including uses in medicine and industry. The most highly radioactive of these are the spent fuel or reprocessed wastes from co...

2005-01-01T23:59:59.000Z

55

Application of the NNWSI [Nevada Nuclear Waste Storage Investigations] unsaturated test method to actinide doped SRL [Savannah River Laboratory] 165 type glass  

SciTech Connect (OSTI)

The results of tests done using the Unsaturated Test Method are presented. These tests, done to determine the suitability of glass in a potential high-level waste repository as developed by the Nevada Nuclear Waste Storage Investigations Project, simulate conditions anticipated for the post-containment phase of the repository when only limited contact between the waste form and water is expected. The reaction of glass occurs via processes that are initiated due to glass/water vapor and glass/liquid water contact. Vapor interaction results in the initiation of an exchange process between water and the more mobile species (alkalis and boron) in the glass. The liquid reaction produces interactions similar to those seen in standard leaching tests, except due to the limited amount of water present and the presence of partially sensitized 304L stainless steel, the formation of reaction products greatly exceeds that found in MCC-1 type leach tests. The effect of sensitized stainless steel on the reaction is to enhance breakdown of the glass matrix thereby increasing the release of the transuranic elements from the glass. However, most of the Pu and Am released is entrained by either the metal components of the test or by the reaction phases, and is not released to solution. 16 refs., 20 figs., 17 tabs.

Bates, J.K.; Gerding, T.J.

1990-08-01T23:59:59.000Z

56

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

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

Analyses Analyses Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation activities within the UFDC are being developed to address issues regarding the extended storage of UNF and its subsequent

57

WORLDWIDE FOCUS ON NUCLEAR WASTE  

Science Journals Connector (OSTI)

WORLDWIDE FOCUS ON NUCLEAR WASTE ... Volume grows and years pile up, but world lacks consensus on disposing of nuclear waste ... WHAT TO DO WITH SPENT nuclear fuel and high-level radioactive waste is a problem shared by much of the world. ...

JEFF JOHNSON

2001-06-18T23:59:59.000Z

58

Use of the Modified Light Duty Utility Arm to Perform Nuclear Waste Cleanup of Underground Waste Storage Tanks at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

The Modified Light Duty Utility Arm (MLDUA) is a selectable seven or eight degree-of-freedom robot arm with a 16.5 ft (5.03 m) reach and a payload capacity of 200 lb. (90.72 kg). The utility arm is controlled in either joystick-based telerobotic mode or auto sequence robotics mode. The MLDUA deployment system deploys the utility arm vertically into underground radioactive waste storage tanks located at Oak Ridge National Laboratory. These tanks are constructed of gunite material and consist of two 25 ft (7.62 m) diameter tanks in the North Tank Farm and six 50 ft (15.24 m) diameter tanks in the South Tank Farm. After deployment inside a tank, the utility arm reaches and grasps the confined sluicing end effecter (CSEE) which is attached to the hose management arm (HMA). The utility arm positions the CSEE within the tank to allow the HMA to sluice the tank's liquid and solid waste from the tank. The MLDUA is used to deploy the characterization end effecter (CEE) and gunite scarifying end effecter (GSEE) into the tank. The CEE is used to survey the tank wall's radiation levels and the physical condition of the walls. The GSEE is used to scarify the tank walls with high-pressure water to remove the wall scale buildup and a thin layer of gunite which reduces the radioactive contamination that is embedded into the gunite walls. The MLDUA is also used to support waste sampling and wall core-sampling operations. Other tools that have been developed for use by the MLDUA include a pipe-plugging end effecter, pipe-cutting end effecter, and pipe-cleaning end effecter. Washington University developed advance robotics path control algorithms for use in the tanks. The MLDUA was first deployed in June 1997 and has operated continuously since then. Operational experience in the first four tanks remediated is presented in this paper.

Blank, J.A.; Burks, B.L.; DePew, R.E.; Falter, D.D.; Glassell, R.L.; Glover, W.H.; Killough, S.M.; Lloyd, P.D.; Love, L.J.; Randolph, J.D.; Van Hoesen, S.D.; Vesco, D.P.

1999-04-01T23:59:59.000Z

59

Site Visit Report, Hanford Waste Encapsulation Storage Facility...  

Energy Savers [EERE]

Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 Site Visit Report, Hanford Waste Encapsulation Storage Facility - January 2011 January 2011 Hanford...

60

Status Update: Extended Storage and Transportation Waste Confidence...  

Office of Environmental Management (EM)

Status Update: Extended Storage and Transportation Waste Confidence Status Update: Extended Storage and Transportation Waste Confidence Presentation made by David W. Pstrak for the...

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

A Perspective on Nuclear Waste  

Science Journals Connector (OSTI)

The management of spent nuclear fuel and high-level nuclear waste has the deserved reputation as one of ... facing the United States and other nations using nuclear reactors for electric power generation. This pa...

D. Warner North

1999-08-01T23:59:59.000Z

62

Waste Panel Expected to Back Interim Storage  

Science Journals Connector (OSTI)

...a nuclear waste repository at Yucca Mountain, Nevada, last year, President...Then it would be shipped to Yucca Mountain, transferred into steel cylinders...licensed. One reason was that Yucca Mountain had to cool waste before permanently...

Eli Kintisch

2011-07-08T23:59:59.000Z

63

WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint |  

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

Uses Recovery Act Funding to Reduce Nuclear Waste Footprint Uses Recovery Act Funding to Reduce Nuclear Waste Footprint WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint August 1, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE's) Carlsbad Field Office (CBFO) reduced the nuclear waste footprint by using American Recovery and Reinvestment Act funds to expedite the clean up of five transuranic (TRU) waste storage sites and to make important infrastructure improvements at the Waste Isolation Pilot Plant (WIPP). Expediting TRU waste shipments supports DOE's goal to dispose of 90 percent of legacy TRU waste by 2015, saving taxpayers million of dollars in storage and maintenance costs. Recovery Act funds allowed highly trained teams to safely prepare and load

64

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

65

Managing America's Defense Nuclear Waste | Department of Energy  

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

Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste Managing America's Defense Nuclear Waste More Documents & Publications National Defense...

66

Nuclear Waste Assessment System for Technical Evaluation (NUWASTE)  

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

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board U.S. Nuclear Waste Technical Review Board: Roles and Priorities Presented by: Nigel Mote, Executive Director, U.S. Nuclear Waste Technical Review Board May 14, 2013 Hyatt Regency Buffalo, Buffalo, NY. Presented to: National Transportation Stakeholders' Forum NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to implementing the NWPA, including: - transportation, packaging, and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW)

67

Solving the Nuclear Waste Problem  

Science Journals Connector (OSTI)

Solving the Nuclear Waste Problem ... Of the many problems that beset the nuclear power industry, none has proved as perplexing as taking out the trash. ... Nuclear waste will remain a potential threat to man and the environment for as long as 10,000 years. ...

1988-09-12T23:59:59.000Z

68

Leaching of Nuclear Waste Glasses  

Science Journals Connector (OSTI)

Resistance to aqueous corrosion is the most important requirement of glasses designed to immobilize high level radioactive wastes. Obtaining a highly durable nuclear waste glass is complicated by the requirement ...

L. L. Hench

1985-01-01T23:59:59.000Z

69

Funds denied for nuclear waste  

Science Journals Connector (OSTI)

... curb on the amount of nuclear waste that can be stored in the state's West Valley .facility, which has been closed since 1972. ...

David Dickson

1979-05-24T23:59:59.000Z

70

Activities Related to Storage of Spent Nuclear Fuel | Department...  

Office of Environmental Management (EM)

Activities Related to Storage of Spent Nuclear Fuel Activities Related to Storage of Spent Nuclear Fuel Activities Related to Storage of Spent Nuclear Fuel More Documents &...

71

Managing Nuclear Waste: Options Considered  

SciTech Connect (OSTI)

Starting in the 1950s, U.S. scientists began to research ways to manage highly radioactive materials accumulating at power plants and other sites nationwide. Long-term surface storage of these materials poses significant potential health, safety, and environmental risks. Scientists studied a broad range of options for managing spent nuclear fuel and high-level radioactive waste. The options included leaving it where it is, disposing of it in various ways, and making it safer through advanced technologies. International scientific consensus holds that these materials should eventually be disposed of deep underground in what is called a geologic repository. In a recent special report, the National Academy of Sciences summarized the various studies and emphasized that geologic disposal is ultimately necessary.

DOE

2002-05-02T23:59:59.000Z

72

Site characterization plan: Conceptual design report, Volume 2: Chapters 4-9: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect (OSTI)

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. 147 refs., 145 figs., 83 tabs.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

73

Site characterization plan: Conceptual design report, Volume 3: Appendices A-E: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect (OSTI)

This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. Volume 3 contains Appendices A through E.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

74

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

75

Nuclear Waste Policy Act | Department of Energy  

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

Nuclear Waste Policy Act Nuclear Waste Policy Act Document on the Nuclear Waste Policy Act of 1982 An Act to provide for the development of repositories for the disposal of...

76

A Roman Shipwreck and Safe Nuclear Storage | Department of Energy  

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

A Roman Shipwreck and Safe Nuclear Storage A Roman Shipwreck and Safe Nuclear Storage A Roman Shipwreck and Safe Nuclear Storage September 12, 2011 - 2:00pm Addthis Vitrification technology -- immobilizing material in glass -- is a practical and effective option for treating radioactive and hazardous chemical wastes. | Image courtesy of PNNL Vitrification technology -- immobilizing material in glass -- is a practical and effective option for treating radioactive and hazardous chemical wastes. | Image courtesy of PNNL Charles Rousseaux Charles Rousseaux Senior Writer, Office of Science How does it work? Vitrification technology immobilizes a material in glass and is a highly effective way of treating and disposing of many types of waste. Ancient Roman glass offers a new opportunity to study how glass will

77

Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect (OSTI)

The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 4 contains Appendices F to O.

MacDougall, H R; Scully, L W; Tillerson, J R [comps.] [comps.

1987-09-01T23:59:59.000Z

78

Site characterization plan: Conceptual design report: Volume 5, Appendices P-R: Nevada Nuclear Waste Storage Investigations Project  

SciTech Connect (OSTI)

The site for the prospective respository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases, design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. Volume 5 contains appendices P through R.

MacDougall, H.R.; Scully, L.W.; Tillerson, J.R. (comps.)

1987-09-01T23:59:59.000Z

79

Hydration Aging of Nuclear Waste Glass  

Science Journals Connector (OSTI)

...of Nuclear Waste Glass 10...STEINDLER Chemical Engineering...60439 The aging of simulated nuclear waste glass by...nuclear waste forms can meet...simulated aging reac-tions...whether a waste formn can...pro-jected Nuclear Regulatory...STEINDLEt Chemical Engineering...Basisfor Waste Form Integrity...

J. K. BATES; L. J. JARDINE; M. J. STEINDLER

1982-10-01T23:59:59.000Z

80

Disposing of nuclear waste in a salt bed  

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

Disposing of nuclear waste in a salt bed Disposing of nuclear waste in a salt bed 1663 Los Alamos science and technology magazine Latest Issue:November 2013 All Issues » submit Disposing of nuclear waste in a salt bed Decades' worth of transuranic waste from Los Alamos is being laid to rest at the Waste Isolation Pilot Plant in southeastern New Mexico March 25, 2013 Disposing of nuclear waste in a salt bed Depending on the impurities embedded within it, the salt from WIPP can be anything from a reddish, relatively opaque rock to a clear crystal like the one shown here. Ordinary salt effectively seals transuranic waste in a long-term repository Transuranic waste, made of items such as lab coats and equipment that have been contaminated by radioactive elements heavier than uranium, is being shipped from the Los Alamos National Laboratory to a long-term storage

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Plan for integrated testing for NNWSI [Nevada Nuclear Waste Storage Investigations] non EQ3/6 data base portion  

SciTech Connect (OSTI)

The purposes of the Integrated Testing Task are to develop laboratory data on thermodynamic properties for actinide and fission product elements for use in the EQ3/6 geochemical modelling code; to determine the transport properties of radionuclides in the near-field environment; and develop and validate a model to describe the rate of release of radionuclides from the near-field environment. Activities to achieve the firs item have been described in the Scientific Investigation Plan for EQ3/6, where quality assurance levels were assigned to the acitivities. This Scientific Investigation Plan describes activities to achieve the second and third purposes. The information gathered in these activities will be used to assess compliance with the performance objective for the Engineered Barrier System (EBS) to control the rate of release of radionuclides if the repository license application includes part of the host rock; to provide a source term for release of radionuclides from the waste package near-field environment to the system performance assessment task for use in showing compliance with the Environmental Protection Agency requirements; and to provide a source term for release of radionculides from the waste package near-field environment to the system performance assessment task for use in doing calculations of cumulative releases of radionuclides from the repository over 100,000 years as required by the site evaluation process. 5 refs.

Oversby, V.M.

1987-05-29T23:59:59.000Z

82

Rutherford backscattering for measuring corrosion layers on glasses for long-term storage of radioactive waste  

Science Journals Connector (OSTI)

The method considered safest for isolation of nuclear waste is vitrification (solidification in a glass or glassceramic matrix) with long-term storage in stable geological repositories. Borosilicate glasses are ....

Hj. Matzke

1984-01-01T23:59:59.000Z

83

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks  

SciTech Connect (OSTI)

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

ROGERS, C.A.

2000-02-17T23:59:59.000Z

84

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

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

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

85

Nuclear Fuel Storage and Transportation Planning Project Overview...  

Office of Environmental Management (EM)

Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project Overview Nuclear Fuel Storage and Transportation Planning Project...

86

Method for forming microspheres for encapsulation of nuclear waste  

DOE Patents [OSTI]

Microspheres for nuclear waste storage are formed by gelling droplets containing the waste in a gelation fluid, transferring the gelled droplets to a furnace without the washing step previously used, and heating the unwashed gelled droplets in the furnace under temperature or humidity conditions that result in a substantially linear rate of removal of volatile components therefrom.

Angelini, Peter (Oak Ridge, TN); Caputo, Anthony J. (Knoxville, TN); Hutchens, Richard E. (Knoxville, TN); Lackey, Walter J. (Oak Ridge, TN); Stinton, David P. (Knoxville, TN)

1984-01-01T23:59:59.000Z

87

2401-W Waste storage building closure plan  

SciTech Connect (OSTI)

This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

LUKE, S.M.

1999-07-15T23:59:59.000Z

88

Nuclear waste solids  

Science Journals Connector (OSTI)

Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since releas...

L. L. Hench; D. E. Clark; A. B. Harker

1986-05-01T23:59:59.000Z

89

Storage of nuclear materials by encapsulation in fullerenes  

DOE Patents [OSTI]

A method of encapsulating radioactive materials inside fullerenes for stable long-term storage. Fullerenes provide a safe and efficient means of disposing of nuclear waste which is extremely stable with respect to the environment. After encapsulation, a radioactive ion is essentially chemically isolated from its external environment.

Coppa, Nicholas V. (Los Alamos, NM)

1994-01-01T23:59:59.000Z

90

Gap Analysis to Support Extended Storage of Used Nuclear Fuel | Department  

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

Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation staff within the UFDC are responsible for addressing issues regarding the

91

Extended storage of low-level radioactive waste: an update  

SciTech Connect (OSTI)

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) has contracted with Brookhaven National Laboratory to address the technical issues of extended storage. The dual objectives of this study are (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. The circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1986-01-01T23:59:59.000Z

92

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology  

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

46: Radioactive Waste Storage at Rocky Flats Environmental 46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste storage facilities in order to increase storage capacity for low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 9, 1996 EA-1146: Finding of No Significant Impact Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

93

Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan  

SciTech Connect (OSTI)

This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

SIMMONS, F.M.

2000-12-01T23:59:59.000Z

94

Pipe overpack container for trasuranic waste storage and shipment  

DOE Patents [OSTI]

A Pipe Overpack Container for transuranic waste storage and shipment. The system consists of a vented pipe component which is positioned in a vented, insulated 55 gallon steel drum. Both the vented pipe component and the insulated drum are capable of being secured to prevent the contents from leaving the vessel. The vented pipe component is constructed of 1/4 inch stainless steel to provide radiation shielding. Thus, allowing shipment having high Americium-241 content. Several Pipe Overpack Containers are then positioned in a type B, Nuclear Regulatory Commission (NRC) approved, container. In the current embodiment, a TRUPACT-II container was employed and a maximum of fourteen Pipe Overpack Containers were placed in the TRUPACT-II. The combination received NRC approval for the shipment and storage of transuranic waste.

Geinitz, Richard R. (Arvada, CO); Thorp, Donald T. (Broomfield, CO); Rivera, Michael A. (Boulder, CO)

1999-01-01T23:59:59.000Z

95

Office of the US Nuclear Waste Negotiator  

SciTech Connect (OSTI)

The Office of the US Nuclear Waste Negotiator was created as an independent federal agency by the US Congress pursuant to the 1987 amendments to the Nuclear Waste Policy Act of 1982. The office, which was authorized by Congress for 5 years following the enactment of the 1987 amendments, is headquartered in Boise, Idaho, and maintains a liaison office in Washington DC. The negotiator is charged with the responsibility of attempting to find a state or Indian tribe willing to host a repository or monitored retrievable storage (MRS) facility at a technically qualified site on reasonable terms. The negotiator is instructed to negotiate with any state or Indian tribe that expresses an interest in hosting a repository or MRS facility. The negotiator will formally submit the negotiated agreement and environmental assessment to Congress, and the agreement will become effective when acted on by Congress and signed by the President into law.

Leroy, D.H.

1991-11-01T23:59:59.000Z

96

Systems and Components Development Expertise [Nuclear Waste Management  

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

Systems and Components Systems and Components Development Expertise Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Systems and Components Development Expertise Bookmark and Share Electrorefiner The electrorefiner: an apparatus used for electrometallurgical treatment of spent nuclear fuel to facilitate storage and ultimate disposal. Click on

97

Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography  

E-Print Network [OSTI]

This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the contents of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy.

Jonkmans, G; Jewett, C; Thompson, M

2012-01-01T23:59:59.000Z

98

Pioneering Nuclear Waste Disposal  

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

T h e W a s t e I s o l a t i o n P i l o t P l a n t DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

99

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

100

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Hydrogen storage systems from waste Mg alloys  

Science Journals Connector (OSTI)

Abstract The production cost of materials for hydrogen storage is one of the major issues to be addressed in order to consider them suitable for large scale applications. In the last decades several authors reported on the hydrogen sorption properties of Mg and Mg-based systems. In this work magnesium industrial wastes of AZ91 alloy and Mg-10 wt.% Gd alloy are used for the production of hydrogen storage materials. The hydrogen sorption properties of the alloys were investigated by means of volumetric technique, in situ synchrotron radiation powder X-ray diffraction (SR-PXD) and calorimetric methods. The measured reversible hydrogen storage capacity for the alloys AZ91 and Mg-10 wt.% Gd are 4.2 and 5.8 wt.%, respectively. For the Mg-10 wt.% Gd alloy, the hydrogenated product was also successfully used as starting reactant for the synthesis of Mg(NH2)2 and as MgH2 substitute in the Reactive Hydride Composite (RHC) 2LiBH4 + MgH2. The results of this work demonstrate the concrete possibility to use Mg alloy wastes for hydrogen storage purposes.

C. Pistidda; N. Bergemann; J. Wurr; A. Rzeszutek; K.T. Møller; B.R.S. Hansen; S. Garroni; C. Horstmann; C. Milanese; A. Girella; O. Metz; K. Taube; T.R. Jensen; D. Thomas; H.P. Liermann; T. Klassen; M. Dornheim

2014-01-01T23:59:59.000Z

102

Nuclear wastes: Small disposals  

Science Journals Connector (OSTI)

... Much to the relief of many east coast hospitals, universities and medical schools, the Nuclear Regulatory Commission (NRC) is proposing that liquid scintillation media used for detecting low levels ... for detecting low levels of radioactivity in biological samples need no longer be buried in nuclear ...

David Dickson

1980-10-16T23:59:59.000Z

103

Policy Issues in Nuclear Waste Disposal  

Science Journals Connector (OSTI)

The Congressional Research Service, in an issue brief on nuclear waste disposal, compactly described a common assessment when it noted that “nuclear waste has sometimes been called the Achilles’ heel of the nu...

2005-01-01T23:59:59.000Z

104

Nuclear waste, secrecy and the mass media  

Science Journals Connector (OSTI)

Invited media scholars and journalists examine the general issue of nuclear waste, risk and the sicentific promises that were ... . The mass media uncovered and reported on nuclear waste problems at Rocky Flats i...

Len Ackland; Karen Dorn Steele; JoAnn M. Valenti PhD

1998-01-01T23:59:59.000Z

105

GNEP Element:Minimize Nuclear Waste | Department of Energy  

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

Minimize Nuclear Waste GNEP Element:Minimize Nuclear Waste An article describing the ways in which the GNEP plans to minimize nuclear waste. GNEP Element:Minimize Nuclear Waste...

106

Disposal of Nuclear Wastes  

Science Journals Connector (OSTI)

...generated between now and A.D. 2000 is about 0.04 km3 (0.01...high-level wastes do not be-come a public hazard. The AEC adopts this...pre-sented at the 66th national meeting of the American Institute of...ARH-SA-41 (Atlantic Richfield Hanford Co., Richland, Washington...

Arthur S. Kubo; David J. Rose

1973-12-21T23:59:59.000Z

107

Nuclear Fuels Storage and Transportation Planning Project (NFST...  

Office of Environmental Management (EM)

Nuclear Fuels Storage and Transportation Planning Project (NFST) Program Status Nuclear Fuels Storage and Transportation Planning Project (NFST) Program Status Presentation made by...

108

SRS Completes Annual Examinations to Verify Safe Storage of Nuclear...  

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

Completes Annual Examinations to Verify Safe Storage of Nuclear Materials SRS Completes Annual Examinations to Verify Safe Storage of Nuclear Materials July 29, 2014 - 12:00pm...

109

Nuclear Waste and Agenda 21  

Science Journals Connector (OSTI)

Nuclear power and its attendant waste are similar to the Ring in J....The Lord of the Rings. The Ring gave mastery over every living creature, but it was created by an evil power. As a result, it inevitably corru...

Kristin Shrader-Frechette

1995-01-01T23:59:59.000Z

110

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington Dear Speaker Pelosi, Senator Byrd, and Secretary Bodman: The Nuclear Waste Technical Review Board, and transporting high-level radioactive waste and spent nuclear fuel. The Board is required to report its findings

111

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

con202vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, the Nuclear Waste Technical Review Board (Board) submits its second report of 2003 in accordance with provisions of the Nuclear Waste Policy Amendments Act of 1987, Public Law 100-203. The Act requires the Board

112

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

113

United States Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

United States Nuclear Waste Technical Review Board Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries A Report to Congress and the Secretary of Energy April 2011 #12;#12;U.S. Nuclear Waste Technical Review Board Experience Gained From

114

The role of NDE in nuclear waste clean-up  

SciTech Connect (OSTI)

With the end of the cold war, the need for large production capability of nuclear weapons has diminished; but concerns have arisen about the condition of the waste and the waste storage tanks from weapon production. The major concern is the potential for the waste to somehow contaminate the water, soil, and air around a plant. To completely solve the problem associated with the nuclear waste, the waste must be ultimately retrieved from the tanks, treated, separated into low-level and high-level waste streams, and then put into a final disposal form that will encapsulate the waste so that it will not penetrate the environment. Going through the process of safely retrieving, characterizing, treating, and disposing of the waste requires a large amount of nondestructive evaluation (NDE) sensor technology. The purpose of this paper is to provide a brief description of the types of NDE technologies needed to provide a safe and adequate solution to the nuclear-waste storage and disposal issue.

Light, G.M. [Southwest Research Inst., San Antonio, TX (United States)

1995-08-01T23:59:59.000Z

115

Nuclear Waste Policy Act Signed | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Waste Policy Act Signed | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

116

Nuclear waste management. Semiannual progress report, October 1983-March 1984  

SciTech Connect (OSTI)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.

McElroy, J.L.; Powell, J.A.

1984-06-01T23:59:59.000Z

117

AIChE issues nuclear waste conclusions  

Science Journals Connector (OSTI)

AIChE issues nuclear waste conclusions ... Long and extensive research, development, and demonstration activities in the U.S. and abroad have made possible the safe, permanent disposal of high-level commercial nuclear waste. ... Titled "The U.S. High-Level Nuclear Waste Management Program," it was prepared by an AIChE nuclear engineering division task force for the institute's government programs steering committee. ...

1986-02-10T23:59:59.000Z

118

Talk, No Action On Nuclear Waste Plan  

Science Journals Connector (OSTI)

Talk, No Action On Nuclear Waste Plan ... “Nowhere” was how an exasperated Lt. Gen. Brent Scowcroft, chairman of the Blue Ribbon Commission on America’s Nuclear Future, described the status of the U.S.’s search for a place to store spent commercial nuclear fuel and other radioactive waste. ... Although the blue-ribbon commission had completed its seminal report on nuclear waste in January, Scowcroft noted that action on its recommendations was “nowhere.” ...

JEFF JOHNSON

2012-09-30T23:59:59.000Z

119

Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes  

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

1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] 1995/01eis0212_cl.html[6/27/2011 1:02:59 PM] Final Environmental Impact Statement Safe Interim Storage Of Hanford Tank Wastes DOE/EIS-0212 VOLUME 1 OF 2 VOLUME 1 FINAL ENVIRONMENTAL IMPACT STATEMENT SAFE INTERIM STORAGE OF HANFORD TANK WASTES Hanford Site Richland, Washington October, 1995 WASHINGTON STATE DEPARTMENT OF ECOLOGY NUCLEAR WASTE PROGRAM LACEY, WASHINGTON 98503 U.S. DEPARTMENT OF ENERGY RICHLAND OPERATIONS OFFICE

120

Simulation of thermal stress influence on the Boom Clay kerogen (Oligocene, Belgium) in relation to long-term storage of high activity nuclear waste: I. Study of generated soluble compounds  

Science Journals Connector (OSTI)

Closed pyrolyses were performed on the Boom Clay kerogen to simulate the weak thermal stress applied during the in situ CERBERUS heating experiment (80 °C for 5 a). Two stronger thermal stresses, encompassing the range generally considered for the long-term disposal of high-activity nuclear waste (80 °C for 1 ka and 120 °C for 3 ka), were also simulated. Quantitative and qualitative studies were carried out on the products thus generated with a focus on the C12+ fraction, especially on its polar components. It thus appeared that the soluble C12+ fractions generated during these simulation experiments comprise a wide variety of polar O- and/or N-containing compounds, including carboxylic acids and phenols. The nature and/or the relative abundance of these polar compounds exhibit strong variations, with the extent of the thermal stress, reflecting the primary cracking of different types of structures with different thermal stability and the occurrence of secondary degradation reactions. These observations support the idea that the compounds, generated upon exposure of the Boom Clay kerogen to a low to moderate thermal stress, may affect the effectiveness of the geological barrier upon long-term storage of high-activity nuclear waste.

I. Deniau; S. Derenne; C. Beaucaire; H. Pitsch; C. Largeau

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Process removes Sr from nuclear wastes  

Science Journals Connector (OSTI)

Process removes Sr from nuclear wastes ... Scientists at Argonne National Laboratory have devised a chemical process for extracting and recovering strontium-90 from liquid nuclear wastes. ... Argonne chemist E. Philip Horwitz, head of the team, says it could be a significant aid in managing such radioactive wastes. ...

WARD WORTHY

1990-09-10T23:59:59.000Z

122

Update Direct-Strike Lightning Environment for Stockpile-to-Target Sequence: Supplement LLNL Subcontract #B568621 Lightning Protection at the Yucca Mountain Waste Storage Facility  

SciTech Connect (OSTI)

The University of Florida has surveyed all relevant publications reporting lightning damage to metals, metals which could be used as components of storage containers for nuclear waste materials. We show that even the most severe lightning could not penetrate the stainless steel thicknesses proposed for nuclear waste storage casks.

Uman, M A

2008-10-09T23:59:59.000Z

123

The U.S. Nuclear Waste Technical Review Board Status Update  

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

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The U S Nuclear Waste Technical Review Board The U.S. Nuclear Waste Technical Review Board Status Update Presented to: National Transportation Stakeholders Forum Presented By: National Transportation Stakeholders Forum Mark Abkowitz May 11, 2011 The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U S Nuclear Waste Technical Review Board established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to: - transportation, packaging and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) - site characterization, design, development, and operations of facilities for

124

Metal Encapsulation of Ceramic Nuclear Waste  

Science Journals Connector (OSTI)

A conceptual flow sheet is presented for encapsulating a ceramic waste form in solid lead, using existing or ... encapsulation might be applied to other solid radioactive wastes from the nuclear fuel cycle. It is...

L. J. Jardine; M. J. Steindler

1979-01-01T23:59:59.000Z

125

Public risk perception of nuclear waste  

Science Journals Connector (OSTI)

Nuclear waste has emerged as a very salient issue in the nuclear power debate. In the present study, a broad range of risk perception and attitude dimensions concerned with nuclear waste was investigated. It was found that most respondents from the general public were not willing to accept a local high-level nuclear waste repository in their home region. Nuclear waste was seen, by the public, as a very important issue. Regression analysis of perceived nuclear waste risk yielded a high level of explained variance (about 65%). Fear of radiation appeared to be an important determinant of the perceived risk and so was attitude to nuclear power, risk sensitivity and a pooled measure of the traditional psychometric dimensions of risk perception. A structural equations model of acceptance of a local repository was quite successful in explaining acceptance.

Lennart Sjoberg; Britt-Marie Drottz-Sjoberg

2009-01-01T23:59:59.000Z

126

RADIOACTIVE WASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK-RESULTS OF FIELD INVESTIGATIONS AT STRIPA, SWEDEN  

E-Print Network [OSTI]

Waste Storage in Mined Caverns—Program Summary. LawrenceWASTE STORAGE IN MINED CAVERNS IN CRYSTALLINE ROCK- BESULTS

Witherspoon, P.A.

2010-01-01T23:59:59.000Z

127

U.S. Nuclear Waste Technical Review Board Performance Evaluation  

E-Print Network [OSTI]

Addendum A Addendum A U.S. Nuclear Waste Technical Review Board Performance Evaluation Fiscal Year 2005 The U.S. Nuclear Waste Technical Review Board The Nuclear Waste Policy Amendments Act nuclear fuel and defense high-level radioactive waste. The Act also estab lished the U.S. Nuclear Waste

128

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A  

SciTech Connect (OSTI)

This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification.

Bowman, R.C.

1994-04-01T23:59:59.000Z

129

Cryograb: A Novel Approach to the Retrieval of Waste from Underground Storage Tanks - 13501  

SciTech Connect (OSTI)

The UK's National Nuclear Laboratory (NNL) is investigating the use of cryogenic technology for the recovery of nuclear waste. Cryograb, freezing the waste on a 'cryo-head' and then retrieves it as a single mass which can then be treated or stabilized as necessary. The technology has a number of benefits over other retrieval approaches in that it minimizes sludge disturbance thereby reducing effluent arising and it can be used to de-water, and thereby reduce the volume of waste. The technology has been successfully deployed for a variety of nuclear and non-nuclear waste recovery operations. The application of Cryograb for the recovery of waste from US underground storage tanks is being explored through a US DOE International Technology Transfer and Demonstration programme. A sample deployment being considered involves the recovery of residual mounds of sludge material from waste storage tanks at Savannah River. Operational constraints and success criteria were agreed prior to the completion of a process down selection exercise which specified the preferred configuration of the cryo-head and supporting plant. Subsequent process modeling identified retrieval rates and temperature gradients through the waste and tank infrastructure. The work, which has been delivered in partnership with US DOE, SRNL, NuVision Engineering and Frigeo AB has demonstrated the technical feasibility of the approach (to TRL 2) and has resulted in the allocation of additional funding from DOE to take the programme to bench and cold pilot-scale trials. (authors)

O'Brien, Luke; Baker, Stephen; Bowen, Bob [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom)] [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom); Mallick, Pramod; Smith, Gary [US Department of Energy (United States)] [US Department of Energy (United States); King, Bill [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Judd, Laurie [NuVision Engineering (United States)] [NuVision Engineering (United States)

2013-07-01T23:59:59.000Z

130

THERMAL IMPACT OF WASTE EMPLACEMENT AND SURFACE COOLING ASSOCIATED WITH GEOLOGIC DISPOSAL OF NUCLEAR WASTE  

E-Print Network [OSTI]

d long-term storage and even methods for centralized waste •long-term storage of spent fuel, interim storage of high levei wastestorage of solid wastes of IAEA categories 3 and 4. 5) studies of long-term

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

131

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors  

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

6 6 Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites December 2008 U.S. Department of Energy Office of Civilian Radioactive Waste Management Washington, D.C. Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel The picture on the cover is the Connecticut Yankee Independent Spent Fuel Storage Installation site in Haddam, Connecticut, with 43 dry storage NRC-licensed dual-purpose (storage and transport) casks. ii Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel EXECUTIVE SUMMARY The House Appropriations Committee Print that accompanied the Consolidated Appropriations Act, 2008, requests that the U.S. Department of Energy (the Department):

132

Conceivable new recycling of nuclear waste by nuclear power companies in their plants  

E-Print Network [OSTI]

We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

Ruggero Maria Santilli

1997-04-09T23:59:59.000Z

133

Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)  

SciTech Connect (OSTI)

This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas.

SIMMONS, F.M.

2000-03-29T23:59:59.000Z

134

Vermont Yankee experience with interim storage of low level radioactive waste in concrete modules  

SciTech Connect (OSTI)

This paper discusses the implementation of interim storage of low level radioactive waste using concrete modules at the Vermont Yankee Nuclear Power Station in Vernon, Vermont. Under the threat of possible loss of disposal capability in 1986, Vermont Yankee first considered the on-site storage option in 1985. prior to settling on a design, an investigation and economic analysis was performed of several designs. Modular concrete storage on a gravel pad was chosen as the most economical and the one providing the greatest flexibility. The engineering work, safety analysis, and pad construction were completed in 1985. Because of the passage of the Low Level Radioactive Waste Policy amendments Act in 1985, the loss of disposal capability did not occur in 1986. However, because the State of Vermont failed to meet the milestones of the Amendments Act, Vermont Yankee was restricted from the existing disposal sites on January 31, 1989. As a result, modules were purchased and waste was stored on site from 1989 until 1991. In 1991, the State of Vermont came back into compliance with the Amendments Act, and all waste stored on-site was shipped for burial. During the storage period 2 types of modules (1 box type and 1 cylinder type) were used. Lessons were learned, and changes were made to better control the off-site dose contribution of the waste. Recommendations are made to enhance the usability of the facility, such s lighting power, phones, etc. A shortcoming of the module storage concept is the inability to move waste during inclement weather. Despite this, the modules have provided an economical, technically sound, method of waste storage. The storage pad has not been used since 1991, but work is under way to review, and update as necessary, the safety analysis and procedures in preparation for reuse of the on-site storage facility after June 30, 1994.

Berger, S.; Weyman, D. [Vermont Yankee Nuclear Power Corporation, Vernon, VT (United States)

1995-05-01T23:59:59.000Z

135

Chemistry related to isolation of high-level nuclear waste  

Science Journals Connector (OSTI)

Chemistry related to isolation of high-level nuclear waste ... This article discusses the isolation of high-level nuclear waste. ... Radioactivity, Radiation, and the Chemistry of Nuclear Waste ...

Darleane C. Hoffman; Gregory R. Choppin

1986-01-01T23:59:59.000Z

136

Basic Research for Evaluating Nuclear Waste Form Performance  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Don J. Bradley

137

Rock Alteration and Mineral Transformations for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Philip A. Helmke

138

CARTER MAPS PLAN TO MANAGE NUCLEAR WASTE  

Science Journals Connector (OSTI)

CARTER MAPS PLAN TO MANAGE NUCLEAR WASTE ... The first part of the 15-year program will concentrate on locating and characterizing a number of potential repository sites, capable of isolating from the biosphere both defense and commercial high-level nuclear wastes. ...

1980-02-18T23:59:59.000Z

139

Court blocks testing of nuclear waste site  

Science Journals Connector (OSTI)

Court blocks testing of nuclear waste site ... WIPP was authorized by Congress in 1979 to provide an R&D facility to demonstrate safe handling, transport, and disposal of "mixed" transuranic wastes (contaminated with radioactive plutonium-239 and hazardous chemicals), which are now stored temporarily at DOE nuclear-weapons-making facilities. ...

RICHARD SELTZER

1992-02-10T23:59:59.000Z

140

Nuclear Waste and the Distant Future Nuclear Waste and the Distant Future  

E-Print Network [OSTI]

Nuclear Waste and the Distant Future 1 Nuclear Waste and the Distant Future PER F. PETERSON WILLIAM://www.issues.org/22.4/peterson.html Regulation of nuclear hazards must be consistent with rules governing other of the radioactive material generated by nuclear energy decays away over short times ranging from minutes to several

Kammen, Daniel M.

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Synergic and conflicting issues in planning underground use to produce energy in densely populated countries, as Italy: Geological storage of CO2, natural gas, geothermics and nuclear waste disposal  

Science Journals Connector (OSTI)

In densely populated countries there is a growing and compelling need to use underground for different and possibly coexisting technologies to produce “low carbon” energy. These technologies include (i) clean coal combustion merged with CO2 Capture and Storage (CCS); (ii) last-generation nuclear power or, in any case, safe nuclear wastes disposal, both “temporary” and “geological” somewhere in Europe (at least in one site): Nuclear wastes are not necessarily associated to nuclear power plants; (iii) safe natural gas (CH4) reserves to allow consumption also when the foreign pipelines are less available or not available for geopolitical reasons and (iv) “low-space-consuming” renewables in terms of Energy Density Potential in Land (EDPL measured in [GW h/ha/year]) as geothermics. When geothermics is exploited as low enthalpy technology, the heat/cool production could be associated, where possible, to increased measures of “building efficiency”, low seismic risks building reworking and low-enthalpy heat managing. This is undispensable to build up “smart cities”. In any case the underground geological knowledge is prerequisite. All these technologies have been already proposed and defined by the International Energy Agency (IEA) Road Map 2009 as priorities for worldwide security: all need to use underground in a rational and safe manner. The underground is not renewable in most of case histories [10,11]. IEA recently matched and compared different technologies in a unique “Clean Energy Economy” improved document (Paris, November 16–17, 2011), by the contribution of this vision too (see reference). In concert with “energy efficiency” improvement both for plants and buildings, in the frame of the “smart cities” scenarios, and the upstanding use of “energy savings”, the energetic planning on regional scale where these cities are located, are strategic for the year 2050: this planning is strongly depending by the underground availability and typology. Therefore, if both literature and European Policy are going fast to improve the concept of “smart cities” this paper stresses the concept of “smart regions”, more strategic than “smart cities”, passing throughout a discussion on the synergic and conflicting use of underground to produce energy for the “smart regions” as a whole. The paper highlights the research lines which are urgent to plan the soundest energy mix for each region by considering the underground performances case by case: a worldwide mapping, by GIS tools of this kind of information could be strategic for all the “world energy management” authorities, up to ONU, with its Intergovernmental Panel on Climate Change (IPCC), the G20, the Carbon Sequestration Leadership Forum (CSLF) and the European Platforms such as the “Zero Emissions Fossil Fuel Power Plants” (EU-ZEP Platform), the Steel Platform, the Biomass Platform too. All of these organizations agree on the need for synergistic and coexistent uses of underground for geological storage of CO2, CH4, nuclear waste and geothermic exploitation. The paper is therefore a discussion of the tools, methods and approaches to these underground affecting technologies, after a gross view of the different uses of underground to produce energy for each use, with their main critical issues (i.e. public acceptance in different cases). The paper gives some gross evaluation for the Lazio Region and some hints from the Campania Region, located in Central Italy. Energy Density Potential in Land (EDPL), is calculated for each renewable energy technology (solar, wind, geothermal) highlighting the potentiality of the last. Why the Italian case history among the densely populated countries? on the Italian territory is hard to find suitable areas (mostly if greenfields) to use the own underground, with respect to other European countries, due to the presence of seismotectonic activity and many faulted areas characterized by Diffuse Degassing Structures (DDSs, which are rich in CO2 and CH4). In this cases, public acceptan

Fedora Quattrocchi; Enzo Boschi; Angelo Spena; Mauro Buttinelli; Barbara Cantucci; Monia Procesi

2013-01-01T23:59:59.000Z

142

EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings  

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

0: Construction of Mixed Waste Storage RCRA Facilities, 0: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee SUMMARY This EA evaluates the environmental impacts of a proposal to construct and operate two mixed (both radioactive and hazardous) waste storage facilities (Buildings 7668 and 7669) in accordance with Resource Conservation and Recovery Act requirements. Site preparation and construction activities would take place at the U.S. Department of Energy's Oak Ridge National Laboratory in Oak Ridge, Tennessee. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 16, 1994 EA-0820: Finding of No Significant Impact

143

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

the Board will focus include the technical implications of very long-term dry storage of commercial spent, facility operation and design, and waste storage and disposal. con266vf #12;con266vf 2 The Board to have responsibility under existing law for the long-term management and disposition of DOE-owned spent

144

Nuclear Waste Management. Semiannual progress report, April 1984-September 1984  

SciTech Connect (OSTI)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; and supporting studies. 33 figures, 13 tables.

McElroy, J.L.; Powell, J.A. (comps.)

1984-12-01T23:59:59.000Z

145

Nuclear Waste Management. Semiannual progress report, October 1984-March 1985  

SciTech Connect (OSTI)

Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs.

McElroy, J.L.; Powell, J.A. (comps.)

1985-06-01T23:59:59.000Z

146

Secretarial Determination of the Adequacy of the Nuclear Waste...  

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

Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee I adopt and approve the attached...

147

Enforcement Notice of Intent to Investigate, Nuclear Waste Partnership...  

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

Nuclear Waste Partnership, LLC Enforcement Notice of Intent to Investigate, Nuclear Waste Partnership, LLC June 16, 2014 DOE Office of Enforcement issues a Notice of Intent to...

148

DOE woos scientists for nuclear waste work  

Science Journals Connector (OSTI)

DOE woos scientists for nuclear waste work ... The Department of Energy has established a $50 million-per-year program to involve for the first time the basic research community in cleaning up nuclear waste at DOE's widely scattered, heavily contaminated nuclear weapons facilities. ... Cleanup of waste at DOE's nuclear weapons facilities—at Savannah River, S.C.; Oak Ridge, Term.; Hanford, Wash.; and Paducah, Ky.; among others—is expected to take at least 50 years and cost at least $300 billion. ...

WIL LEPKOWSKI

1996-02-19T23:59:59.000Z

149

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6  

SciTech Connect (OSTI)

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

Not Available

1994-04-01T23:59:59.000Z

150

Large Scale Computing and Storage Requirements for Nuclear Physics  

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

Science at NERSC HPC Requirements Reviews Requirements for Science: Target 2014 Nuclear Physics (NP) Large Scale Computing and Storage Requirements for Nuclear Physics:...

151

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

152

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

153

SWEDISH-AMERICAN COOPERATIVE PROGRAM ON RADIOACTIVE WASTE STORAGE IN MINED CAVERNS. PROGRAM SUMMARY  

E-Print Network [OSTI]

WASTE STORAGE IN MINED CAVERNS by P. A. Witherspoon LawrenceWASTE STORAGE IN MINED CAVERNS INTRODUCTION Final and safeon the possibility of using mined caverns in salt as waste

Witherspoon, P.A.

2011-01-01T23:59:59.000Z

154

Nuclear Waste Policy Act.doc  

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

Civilian Radioactive Civilian Radioactive Waste Management Washington, D.C. 20585 March 2004 i THE NUCLEAR WASTE POLICY ACT OF 1982 1 An Act to provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel, to establish a program of research, development, and demonstration regarding the disposal of high-level radioactive waste and spent nuclear fuel, and for other purposes. Be it enacted by the Senate and House of Representatives of the United States of America in Congress assembled, SHORT TITLE AND TABLE OF CONTENTS Section 1. This Act may be cited as the "Nuclear Waste Policy Act of 1982". Sec. 1. Short title and table of contents...........................................................................i

155

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

156

Waste Encapsulation and Storage Facility - Hanford Site  

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

of heat were removed from the high level waste tanks at Hanford. Called cesium and strontium, these elements had to be taken out of single shell waste tanks to reduce the...

157

Aluminum phosphate ceramics for waste storage  

SciTech Connect (OSTI)

The present disclosure describes solid waste forms and methods of processing waste. In one particular implementation, the invention provides a method of processing waste that may be particularly suitable for processing hazardous waste. In this method, a waste component is combined with an aluminum oxide and an acidic phosphate component in a slurry. A molar ratio of aluminum to phosphorus in the slurry is greater than one. Water in the slurry may be evaporated while mixing the slurry at a temperature of about 140-200.degree. C. The mixed slurry may be allowed to cure into a solid waste form. This solid waste form includes an anhydrous aluminum phosphate with at least a residual portion of the waste component bound therein.

Wagh, Arun; Maloney, Martin D

2014-06-03T23:59:59.000Z

158

Geological Constraints on High-Level Nuclear Waste Disposal and their Relationship to Possible  

E-Print Network [OSTI]

to Possible Long Term Storage Solutions- A Case Study of the Yucca Mountain Project Teresa Dunn 2013 #12;Dunn systems and geologic composition in the selection and development of a secure, long-term storage facilityDunn 1 Geological Constraints on High-Level Nuclear Waste Disposal and their Relationship

Polly, David

159

Removing nuclear waste, one shipment at a time  

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

Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way...

160

SRNL CRP progress report [Development of Melt Processed Ceramics for Nuclear Waste Immobilization  

SciTech Connect (OSTI)

A multi-phase ceramic waste form is being developed at the Savannah River National Laboratory (SRNL) for treatment of secondary waste streams generated by reprocessing commercial spent nuclear. The envisioned waste stream contains a mixture of transition, alkali, alkaline earth, and lanthanide metals. Ceramic waste forms are tailored (engineered) to incorporate waste components as part of their crystal structure based on knowledge from naturally found minerals containing radioactive and non-radioactive species similar to the radionuclides of concern in wastes from fuel reprocessing. The ability to tailor ceramics to mimic naturally occurring crystals substantiates the long term stability of such crystals (ceramics) over geologic timescales of interest for nuclear waste immobilization [1]. A durable multiphase ceramic waste form tailored to incorporate all the waste components has the potential to broaden the available disposal options and thus minimize the storage and disposal costs associated with aqueous reprocessing.

Amoroso, J.; Marra, J.

2014-10-02T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Technical basis for performance goals, design requirements, and material recommendations for the NNWSI [Nevada Nuclear Waste Storage Investigations] Repository Sealing Program  

SciTech Connect (OSTI)

The objectives are to develop performance goals, to assess the need for seals, to define design requirements, and to recommend potential sealing materials for the sealing system. Performance goals are the allowable amounts of water that can enter the waste disposal areas directly from the rock mass above the repository and indirectly from shafts and ramps connecting to the underground facility. These goals are developed using a numerical model that calculates radionuclide releases. To determine the need for sealing, estimates of water flow into shafts, ramps, and the underground facility under anticipated conditions are developed and are compared with the performance goals. It is concluded that limited sealing measures, such as emplacement of shaft fill, are sufficient to properly isolate the radioactive waste in the repository. A broad range of sealing design options and associated hydrologic design requirements are proposed to provide a greater degree of assurance that the hydrologic performance goals can be met even if unanticipated hydrologic flows enter the waste disposal areas. The hydrologic design requirements are specific, hydraulic conductivity values selected for specific, seal design options to achieve the performance goals. Using these hydrologic design requirements and additional design requirements, preferred materials are identified for continued design and laboratory analyses. In arriving at these preferred materials, results from previous laboratory testing are briefly discussed. 96 refs., 48 figs., 28 tabs.

Fernandez, J.A.; Kelsall, P.C.; Case, J.B.; Meyer, D.

1987-09-01T23:59:59.000Z

162

Whats Next for Nuclear Waste  

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

WHAT'S NEXT FOR NUCLEAR WASTE? A New Strategy for the CSRA September 2009 PREFACE This White Paper was prepared by the Savannah River Site Community Reuse Organization (SRSCRO) to...

163

US nuclear waste: Widespread problem of disposal  

Science Journals Connector (OSTI)

... individual states in the United States to develop facilities for disposal of low-level radioactive waste produced by ... produced by nuclear reactors, industry and biomdical research and treatment. The federal Low-Level ...

Christopher Earl

1984-07-19T23:59:59.000Z

164

Questioning nuclear waste substitution: a case study  

Science Journals Connector (OSTI)

This article looks at the ethical quandaries, and their social and political context, which emerge as a result of international nuclear waste substitution. In particular it addresses the dilemmas inherent within ...

Alan Marshall

2007-03-01T23:59:59.000Z

165

Permitting plan for the high-level waste interim storage  

SciTech Connect (OSTI)

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

Deffenbaugh, M.L.

1997-04-23T23:59:59.000Z

166

Federal nuclear waste cleanup plan proposed  

Science Journals Connector (OSTI)

Federal nuclear waste cleanup plan proposed ... The Department of Energy has asked Congress to find $19.5 billion over the next five years to finance initial cleanup of environmental contamination at its nuclear, primarily weapons, facilities. ... DOE estimates that to begin implementing the plan in 1990, it needs considerably more than the $1.3 billion originally requested for defense waste and environmental restoration activities. ...

JANICE LONG

1989-08-07T23:59:59.000Z

167

TRU waste certification compliance requirements for contact-handled wastes retrieved from storage for shipment to the WIPP  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE Orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste.

Not Available

1982-09-01T23:59:59.000Z

168

Natural analogues of nuclear waste glass corrosion.  

SciTech Connect (OSTI)

This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses.

Abrajano, T.A. Jr.; Ebert, W.L.; Luo, J.S.

1999-01-06T23:59:59.000Z

169

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

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

Nuclear Fuel Cycle and Nuclear Fuel Cycle and Waste Management Technologies Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Fuel Cycle and Waste Management Technologies Overview Bookmark and Share Much of the NE Division's research is directed toward developing software and performing analyses, system engineering design, and experiments to support the demonstration and optimization of the electrometallurgical

170

System Engineering Design [Nuclear Waste Management using  

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

System Engineering System Engineering Design Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology System Engineering Design Bookmark and Share Two major pieces of electrometallurgical process equipment are the Electrorefiner and the Cathode Processor. NE personnel have been involved in the conceptual design, final design, procurement, manufacture,

171

Vitrified municipal waste as a host form for high-level nuclear waste  

Science Journals Connector (OSTI)

Using glass as a safe and long term hosting matrix for hazardous wastes and for the immobilization of heavy metals and nuclear wastes has become an attractive method [3]. The most known glasses used as nuclear waste

N. A. El-Alaily; E. M. Abou-Hussein…

2014-01-01T23:59:59.000Z

172

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

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

Investment in Nuclear Fuel Storage Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

173

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

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

Announces New Investment in Nuclear Fuel Storage Announces New Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

174

Doing the impossible: Recycling nuclear waste  

ScienceCinema (OSTI)

A Science Channel feature explores how Argonne techniques could be used to safely reduce the amount of radioactive waste generated by nuclear power?the most plentiful carbon-neutral energy source. Read more at http://www.anl.gov/Media_Center/ArgonneNow/Fall_2009/nuclear.html

None

2013-04-19T23:59:59.000Z

175

Deep Geologic Nuclear Waste Disposal - No New Taxes - 12469  

SciTech Connect (OSTI)

To some, the perceived inability of the United States to dispose of high-level nuclear waste justifies a moratorium on expansion of nuclear power in this country. Instead, it is more an example of how science yields to social pressure, even on a subject as technical as nuclear waste. Most of the problems, however, stem from confusion on the part of the public and their elected officials, not from a lack of scientific knowledge. We know where to put nuclear waste, how to put it there, how much it will cost, and how well it will work. And it's all about the geology. The President's Blue Ribbon Commission on America's Nuclear Future has drafted a number of recommendations addressing nuclear energy and waste issues (BRC 2011) and three recommendations, in particular, have set the stage for a new strategy to dispose of high-level nuclear waste and to manage spent nuclear fuel in the United States: 1) interim storage for spent nuclear fuel, 2) resumption of the site selection process for a second repository, and 3) a quasi-government entity to execute the program and take control of the Nuclear Waste Fund in order to do so. The first two recommendations allow removal and storage of spent fuel from reactor sites to be used in the future, and allows permanent disposal of actual waste, while the third controls cost and administration. The Nuclear Waste Policy Act of 1982 (NPWA 1982) provides the second repository different waste criteria, retrievability, and schedule, so massive salt returns as the candidate formation of choice. The cost (in 2007 dollars) of disposing of 83,000 metric tons of heavy metal (MTHM) high-level waste (HLW) is about $ 83 billion (b) in volcanic tuff, $ 29 b in massive salt, and $ 77 b in crystalline rock. Only in salt is the annual revenue stream from the Nuclear Waste Fund more than sufficient to accomplish this program without additional taxes or rate hikes. The cost is determined primarily by the suitability of the geologic formation, i.e., how well it performs on its own for millions of years with little engineering assistance from humans. It is critical that the states most affected by this issue (WA, SC, ID, TN, NM and perhaps others) develop an independent multi-state agreement in order for a successful program to move forward. Federal approval would follow. Unknown to most, the United States has a successful operating deep permanent geologic nuclear repository for high and low activity waste, called the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Its success results from several factors, including an optimal geologic and physio-graphic setting, a strong scientific basis, early regional community support, frequent interactions among stakeholders at all stages of the process, long-term commitment from the upper management of the U.S. Department of Energy (DOE) over several administrations, strong New Mexico State involvement and oversight, and constant environmental monitoring from before nuclear waste was first emplaced in the WIPP underground (in 1999) to the present. WIPP is located in the massive bedded salts of the Salado Formation, whose geological, physical, chemical, redox, thermal, and creep-closure properties make it an ideal formation for long-term disposal, long-term in this case being greater than 200 million years. These properties also mean minimal engineering requirements as the rock does most of the work of isolating the waste. WIPP has been operating for twelve years, and as of this writing, has disposed of over 80,000 m{sup 3} of nuclear weapons waste, called transuranic or TRU waste (>100 nCurie/g but <23 Curie/1000 cm{sup 3}) including some high activity waste from reprocessing of spent fuel from old weapons reactors. All nuclear waste of any type from any source can be disposed in this formation better, safer and cheaper than in any other geologic formation. At the same time, it is critical that we complete the Yucca Mountain license application review so as not to undermine the credibility of the Nuclear Regulatory Commission and the scientific commun

Conca, James [RJLee Group, Inc., Pasco WA 509.205.7541 (United States); Wright, Judith [UFA Ventures, Inc., Richland, WA (United States)

2012-07-01T23:59:59.000Z

176

United States National Waste Terminal Storage argillaceous rock studies  

SciTech Connect (OSTI)

The past and present argillaceous rock studies for the US National Waste Terminal Storage Program consist of: (1) evaluation of the geological characteristics of several widespread argillaceous formations in the United States; (2) laboratory studies of the physical and chemical properties of selected argillaceous rock samples; and (3) two full-scale in situ surface heater experiments that simulate the emplacement of heat-generating radioactive waste in argillaceous rock.

Brunton, G.D.

1981-01-01T23:59:59.000Z

177

Nuclear waste could bury itself  

Science Journals Connector (OSTI)

... we can have strong scientific confidence in," says the chairman of Britain's Radioactive Waste Management Advisory Committee, Charles Curtis, a geochemist at the University of Manchester. ...

Tom Clarke

2003-08-13T23:59:59.000Z

178

US nuclear waste site "unsuitable"  

Science Journals Connector (OSTI)

... about the suitability of Yucca Mountain as the site for the nation's first highlevel nuclear ...

Mary Manning

1988-01-28T23:59:59.000Z

179

Waste-heat recovery in batch processes using heat storage  

SciTech Connect (OSTI)

The waste-heat recovery in batch processes has been studied using the pinch-point method. The aim of the work has been to investigate theoretical and practical approaches to the design of heat-exchanger networks, including heat storage, for waste-heat recovery in batch processes. The study is limited to the incorporation of energy-storage systems based on fixed-temperature variable-mass stores. The background for preferring this to the alternatives (variable-temperature fixed-mass and constant-mass constant-temperature (latent-heat) stores) is given. It is shown that the maximum energy-saving targets as calculated by the pinch-point method (time average model, TAM) can be achieved by locating energy stores at either end of each process stream. This theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. A simple procedure for determining a number of heat-storage tanks sufficient to achieve the maximum energy-saving targets as calculated by the pinch-point method is described. This procedure relies on combinatorial considerations, and could therefore be labeled the combinatorial method for incorporation of heat storage in heat-exchanger networks. Qualitative arguments justifying the procedure are presented. For simple systems, waste-heat recovery systems with only three heat-storage temperatures (a hot storage, a cold storage, and a heat store at the pinch temperature) often can achieve the maximum energy-saving targets. Through case studies, six of which are presented, it is found that a theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. The description of these six cases is intended to be sufficiently detailed to serve as benchmark cases for development of alternative methods.

Stoltze, S.; Mikkelsen, J.; Lorentzen, B.; Petersen, P.M.; Qvale, B. [Technical Univ. of Denmark, Lyngby (Denmark). Lab. for Energetics

1995-06-01T23:59:59.000Z

180

Impact of earthen waste storage on nitrate concentration of surface water  

Science Journals Connector (OSTI)

One of the major sources of nitrogen is animal waste stored in earthen waste storage or unlined storage ponds. Quantifying seepage and mass transport of ... is the first critical step in estimating the long-term ...

Tasuku Kato; Motoko Shimura

2007-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

U.S. Department of Energy Awards Contracts for Waste Storage...  

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

Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis...

182

Pump targets hydrogen risk in nuclear waste tank  

Science Journals Connector (OSTI)

Pump targets hydrogen risk in nuclear waste tank ... Researchers believe that thermal and radiolytic breakdown of organic compounds in the tank's wastes produces the hydrogen. ...

DEBORAH ILLMAN

1993-07-12T23:59:59.000Z

183

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 37 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board as chair, on the U.S. Nuclear Regulatory Commission's Advisory Commit tee on Nuclear Waste. His areas to the Nuclear Waste Technical Review Board on June 26, 2002, by President George W. Bush. Dr. Abkowitz

184

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 31 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board.S. Nuclear Waste Technical Review Board as Chairman on September 10, 2004, by President George W. Bush. Dr­2004), 4 years as chair, on the U.S. Nuclear Regulatory Commission's Advisory Committee on Nuclear Waste

185

Radioactivity, Radiation, and the Chemistry of Nuclear Waste  

Science Journals Connector (OSTI)

Radioactivity, Radiation, and the Chemistry of Nuclear Waste ... A chemistry course for nonmajors, which centers on the chemistry of nuclear waste, has as a prerequisite at least two semesters of general chemistry. ... The final section of the course is devoted to the treatment of nuclear waste by vitrification and applications based on nuclear or radiation chemistry. ...

Nick Zevos

2002-06-01T23:59:59.000Z

186

Nuclear Waste Technical Review Board Members Appendix A 53  

E-Print Network [OSTI]

51 Appendix A Nuclear Waste Technical Review Board Members #12;#12;Appendix A 53 B. John Garrick, Ph.D., P.E. Chairman Dr. B. John Garrick was appointed to the U.S. Nuclear Waste Technical Review, on the U.S. Nuclear Regula- tory Commission's Advisory Committee on Nuclear Waste. His areas of expertise

187

Sandia National Laboratories: Batteries & Energy Storage Publications  

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

Radioactive Waste Prioritized Safeguards and Security Issues for extended Storage of Used Nuclear Fuel Research to Improve Transportation Energy Storage Fact Sheet Sandia's Battery...

188

Refinishing contamination floors in Spent Nuclear Fuels storage basins  

SciTech Connect (OSTI)

The floors of the K Basins at the Hanford Site are refinished to make decontamination easier if spills occur as the spent nuclear fuel (SNF) is being unloaded from the basins for shipment to dry storage. Without removing the contaminated existing coating, the basin floors are to be coated with an epoxy coating material selected on the basis of the results of field tests of several paint products. The floor refinishing activities must be reviewed by a management review board to ensure that work can be performed in a controlled manner. Major documents prepared for management board review include a report on maintaining radiation exposure as low as reasonably achievable, a waste management plan, and reports on hazard classification and unreviewed safety questions. To protect personnel working in the radiation zone, Operational Health Physics prescribed the required minimum protective methods and devices in the radiological work permit. Also, industrial hygiene safety must be analyzed to establish respirator requirements for persons working in the basins. The procedure and requirements for the refinishing work are detailed in a work package approved by all safety engineers. After the refinishing work is completed, waste materials generated from the refinishing work must be disposed of according to the waste management plan.

Huang, F.F.; Moore, F.W.

1997-07-11T23:59:59.000Z

189

General Heat Transfer Characterization and Empirical Models of Material Storage Temperatures for the Los Alamos Nuclear Materials Storage Facility  

SciTech Connect (OSTI)

The Los Alamos National Laboratory's Nuclear Materials Storage Facility (NMSF) is being renovated for long-term storage of canisters designed to hold heat-generating nuclear materials. A fully passive cooling scheme, relying on the transfer of heat by conduction, free convection, and radiation has been proposed as a reliable means of maintaining material at acceptable storage temperatures. The storage concept involves placing radioactive materials, with a net heat-generation rate of 10 W to 20 W, inside a set of nested steel canisters. The canisters are, in placed in holding fixtures and positioned vertically within a steel storage pipe. Several hundred drywells are arranged in a linear array within a large bay and dissipate the waste heat to the surrounding air, thus creating a buoyancy driven airflow pattern that draws cool air into the storage facility and exhausts heated air through an outlet stack. In this study, an experimental apparatus was designed to investigate the thermal characteristics of simulated nuclear materials placed inside two nested steel canisters positioned vertically on an aluminum fixture plate and placed inside a section of steel pipe. The heat-generating nuclear materials were simulated with a solid aluminum cylinder containing .an embedded electrical resistance heater. Calibrated type T thermocouples (accurate to ~ O.1 C) were used to monitor temperatures at 20 different locations within the apparatus. The purposes of this study were to observe the heat dissipation characteristics of the proposed `canister/fixture plate storage configuration, to investigate how the storage system responds to changes in various parameters, and to develop and validate empirical correlations to predict material temperatures under various operating conditions

J. D. Bernardin; W. S. Gregory

1998-10-01T23:59:59.000Z

190

Nuclear waste isolation activities report  

SciTech Connect (OSTI)

Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE`s radwaste management programs. (DLC)

None

1980-12-01T23:59:59.000Z

191

Phosphates as Nuclear Waste Forms  

Science Journals Connector (OSTI)

...environment of the disposal site, the...the sustained funding of the Office...EP (1999) Yucca Mountain as a radioactive-waste...Ultimate disposal of radioactive...Adirondack Mountains, New York...for geologic disposal. Mater Res...

Rodney C. Ewing; LuMin Wang

192

Ion implantation effects in insulators and the long-term stability of radioactive waste storage materials  

Science Journals Connector (OSTI)

Most insulator materials so far proposed for storing high-level radioactive wastes, such as glass and and the constituent minerals of ceramics are nuclear track detectors. Lead ion implantation experiments show that such materials should be transformed into “giant” nuclear tracks, when the internal fluence of heavy recoils emitted during the ?-decay of actinide elements stored in them exceeds a critical value, which corresponds to an equivalent storage period of a few thousand years for the wastes expected from a pressurized water reactor. In contrast, actinide bearing minerals are much more stable against ?-recoil damage. As nuclear tracks are extremely chemical reactive, ?-recoil damage is expected to shorten the lifetime of storage materials such as glass and ceramics against dissolution in ground waters. Fortunately new nuclear track concepts are already yielding guidelines for predicting and improving the long-term stability of storage materials. The results of the present studies also bear on the physics of ion implantation phenomena an insulator targets exposed to high fluences of low energy ions.

J.C. Dran; Y. Langevin; M. Maurette; J.C. Petit; B. Vassent

1981-01-01T23:59:59.000Z

193

Coincidence counter design for the assay of vitrified nuclear waste  

SciTech Connect (OSTI)

For the termination of nuclear safeguards and transfers to waste storage, the verification of the plutonium content in vitrified nuclear waste is required by international safeguards agreements. A novel design has been used to develop a coincidence counter for measuring vitrified nuclear waste. The authors have devised a method to measure the {sup 244}Cm content and to calculate the plutonium content from the curium-to-plutonium ratio. In order to provide unattended inspection, the counter is designed for continuous operation in the presence of highly radioactive samples: 3.0 {times} 10{sup 7} Rad/h gamma and 9.0 {times} 10{sup 7}/s neutron fluence. Operability under these conditions has been obtained by designing a heavily shielded detector with radiation hard components subtending a limited solid angle. A counting technique, Localized Source Term Coincidence Counting, has been developed to allow neutron assay of this type of sample. The system will be installed at the Power Nuclear Corporation Tokai Vitrification Facility in the later part of 1998.

Beddingfield, D.H.; Menlove, H.O. [Los Alamos National Lab., NM (United States); Iwamoto, T.; Tomikawa, H. [Power Nuclear Corp. (Japan)

1998-12-31T23:59:59.000Z

194

Final Environmental Impact Statement (Supplement to ERDA-1537, September 1977) Waste Management Operations Double-Shell Tanks for Defense High-Level Radioactive Waste Storage Savannah River Plant  

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

Do Do E/EIS-0062 FINAL ENVIRONMENTAL IMPACT mATEIUIENT (Supplement to ERDA-1537, September 1977) Waste ~ Management Operations Savannah River Plant ! Aiken, South Carolina Double-Shell Tanks for Defense High-Level Radioactive Waste Storage April 1980 U.S. DEPARTMENT OF ENERGY WASHINGTON. D.C.20545 1980 WL 94273 (F.R.) NOTICES DEPARTMENT OF ENERGY Office of Deputy Assistant Secretary for Nuclear Waste Management Double-Shell Tanks for Defense High-Level Radioactive Waste Storage, Savannah River Plant, Aiken, S.C. Wednesday, July 9, 1980 *46154 Record of Decision Decision. The decision has been made to complete the construction of the 14 double-shell tanks and use them to store defense high-level radioactive waste at the Savannah River Plant (SRP). Background. The SRP, located near Aiken, South Carolina, is a major installation of the

195

Neutron sources and transmutation of nuclear waste  

Science Journals Connector (OSTI)

Intense neutron sources with different energy spectra are of interest for a variety of applications. In my presentation, after briefly touching on the situation of radioactive waste in Italy, I will try to give a broad picture of Italian existing or proposed neutron sources based on accelerators, ranging from thermal to fast neutrons. I will also describe a specific project for a low-power ADS, aimed at studying neutron spectra as well as at demonstrating incineration and transmutation of nuclear waste.

M. Ripani

2013-01-01T23:59:59.000Z

196

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect (OSTI)

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-01-01T23:59:59.000Z

197

Technical considerations and problems associated with long-term storage of low-level waste  

SciTech Connect (OSTI)

If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) contracted with Brookhaven National Laboratory (BNL) several years ago (1984--86) to address the technical issues of extended storage. The dual objectives of this study were (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. In this summary of that study, the circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW.

Siskind, B.

1991-12-31T23:59:59.000Z

198

Nuclear waste management. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-06-01T23:59:59.000Z

199

The discourse of democracy in Canadian nuclear waste management policy  

Science Journals Connector (OSTI)

Canadian nuclear waste management policy has taken a deliberative democratic turn. What ... identify limitations in this turn by evaluating the Nuclear Waste Management Organization’s subsequent consultation proc...

Genevieve Fuji Johnson

2007-06-01T23:59:59.000Z

200

Move to test nuclear waste site draws fire  

Science Journals Connector (OSTI)

Move to test nuclear waste site draws fire ... The Department of Energy has stirred up a storm of opposition by taking administrative action, bypassing Congress, that would enable it to start testing an underground nuclear waste repository in New Mexico. ...

RICHARD SELTZER

1991-10-14T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

2008 DOE Spent Nuclear Fuel and High Level Waste Inventory  

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

Management >> National Spent Nuclear Fuel INL Logo Search 2008 DOE Spent Nuclear Fuel and High Level Waste Inventory Content Goes Here Skip Navigation Links Home Newsroom About INL...

202

7 - Assessing and modelling the performance of nuclear waste and associated packages for long-term management  

Science Journals Connector (OSTI)

Abstract: Examples of analytical approaches and methodologies for modelling the behaviour of waste forms and waste package metals in long-term management of spent nuclear fuel (SNF) and high level waste (HLW) are presented. Two cases, long-term geological disposal and interim extended dry storage, are considered. The integrity of the waste package (or canister) that serves as a barrier is dependent upon the performance of construction metals. Corrosion degradation modes of the construction metals are evaluated. The waste behaviour during SNF degradation is also evaluated. In each mode of corrosion or degradation, the associated risk insights are discussed in the system performance of disposal or storage.

T.M. Ahn

2013-01-01T23:59:59.000Z

203

Hanford facility dangerous waste permit application, PUREX storage tunnels  

SciTech Connect (OSTI)

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997.

Price, S.M.

1997-09-08T23:59:59.000Z

204

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

Schultz, Peter Andrew

2011-12-01T23:59:59.000Z

205

E-Print Network 3.0 - alkaline nuclear waste Sample Search Results  

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

waste Search Powered by Explorit Topic List Advanced Search Sample search results for: alkaline nuclear waste...

206

E-Print Network 3.0 - acidic nuclear waste Sample Search Results  

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

waste Search Powered by Explorit Topic List Advanced Search Sample search results for: acidic nuclear waste...

207

Glossary of Nuclear Waste Terms  

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

measures 12 feet in diameter by 22 feet long and weighs 200 tons. Chain Reaction A self-sustaining series of nuclear fissions taking place in a reactor core. Neutrons produced in...

208

UK waives nuclear waste rule for Georgia  

Science Journals Connector (OSTI)

... Only hours before the government's announcement, the Nuclear Installations Inspectorate (NII), part of the UK government's Health and Safety Executive, ... material for reprocessing until a complete safety audit and an assessment of the plant's waste-management capability had been carried out. The other contract is with the Australian ...

Alison Abbott

1998-04-30T23:59:59.000Z

209

Nuclear waste plans enter critical phase  

Science Journals Connector (OSTI)

... London. Britain's newly privatized nuclear power industry is facing a critical few months as it contemplates how to dispose of ... as it contemplates how to dispose of up to 300,000 cubic metres of radioactive waste by early next century á" and answer critics who claim that its plans are ...

Ehsan Masood

1996-10-31T23:59:59.000Z

210

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to January 1, 2001, to January 31, 2002 The U All NWTRB reports are available at www.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Appendices Appendix A U.S. Nuclear Waste Technical Review Board Members

211

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.S. Congress And The Secretary of Energy January 1, 2003, to December 31, 2003 #12;U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD 2003 Dr. Michael L. Corradini

212

Nuclear waste, public information and residential property values  

SciTech Connect (OSTI)

This document presents details about how increased public knowledge of high-level radioactive waste storage facilities effects the price of near-by residential properties.

Clark, E.E. [Marquette Univ., Milwaukee, WI (United States). Dept. of Economics]|[Argonne National Lab., IL (United States); Allison, T. [Argonne National Lab., IL (United States)

1995-10-10T23:59:59.000Z

213

Nuclear Waste Fund fee adequacy: An assessment  

SciTech Connect (OSTI)

The purpose of this report is to present the Department of Energy`s (the Department) analysis of the adequacy of the 1.00 mill per kilowatt-hour (kWh) fee being paid by the utilities generating nuclear power for the permanent disposal of their spent nuclear fuel (SNF). In accordance with the Nuclear Waste Policy Act (NWPA), the SNF would be disposed of in a geologic repository to be developed by the Department. An annual analysis of the fee`s adequacy is required by the NWPA.

NONE

1990-11-01T23:59:59.000Z

214

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington  

SciTech Connect (OSTI)

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Not Available

1994-07-01T23:59:59.000Z

215

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

216

Development of an Integrated Raman and Turbidity Fiber Optic Sensor for the In-Situ Analysis of High Level Nuclear Waste - 13532  

SciTech Connect (OSTI)

Stored nuclear waste must be retrieved from storage, treated, separated into low- and high-level waste streams, and finally put into a disposal form that effectively encapsulates the waste and isolates it from the environment for a long period of time. Before waste retrieval can be done, waste composition needs to be characterized so that proper safety precautions can be implemented during the retrieval process. In addition, there is a need for active monitoring of the dynamic chemistry of the waste during storage since the waste composition can become highly corrosive. This work describes the development of a novel, integrated fiber optic Raman and light scattering probe for in situ use in nuclear waste solutions. The dual Raman and turbidity sensor provides simultaneous chemical identification of nuclear waste as well as information concerning the suspended particles in the waste using a common laser excitation source. (authors)

Gasbarro, Christina; Bello, Job [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States)] [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States); Bryan, Samuel; Lines, Amanda; Levitskaia, Tatiana [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)] [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)

2013-07-01T23:59:59.000Z

217

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

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

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

218

Nuclear waste problem solved, claims Sweden's nuclear industry  

Science Journals Connector (OSTI)

... "WE are not going to leave any waste around that is going to harm anybody." So says Asea-Atom's Dr Kare ... Manners, one of the authors of a just-published report which asserts that the Swedish nuclear power industry has found a way of safely storing unreprocessed, spent fuel from ...

Wendy Barnaby

1978-07-06T23:59:59.000Z

219

US Department of Energy Storage of Spent Fuel and High Level Waste  

SciTech Connect (OSTI)

ABSTRACT This paper provides an overview of the Department of Energy's (DOE) spent nuclear fuel (SNF) and high level waste (HLW) storage management. Like commercial reactor fuel, DOE's SNF and HLW were destined for the Yucca Mountain repository. In March 2010, the DOE filed a motion with the Nuclear Regulatory Commission (NRC) to withdraw the license application for the repository at Yucca Mountain. A new repository is now decades away. The default for the commercial and DOE research reactor fuel and HLW is on-site storage for the foreseeable future. Though the motion to withdraw the license application and delay opening of a repository signals extended storage, DOE's immediate plans for management of its SNF and HLW remain the same as before Yucca Mountain was designated as the repository, though it has expanded its research and development efforts to ensure safe extended storage. This paper outlines some of the proposed research that DOE is conducting and will use to enhance its storage systems and facilities.

Sandra M Birk

2010-10-01T23:59:59.000Z

220

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

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

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from...

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Nuclear Waste Fund Activities Management Team | Department of Energy  

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

Waste Fund Activities Management Team Waste Fund Activities Management Team Nuclear Waste Fund Activities Management Team The Nuclear Waste Fund Activities Management Team has responsibility to: Manage the investments and expenditures of the Nuclear Waste Fund; Support correspondence regarding Nuclear Waste Policy Act issues raised by congressional, Inspector General, Government Accounting Office and Freedom of Information Act inquiries; and, Manage the annual fee adequacy assessment process. Applicable Documents Nuclear Waste Policy Act of 1982 Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste Standard Contract Amendment for New Reactors FY 2007 Total System Life Cycle Cost, Pub 2008 FY 2007 Fee Adequacy, Pub 2008 2009 Letter to Congress OCRWM Financial Statements for Annual Report for Years Ended

222

Nuclear Materials: Reconsidering Wastes and Assets - 13193  

SciTech Connect (OSTI)

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

Michalske, T.A. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

223

International nuclear waste management fact book  

SciTech Connect (OSTI)

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

Abrahms, C W; Patridge, M D; Widrig, J E

1995-11-01T23:59:59.000Z

224

Seal welded cast iron nuclear waste container  

DOE Patents [OSTI]

This invention identifies methods and articles designed to circumvent metallurgical problems associated with hermetically closing an all cast iron nuclear waste package by welding. It involves welding nickel-carbon alloy inserts which are bonded to the mating plug and main body components of the package. The welding inserts might be bonded in place during casting of the package components. When the waste package closure weld is made, the most severe thermal effects of the process are restricted to the nickel-carbon insert material which is far better able to accommodate them than is cast iron. Use of nickel-carbon weld inserts should eliminate any need for pre-weld and post-weld heat treatments which are a problem to apply to nuclear waste packages. Although the waste package closure weld approach described results in a dissimilar metal combination, the relative surface area of nickel-to-iron, their electrochemical relationship, and the presence of graphite in both materials will act to prevent any galvanic corrosion problem.

Filippi, Arthur M. (Pittsburgh, PA); Sprecace, Richard P. (Murrysville, PA)

1987-01-01T23:59:59.000Z

225

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

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

Analysis Analysis Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis While both wet and dry storage have been shown to be safe options for storing used nuclear fuel (UNF), the focus of the program is on dry storage of commercial UNF at reactor or centralized locations. This report focuses on the knowledge gaps concerning extended storage identified in numerous domestic and international investigations and provides the Used Fuel Disposition Campaign"s (UFDC) gap description, any alternate gap descriptions, the rankings by the various organizations, evaluation of the priority assignment, and UFDC-recommended action based on the comparison. Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis More Documents & Publications

226

Nuclear waste programs; Semiannual progress report, October 1991--March 1992  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Finn, P.A.; Gerding, T.J.; Hoh, J.C. [and others

1993-11-01T23:59:59.000Z

227

Radiotoxicity and decay heat power of spent nuclear fuel of VVER type reactors at long-term storage  

Science Journals Connector (OSTI)

......a controllable storage facility for cooling...transferred for long-term storage. The storage...adequately handle waste radiation characteristics...type reactors at long-term storage. | Radiotoxicity...of radioactive waste (radwaste) determines......

B. R. Bergelson; A. S. Gerasimov; G. V. Tikhomirov

2005-12-20T23:59:59.000Z

228

E-Print Network 3.0 - aqueous nuclear wastes Sample Search Results  

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

nuclear wastes Search Powered by Explorit Topic List Advanced Search Sample search results for: aqueous nuclear wastes Page: << < 1 2 3 4 5 > >> 1 Enabling a Sustainable Nuclear...

229

Fire protection guide for solid waste metal drum storage  

SciTech Connect (OSTI)

This guide provides a method to assess potential fire development in drum storage facilities. The mechanism of fire propagation/spread through stored drum arrays is a complex process. It involves flame heat transfer, transient conduction,convection, and radiation between drums (stored in an array configuration). There are several phenomena which may occur when drums are exposed to fire. The most dramatic is violent lid failure which results in total lid removal. When a drum loses its lid due to fire exposure, some or all of the contents may be ejected from the drum, and both the ejected combustible material and the combustible contents remaining within the container will burn. The scope of this guide is limited to storage arrays of steel drums containing combustible (primarily Class A) and noncombustible contents. Class B combustibles may be included in small amounts as free liquid within the solid waste contents.Storage arrays, which are anticipated in this guide, include single or multi-tier palletized (steel or wood pallets) drums,high rack storage of drums, and stacked arrays of drums where plywood sheets are used between tiers. The purpose of this guide is to describe a simple methodology that estimates the consequences of a fire in drum storage arrays. The extent of fire development and the resulting heat release rates can be estimated. Release fractions applicable to this type of storage are not addressed, and the transport of contaminants away from the source is not addressed. However, such assessments require the amount of combustible material consumed and the surface area of this burning material. The methods included in this guide do provide this information.

Bucci, H.M.

1996-09-16T23:59:59.000Z

230

Integrated mixed waste storage program for spent solvent and laboratory waste  

SciTech Connect (OSTI)

A new tank project was initiated to provide a facility capable of providing the necessary storage capacity while meeting the South Carolina Hazardous Waste Management Regulations. The new project was initiated as a Category 11, General Plant Project. This project funding strategy would have allowed SRS access to project funding without Congressional approval as a Line Item, permitting the use of an expedited schedule for design and construction. The project team and Department of Energy -- Savannah River were successful in obtaining FY94 Line Item funding for the new tank project. However, the operational date for the new tank project was extended to October 1996. The revised facility operational date did not support the date submitted to South Carolina Department of Heath and Environmental Control as part of the existing facility closure plan. A plan to alleviate the South Carolina Department of Heath and Environmental Control concerns with the SRS existing tanks system had to be developed prior to notifying the state that the operational date was extended to October 1996. The remainder of this paper presents the plan that was developed and presented to the South Carolina Department of Heath and Environmental Control. The SRS integrated mixed waste storage program is divided into three separate phase: (1) interim waste storage for the period between facility closure and operation of the new tank facility, (2) closure of the existing facility and (3) the new solvent storage facility.

Walker, C.M.

1994-03-01T23:59:59.000Z

231

Robotics for waste storage inspection: A user`s perspective  

SciTech Connect (OSTI)

Self-navigating robotic vehicles are now commercially available, and the technology supporting other important system components has also matured. Higher reliability and the obtainability of system support now make it practical to consider robotics as a way of addressing the growing operational requirement for the periodic inspection and maintenance of radioactive, hazardous, and mixed waste inventories. This paper describes preparations for the first field deployment of an autonomous container inspection robot at a Department of Energy (DOE) site. The Stored Waste Autonomous Mobile Inspector (SWAMI) is presently being completed by engineers at the Savannah River Technology Center (SRTC). It is a modified version of a commercially available robot. It has been outfitted with sensor suites and cognition that allow it to perform inspections of drum inventories and their storage facilities.

Hazen, F.B.

1994-06-23T23:59:59.000Z

232

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

Fuels Storage Fuels Storage and Transportation Planning Project (NFST) Program Status Jeff Williams Project Director National Transportation Stakeholders Forum Buffalo, New York May 2013 2  "With the appropriate authorizations from Congress, the Administration currently plans to implement a program over the next 10 years that:  Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility by 2021 with an initial focus on accepting used nuclear fuel from shut-down reactor sites;  Advances toward the siting and licensing of a larger interim storage facility to be available by 2025 that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used

233

Nuclear waste disposal in Switzerland: science, politics and uncertainty  

Science Journals Connector (OSTI)

In Switzerland, radioactive waste arises from electricity produced by five nuclear power plants and from the use of ... fields of medicine, industry and research. The waste is grouped into three categories: High-...

Simon Loew

2004-04-01T23:59:59.000Z

234

Extraction of cesium and strontium from nuclear waste  

DOE Patents [OSTI]

Cesium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5) [1-hydroxy-2-ethylhexyl]benzo 18-crown-6 compound and a cation exchanger in a matrix solution. Strontium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5') [1-hydroxyheptyl]cyclohexo 18-crown-6 compound, and a cation exchanger in a matrix solution.

Davis, Jr., Milton W. (Lexington, SC); Bowers, Jr., Charles B. (Columbia, SC)

1988-01-01T23:59:59.000Z

235

Evaluation of the Technical Basis for Extended Dry Storage and  

E-Print Network [OSTI]

-- Executive Summary U.S. Nuclear Waste Technical Review Board December 2010 #12;U.S.U.S. Nuclear Waste Technical Review Board Authors This report was prepared for the U.S. Nuclear Waste Technical Review Board.NWTRB.GOV ii #12;Extended Dry Storage and Transportation of Used Nuclear Fuel U.S. Nuclear Waste Technical

236

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect (OSTI)

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States [CIS]). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

237

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect (OSTI)

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States (CIS)). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

238

Title: An Advanced Solution for the Storage, Transportation and Disposal of Vitrified High Level Waste  

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

Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 1 AN ADVANCED SOLUTION FOR THE STORAGE, TRANSPORTATION AND DISPOSAL OF SPENT FUEL AND VITRIFIED HIGH LEVEL WASTE William J. Quapp Teton Technologies, Inc. 860 W. Riverview Dr. Idaho Falls, ID 83401 208-535-9001 ABSTRACT For future nuclear power deployment in the US, certain changes in the back end of the fuel cycle, i.e., disposal of high level waste and spent fuel, must become a real options. However, there exists another problem from the front end of the fuel cycle which has until recently, received less attention. Depleted uranium hexafluoride is a by-product of the enrichment process and has accumulated for over 50 years. It now represents a potential environmental problem. This paper describes a

239

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper (II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the orginal organic compounds, is subsequently blended with high level radioactive sludge and transferred to a virtrification facility for processing into borosilicate glass for long-term storage.

Doherty, Joseph P. (Elkton, MD); Marek, James C. (Augusta, GA)

1989-01-01T23:59:59.000Z

240

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper(II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the original organic compounds, is subsequently blended with high level radioactive sludge land transferred to a vitrification facility for processing into borosilicate glass for long-term storage. 2 figs., 3 tabs.

Doherty, J.P.; Marek, J.C.

1987-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

U.S. Nuclear Waste Technical Review Board Report to The U.S. Congressand The Secretary of Energy March 1, 2006­December 31, 2007 #12;#12;U.S. Nuclear Waste Technical Review Board Report to The U in this report. #12;#12;#12;U.S. Nuclear Waste Technical Review Board B. John Garrick, Ph.D., P.E., Chairman

242

Hot demonstrations of nuclear-waste processing technologies  

Science Journals Connector (OSTI)

Several types of nuclear-waste-treatment technologies are currently being demonstrated at Argonne National Laboratory-West, ranging from complex,...

H. F. McFarlane; K. M. Goff; F. S. Felicione; C. C. Dwight; D. B. Barber

1997-07-01T23:59:59.000Z

243

Congressional Preferences and the Advancement of American Nuclear Waste Policy.  

E-Print Network [OSTI]

??The problem of nuclear waste disposal has existed since the time of the Manhattan Project in World War II. Although there exist a number of… (more)

Ternate, Rhoel Gonzales

2013-01-01T23:59:59.000Z

244

Canister design for deep borehole disposal of nuclear waste .  

E-Print Network [OSTI]

??The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories… (more)

Hoag, Christopher Ian.

2006-01-01T23:59:59.000Z

245

DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary  

SciTech Connect (OSTI)

This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis.

DeMuth, S.F.

1996-10-01T23:59:59.000Z

246

Nuclear Hybrid Energy Systems: Molten Salt Energy Storage  

SciTech Connect (OSTI)

With growing concerns in the production of reliable energy sources, the next generation in reliable power generation, hybrid energy systems, are being developed to stabilize these growing energy needs. The hybrid energy system incorporates multiple inputs and multiple outputs. The vitality and efficiency of these systems resides in the energy storage application. Energy storage is necessary for grid stabilizing and storing the overproduction of energy to meet peak demands of energy at the time of need. With high thermal energy production of the primary nuclear heat generation source, molten salt energy storage is an intriguing option because of its distinct properties. This paper will discuss the different energy storage options with the criteria for efficient energy storage set forth, and will primarily focus on different molten salt energy storage system options through a thermodynamic analysis

P. Sabharwall; M. Green; S.J. Yoon; S.M. Bragg-Sitton; C. Stoots

2014-07-01T23:59:59.000Z

247

DUSCOBS - a depleted-uranium silicate backfill for transport, storage, and disposal of spent nuclear fuel  

SciTech Connect (OSTI)

A Depleted Uranium Silicate COntainer Backfill System (DUSCOBS) is proposed that would use small, isotopically-depleted uranium silicate glass beads as a backfill material inside storage, transport, and repository waste packages containing spent nuclear fuel (SNF). The uranium silicate glass beads would fill all void space inside the package including the coolant channels inside SNF assemblies. Based on preliminary analysis, the following benefits have been identified. DUSCOBS improves repository waste package performance by three mechanisms. First, it reduces the radionuclide releases from SNF when water enters the waste package by creating a local uranium silicate saturated groundwater environment that suppresses (1) the dissolution and/or transformation of uranium dioxide fuel pellets and, hence, (2) the release of radionuclides incorporated into the SNF pellets. Second, the potential for long-term nuclear criticality is reduced by isotopic exchange of enriched uranium in SNF with the depleted uranium (DU) in the glass. Third, the backfill reduces radiation interactions between SNF and the local environment (package and local geology) and thus reduces generation of hydrogen, acids, and other chemicals that degrade the waste package system. In addition, the DUSCOBS improves the integrity of the package by acting as a packing material and ensures criticality control for the package during SNF storage and transport. Finally, DUSCOBS provides a potential method to dispose of significant quantities of excess DU from uranium enrichment plants at potential economic savings. DUSCOBS is a new concept. Consequently, the concept has not been optimized or demonstrated in laboratory experiments.

Forsberg, C.W.; Pope, R.B.; Ashline, R.C.; DeHart, M.D.; Childs, K.W.; Tang, J.S.

1995-11-30T23:59:59.000Z

248

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants  

SciTech Connect (OSTI)

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

Not Available

1980-04-01T23:59:59.000Z

249

Engineering of Deinococcus radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste  

Science Journals Connector (OSTI)

...radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste Published ahead of print on 20 October 2006. Deepti...situ approach to biorecovery of uranium from dilute nuclear waste. Nuclear waste contains a variety of heavy metals, radionuclides...

Deepti Appukuttan; Amara Sambasiva Rao; Shree Kumar Apte

2006-10-20T23:59:59.000Z

250

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry  

Science Journals Connector (OSTI)

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry ... Various aspects of nuclear waste disposal are discussed for their value in providing pedagogical examples. ... Radioactivity, Radiation, and the Chemistry of Nuclear Waste ...

Gregory R. Choppin

1994-01-01T23:59:59.000Z

251

The U.S. Nuclear Waste Technical Review Board Status Update ...  

Office of Environmental Management (EM)

The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update...

252

EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage  

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

42: Return of Isotope Capsules to the Waste Encapsulation and 42: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington EA-0942: Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington SUMMARY This EA evaluates the environmental impacts of the proposal for the return of all leased cesium-137 and strontium-90 leased capsules to the U.S. Department of Energy's Waste Encapsulation and Storage Facility on the Hanford Site, to ensure safe management and storage, pending final disposition. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD May 11, 1994 EA-0942: Finding of No Significant Impact Return of Isotope Capsules to the Waste Encapsulation and Storage Facility, Hanford Site, Richland, Washington

253

A Short History of Hanford Waste Generation, Storage, and Release  

SciTech Connect (OSTI)

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

Gephart, Roy E.

2003-10-01T23:59:59.000Z

254

Management of Low-Level Radioactive Waste from Research, Hospitals and Nuclear Medical Centers in Egypt - 13469  

SciTech Connect (OSTI)

The application of radioisotopes and radiation sources in medical diagnosis and therapy is an important issue. Physicians can use radioisotopes to diagnose and treat diseases. Methods of treatment, conditioning and management of low level radioactive wastes from the use of radiation sources and radioisotopes in hospitals and nuclear medicine application, are described. Solid Radioactive waste with low-level activity after accumulation, minimization, segregation and measurement, are burned or compressed in a compactor according to the international standards. Conditioned drums are transported to the interim storage site at the Egyptian Atomic Energy Authority (EAEA) represented in Hot Labs and Waste Management Center (HLWMC) for storage and monitoring. (authors)

Hasan, M.A.; Selim, Y.T.; Lasheen, Y.F. [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

255

TRU waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the WIPP. Revision 1  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 2 refs., 1 fig.

Not Available

1985-09-01T23:59:59.000Z

256

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD The U.S. Congress And The Secretary of Energy Report.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie, California Dr. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson

257

NUCLEAR ARMS PLANTS: Idaho bars entry of plutonium wastes  

Science Journals Connector (OSTI)

The Department of Energy—already beset by massive cleanup and safety problems at its nuclear arms plants—now must grapple with a further dilemma in dealing with radioactive wastes. ... Gov. Cecil D. Andrus of Idaho closed the state's borders on Sept. 1 to waste shipments from the Rocky Flats nuclear weapons plant near Denver. ...

RICHARD SELTZER

1989-09-11T23:59:59.000Z

258

Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216  

SciTech Connect (OSTI)

Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning Directorate (IDD) is responsible for decommissioning activities. The IDD and the RWTMD work together on decommissioning projects. The IDD has developed plans and has completed decommissioning of the GeoPilot Facility in Baghdad and the Active Metallurgical Testing Laboratory (LAMA) in Al-Tuwaitha. Given this experience, the IDD has initiated work on more dangerous facilities. Plans are being developed to characterize, decontaminate and decommission the Tamuz II Research Reactor. The Tammuz Reactor was destroyed by an Israeli air-strike in 1981 and the Tammuz II Reactor was destroyed during the First Gulf War in 1991. In addition to being responsible for managing the decommissioning wastes, the RWTMD is responsible for more than 950 disused sealed radioactive sources, contaminated debris from the first Gulf War and (approximately 900 tons) of naturally-occurring radioactive materials wastes from oil production in Iraq. The RWTMD has trained staff, rehabilitated the Building 39 Radioactive Waste Storage building, rehabilitated portions of the French-built Radioactive Waste Treatment Station, organized and secured thousands of drums of radioactive waste organized and secured the stores of disused sealed radioactive sources. Currently, the IDD and the RWTMD are finalizing plans for the decommissioning of the Tammuz II Research Reactor. (authors)

Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq)] [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)] [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

2013-07-01T23:59:59.000Z

259

Soil load above Hanford waste storage tanks (2 volumes)  

SciTech Connect (OSTI)

This document is a compilation of work performed as part of the Dome Load Control Project in 1994. Section 2 contains the calculations of the weight of the soil over the tank dome for each of the 75-feet-diameter waste-storage tanks located at the Hanford Site. The chosen soil specific weight and soil depth measured at the apex of the dome crown are the same as those used in the primary analysis that qualified the design. Section 3 provides reference dimensions for each of the tank farm sites. The reference dimensions spatially orient the tanks and provide an outer diameter for each tank. Section 4 summarizes the available soil surface elevation data. It also provides examples of the calculations performed to establish the present soil elevation estimates. The survey data and other data sources from which the elevation data has been obtained are printed separately in Volume 2 of this Supporting Document. Section 5 contains tables that provide an overall summary of the present status of dome loads. Tables summarizing the load state corresponding to the soil depth and soil specific weight for the original qualification analysis, the gravity load requalification for soil depth and soil specific weight greater than the expected actual values, and a best estimate condition of soil depth and specific weight are presented for the Double-Shell Tanks. For the Single-Shell Tanks, only the original qualification analysis is available; thus, the tabulated results are for this case only. Section 6 provides a brief overview of past analysis and testing results that given an indication of the load capacity of the waste storage tanks that corresponds to a condition approaching ultimate failure of the tank. 31 refs.

Pianka, E.W. [Advent Engineering Services, Inc., San Ramon, CA (United States)

1995-01-25T23:59:59.000Z

260

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment...  

Energy Savers [EERE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste...

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

E-Print Network 3.0 - affecting nuclear waste Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: affecting nuclear waste Page: << < 1 2 3 4 5 > >> 1 Nuclear Waste Assessment System for Technical...

262

NUCLEAR WASTE VITRIFICATION EFFICIENCY COLD CAP REACTIONS  

SciTech Connect (OSTI)

The cost and schedule of nuclear waste treatment and immobilization are greatly affected by the rate of glass production. Various factors influence the performance of a waste-glass melter. One of the most significant, and also one of the least understood, is the process of batch melting. Studies are being conducted to gain fundamental understanding of the batch reactions, particularly those that influence the rate of melting, and models are being developed to link batch makeup and melter operation to the melting rate. Batch melting takes place within the cold cap, i.e., a batch layer floating on the surface of molten glass. The conversion of batch to glass consists of various chemical reactions, phase transitions, and diffusion-controlled processes. These include water evaporation (slurry feed contains as high as 60% water), gas evolution, the melting of salts, the formation of borate melt, reactions of borate melt with molten salts and with amorphous oxides (Fe{sub 2}O{sub 3} and Al{sub 2}O{sub 3}), the formation of intermediate crystalline phases, the formation of a continuous glass-forming melt, the growth and collapse of primary foam, and the dissolution of residual solids. To this list we also need to add the formation of secondary foam that originates from molten glass but accumulates on the bottom of the cold cap. This study presents relevant data obtained for a high-level-waste melter feed and introduces a one-dimensional (1D) mathematical model of the cold cap as a step toward an advanced three-dimensional (3D) version for a complete model of the waste glass melter. The 1D model describes the batch-to-glass conversion within the cold cap as it progresses in a vertical direction. With constitutive equations and key parameters based on measured data, and simplified boundary conditions on the cold-cap interfaces with the glass melt and the plenum space of the melter, the model provides sensitivity analysis of the response of the cold cap to the batch makeup and melter conditions. The model demonstrates that batch foaming has a decisive influence on the rate of melting. Understanding the dynamics of the foam layer at the bottom of the cold cap and the heat transfer through it appears crucial for a reliable prediction of the rate of melting as a function of the melter-feed makeup and melter operation parameters. Although the study is focused on a batch for waste vitrification, the authors expect that the outcome will also be relevant for commercial glass melting.

KRUGER AA; HRMA PR; POKORNY R

2011-07-29T23:59:59.000Z

263

Nuclear waste vitrification efficiency: cold cap reactions  

SciTech Connect (OSTI)

The cost and schedule of nuclear waste treatment and immobilization are greatly affected by the rate of glass production. Various factors influence the performance of a waste-glass melter. One of the most significant, and also one of the least understood, is the process of batch melting. Studies are being conducted to gain fundamental understanding of the batch reactions, particularly those that influence the rate of melting, and models are being developed to link batch makeup and melter operation to the melting rate. Batch melting takes place within the cold cap, i.e., a batch layer floating on the surface of molten glass. The conversion of batch to glass consists of various chemical reactions, phase transitions, and diffusion-controlled processes. These include water evaporation (slurry feed contains as high as 60% water), gas evolution, the melting of salts, the formation of borate melt, reactions of borate melt with molten salts and with amorphous oxides (Fe2O3 and Al2O3), the formation of intermediate crystalline phases, the formation of a continuous glass-forming melt, the growth and collapse of primary foam, and the dissolution of residual solids. To this list we also need to add the formation of secondary foam that originates from molten glass but accumulates on the bottom of the cold cap. This study presents relevant data obtained for a high-level-waste melter feed and introduces a one-dimensional (1D) mathematical model of the cold cap as a step toward an advanced three-dimensional (3D) version for a complete model of the waste glass melter. The 1D model describes the batch-to-glass conversion within the cold cap as it progresses in a vertical direction. With constitutive equations and key parameters based on measured data, and simplified boundary conditions on the cold-cap interfaces with the glass melt and the plenum space of the melter, the model provides sensitivity analysis of the response of the cold cap to the batch makeup and melter conditions. The model demonstrates that batch foaming has a decisive influence on the rate of melting. Understanding the dynamics of the foam layer at the bottom of the cold cap and the heat transfer through it appears crucial for a reliable prediction of the rate of melting as a function of the melter-feed makeup and melter operation parameters. Although the study is focused on a batch for waste vitrification, the authors expect that the outcome will also be relevant for commercial glass melting.

Hrma, Pavel R.; Kruger, Albert A.; Pokorny, Richard

2012-12-15T23:59:59.000Z

264

EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

265

Dry storage of spent nuclear fuel in UAE – Economic aspect  

Science Journals Connector (OSTI)

Abstract Cost analysis of dry storage of spent nuclear fuel (SNF) discharged from Barakah nuclear power plants in the UAE was performed using three variables: average fuel discharge rate (FD), discount rate (d), and cooling time in a spent fuel pool (Tcool). The costs of dry storage as an interim spent fuel storage option in the UAE were estimated and compared between the following two scenarios: Scenario 1 is ‘accelerated transfer of spent fuel to dry storage’ that SNF will be transferred to dry storage facilities as soon as spent fuel has been sufficiently cooled down in a pool for the dry storage; Scenario 2 is defined as ‘maximum use of spent fuel pool’ that SNF will be stored in a pool as long as possible till the amount of stored SNF in the pool reaches the capacity of the pools and, then, to be moved to dry storage. A sensitivity analysis on the costs was performed and multiple regression analysis was applied to the resulting net present values (NPVs) for Scenarios 1 and 2 and ?NPV that is difference in the net present values between the two scenarios. The results showed that \\{NPVs\\} and ?NPV could be approximately expressed by single equations with the three variables. Among the three variables, the discount rate had the largest effect on the \\{NPVs\\} of the dry storage costs. However, ?NPV was turned out to be equally sensitive to the discount rate and cooling period. Over the ranges of the variables, the additional cost for accelerated fuel transfer (Scenario 1) ranged from 86.4 to 212.9 million $. Calculated using the maximum difference (212.9 M$) between the two scenarios, the accelerated fuel transfer to dry storage could incur the additional electricity rate 8.0 × 10?5 USD/kWh, which is not considered to be significant, compared to the overall electricity generation cost.

Sara Al Saadi; Yongsun Yi

2015-01-01T23:59:59.000Z

266

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and 8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) 18HIB - RCRAHazardousWasteTreatmentStorageAndDisposalPermitTSD.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Health Solid and Hazardous Waste Branch United States Environmental Protection Agency Regulations & Policies Resource Conversation and Recovery Act (42 U.S.C. 6901, et seq.) 40 CFR 270 Hawaii Administrative Rules Title 11, Chapter 261 Hawaii Administrative Rules Title 11, Chapter 265 Triggers None specified Click "Edit With Form" above to add content

267

Nuclear waste management. Quarterly progress report, April-June 1980  

SciTech Connect (OSTI)

The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

Platt, A.M.; Powell, J.A. (comps.)

1980-09-01T23:59:59.000Z

268

Removing nuclear waste, one shipment at a time  

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

Stories » Stories » Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email "The milestone we're celebrating is one that has been a long-term environmental commitment." Removing nuclear waste, one shipment at a time Elected officials and other dignitaries recently gathered at Los Alamos

269

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

270

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

271

TRU (transuranic) waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the Waste Isolation Pilot Plant: Revision 2  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for acceptance of newly generated CH waste to be shipped to the WIPP are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig.

Not Available

1989-01-01T23:59:59.000Z

272

The Impacts of Dry-Storage Canister Designs on Spent Nuclear...  

Office of Environmental Management (EM)

The Impacts of Dry-Storage Canister Designs on Spent Nuclear Fuel Handling, Storage, Transportation, and Disposal in the U.S. The Impacts of Dry-Storage Canister Designs on Spent...

273

Accelerated chemical aging of crystalline nuclear waste forms  

Science Journals Connector (OSTI)

Nuclear waste disposal is a significant technological issue, and the solution of this problem (or lack thereof) will ultimately determine whether nuclear energy is deemed environmentally friendly, despite significantly lower carbon emissions than fossil fuel energy sources. A critical component of any waste disposal strategy is the selection of the waste form that is tasked with preventing radionuclides from entering the environment. The design of robust nuclear waste forms requires consideration of several criteria, including: radiation tolerance, geological interaction and chemical durability; all of these criteria ensure that the radionuclides do not escape from the waste form. Over the past 30 years, there have been numerous and thorough studies of these criteria on candidate waste forms, including radiation damage and leaching. However, most of these efforts have focused on the performance of the candidate waste form at t = 0, with far less attention paid to the phase stability, and subsequent durability, of candidate waste forms during the course of daughter product formation; that is, the chemical aging of the material. Systematic understanding of phase evolution as a function of chemistry is important for predictions of waste form performance as well as informing waste form design. In this paper, we highlight the research challenges associated with understanding waste form stability when attempting to systematically study the effects of dynamic composition variation due to in situ radionuclide daughter production formation.

C.R. Stanek; B.P. Uberuaga; B.L. Scott; R.K. Feller; N.A. Marks

2012-01-01T23:59:59.000Z

274

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect (OSTI)

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging system—a system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

275

Spallation reactions for nuclear waste transmutation and production of radioactive nuclear beams  

Science Journals Connector (OSTI)

Spallation reactions are considered an optimum neutron source for nuclear waste transmutation in accelerator-driven systems (ADS). ... They are also used to produce intense radioactive nuclear beams in ISOL facil...

J. Benlliure

2005-09-01T23:59:59.000Z

276

Spallation reactions for nuclear waste transmutation and production of radioactive nuclear beams  

Science Journals Connector (OSTI)

Spallation reactions are considered an optimum neutron source for nuclear waste transmutation in accelerator-driven systems (ADS). ... They are also used to produce intense radioactive nuclear beams in ISOL facil...

J. Benlliurea

2005-01-01T23:59:59.000Z

277

Design of the Prototypical Cryomodule for the EUROTRANS Superconducting Linac for Nuclear Waste Transmutation  

E-Print Network [OSTI]

Design of the Prototypical Cryomodule for the EUROTRANS Superconducting Linac for Nuclear Waste Transmutation

Barbanotti, S; Blache, P; Commeaux, C; Duthil, P; Panzeri, N; Pierini, P; Rampnoux, E; Souli, M

2008-01-01T23:59:59.000Z

278

Composite analysis for solid waste storage area 6  

SciTech Connect (OSTI)

The composite analysis (CA) provides an estimate of the potential cumulative impacts to a hypothetical future member of the public from the Solid Waste Storage Area 6 (SWSA 6) disposal operations and all of the other sources of radioactive material in the ground on the ORR that may interact with contamination originating in SWSA 6.The projected annual dose to hypothetical future member of the public from all contributing sources is compared to the primary dose limit of 100 mrem per year and a dose constraint of 30 mrem per year. Consistent with the CA guidance, dose estimates for the first 1000 years after disposal are emphasized for comparison with the primary dose limit and dose constraint.The current land use plan for the ORR is being revised, and may include a reduction in the land currently controlled by DOE on the ORR. The possibility of changes in the land use boundary is considered in the CA as part of the sensitivity and uncertainty analysis of the results, the interpretation of results, and the conclusions.

Lee, D.W.

1997-09-01T23:59:59.000Z

279

The Measurement of Thermal Diffusivity of Simulated Glass Forming Nuclear Waste Melts  

Science Journals Connector (OSTI)

High-level nuclear waste is generated during reprocessing of nuclear reactor fuels. At present, these wastes are stored at various locations in the United States until a final waste form (i.e., glass, SYNROC, ......

James U. Derby; L. David Pye; M. J. Plodinec

1983-01-01T23:59:59.000Z

280

Use of Thermal Energy Storage to Enhance the Recovery and Utilization of Industrial Waste Heat  

E-Print Network [OSTI]

evaluation involving process data from 12 industrial plants to determine if thermal energy storage (TES) systems can be used with commercially available energy management equipment to enhance the recovery and utilization of industrial waste heat. Results...

McChesney, H. R.; Bass, R. W.; Landerman, A. M.; Obee, T. N.; Sgamboti, C. T.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes  

SciTech Connect (OSTI)

Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost.

Delbert E. Day; Chandra S. Ray; Cheol-Woon Kim

2004-12-28T23:59:59.000Z

282

Mortgaging the future: Dumping ethics with nuclear waste  

Science Journals Connector (OSTI)

On August 22, 2005 the U.S. Environmental Protection Agency issued proposed new regulations for radiation releases from the planned permanent U.S. nuclear-waste repository in Yucca Mountain, Nevada. The ... — eve...

Kristin Shrader-Frechette

2005-01-01T23:59:59.000Z

283

Canister design for deep borehole disposal of nuclear waste  

E-Print Network [OSTI]

The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories using currently available and proven oil, gas, and geothermal drilling ...

Hoag, Christopher Ian

2006-01-01T23:59:59.000Z

284

Department of Energy's Nuclear Waste Fund's Fiscal Year 2014...  

Office of Environmental Management (EM)

Nuclear Waste Fund's Fiscal Year 2014 Financial Statement Audit OAS-FS-15-03 November 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections...

285

Nuclear Waste Management in the United States—Starting Over  

Science Journals Connector (OSTI)

...selection of Yucca Mountain prevented the...Unreliable funding source...The Yucca Mountain program will...nuclear waste disposal” (17...Underground—Yucca Mountain and the Nation's...Sweden, SNF disposal site , www...

Rodney C. Ewing; Frank N. von Hippel

2009-07-10T23:59:59.000Z

286

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

Johnson, Terry R. (Wheaton, IL); Ackerman, John P. (Downers Grove, IL); Tomczuk, Zygmunt (Orland Park, IL); Fischer, Donald F. (Glen Ellyn, IL)

1989-01-01T23:59:59.000Z

287

Nuclear Waste: Public Perception and Siting Policy  

Science Journals Connector (OSTI)

The siting of radioactive wastes poses a significant planning challenge to many countries. The public is generally extremely apprehensive about radioactive waste, and this has led to substantial delays in siti...

Joop Van Der Pligt

1989-01-01T23:59:59.000Z

288

Nuclear waste peer review 'needs more transparency'  

Science Journals Connector (OSTI)

... [LONDON] Scientists advising the UK government on radioactive waste disposal have called on the ... disposal have called on the waste management agency Nirex to open up its peer-review arrangements to independent scrutiny if it ...

Ehsan Masood

1997-01-23T23:59:59.000Z

289

Nuclear Waste Disposal: Two Social Criteria  

Science Journals Connector (OSTI)

...1974). 51. Accidents in North American...short-term storage, (ii) long-term...underground caverns mined in salt (7, section...Retrievable surface storage Very low for...low Mined caverns in salt Moderately...removing the salt cake from the storage tanks will...

Gene I. Rochlin

1977-01-07T23:59:59.000Z

290

NEAMS Nuclear Waste Management IPSC : evaluation and selection of tools for the quality environment.  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. These M&S capabilities are to be managed, verified, and validated within the NEAMS Nuclear Waste Management IPSC quality environment. M&S capabilities and the supporting analysis workflow and simulation data management tools will be distributed to end-users from this same quality environment. The same analysis workflow and simulation data management tools that are to be distributed to end-users will be used for verification and validation (V&V) activities within the quality environment. This strategic decision reduces the number of tools to be supported, and increases the quality of tools distributed to end users due to rigorous use by V&V activities. This report documents an evaluation of the needs, options, and tools selected for the NEAMS Nuclear Waste Management IPSC quality environment. The objective of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) program element is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to assess quantitatively the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. This objective will be fulfilled by acquiring and developing M&S capabilities, and establishing a defensible level of confidence in these M&S capabilities. The foundation for assessing the level of confidence is based upon the rigor and results from verification, validation, and uncertainty quantification (V&V and UQ) activities. M&S capabilities are to be managed, verified, and validated within the NEAMS Nuclear Waste Management IPSC quality environment. M&S capabilities and the supporting analysis workflow and simulation data management tools will be distributed to end-users from this same quality environment. The same analysis workflow and simulation data management tools that are to be distributed to end-users will be used for verification and validation (V&V) activities within the quality environment. This strategic decision reduces the number of tools to be supported, and increases the quality of tools distributed to end users due to rigorous use by V&V activities. NEAMS Nuclear Waste Management IPSC V&V and UQ practices and evidence management goals are documented in the V&V Plan. This V&V plan includes a description of the quality environment into which M&S capabilities are imported and V&V and UQ activities are managed. The first phase of implementing the V&V plan is to deploy an initial quality environment through the acquisition and integration of a set of software tools. An evaluation of the needs, options, and tools selected for the quality environment is given in this report.

Bouchard, Julie F.; Stubblefield, William Anthony; Vigil, Dena M.; Edwards, Harold Carter (Org. 1444 : Multiphysics Simulation Technology)

2011-05-01T23:59:59.000Z

291

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)  

SciTech Connect (OSTI)

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Burgard, K.C.

1998-04-09T23:59:59.000Z

292

ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and  

E-Print Network [OSTI]

, The Texas A&M University System. #12;Pumping Pumping from the lagoon should be conducted annually, at least the designed life of sludge storage, frequent agitation and pumping may be necessary. In addition, solidsL ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage

Mukhtar, Saqib

293

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

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

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

294

Alternate airborne release fraction determination for hazardous waste management storage repository hazard categorization at the Lawrence Livermore National Laboratory  

SciTech Connect (OSTI)

Hazardous Waste Management (HWM) facilities are used in the handling and processing of solid and liquid radioactive, hazardous, mixed, and medical wastes generated at Lawrence Livermore National Laboratory (LLNL). Waste may be treated or stored in one of the HWM facility units prior to shipment off site for treatment or disposal. Planned facilities such as the Decontamination and Waste Treatment Facility (DWTF) and the Building 280 Container Storage Unit are expected to handle similar waste streams. A hazard classification was preformed in each facility safety analysis report (SAR) according to the DOE Standard 1027-92 `Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports.` The general methodology practiced by HWM to determine alternate airborne release fractions (ARFs) in those SARs was based upon a beyond evaluation basis earthquake accident scenario characterized by the release of the largest amount of respirable, airborne radioactive material. The alternate ARF was calculated using a three-factor formula consisting of the fraction of failed waste containers, fraction of material released from failed waste containers,and the fraction of material entrained to the environment. Recently, in deliberation with DOE-Oakland representatives, HWM decided to modify this methodology. In place of the current detailed analysis, a more straightforward process was proposed based upon material form, credible accident environments, and empirical data. This paper will discuss the methodology and derivation of ARFs specific to HWM treatment and storage facilities that are alternative to those presented in DOE-STD-1027-92.

Brumburgh, G.P.

1998-05-01T23:59:59.000Z

295

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities: (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1992-12-31T23:59:59.000Z

296

EIS-0212: Safe Interim Storage of Hanford Tank Wastes, Hanford Site, Richland, WA  

Broader source: Energy.gov [DOE]

This environmental impact statement asseses Department of Energy and Washington State Department of Ecology maintanence of safe storage of high-level radioactive wastes currently stored in the older single-shell tanks, the Watchlist Tank 101-SY, and future waste volumes associated with tank farm and other Hanford facility operations, including a need to provide a modern safe, reliable, and regulatory-compliant replacement cross-site transfer capability. The purpose of this action is to prevent uncontrolled releases to the environment by maintaining safe storage of high-level tank wastes.

297

Management of radioactive waste from nuclear power plants: An overview  

SciTech Connect (OSTI)

The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation`s energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse.

Devgun, J.S.

1994-07-01T23:59:59.000Z

298

Nuclear physics information needed for accelerator driven transmutation of nuclear waste  

SciTech Connect (OSTI)

There is renewed interest in using accelerator driven neutron sources to address the problem of high-level long-lived nuclear waste. Several laboratories have developed systems that may have a significant impact on the future use of nuclear power, adding options for dealing with long-lived actinide wastes and fission products, and for power production. This paper describes a new Los Alamos concept using thermal neutrons and examines the nuclear data requirements. 7 refs., 3 figs., 1 tab.

Lisowski, P.W.; Bowman, C.D.; Arthur, E.D.; Young, P.G.

1991-01-01T23:59:59.000Z

299

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

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

Settlement Agreement for Transuranic (TRU) Mixed Settlement Agreement for Transuranic (TRU) Mixed Waste Storage Issues at the Nevada Test Site (NTS) State Nevada Agreement Type Settlement Agreement Legal Driver(s) RCRA Scope Summary Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS Parties DOE; Nevada Department of Environmental Protection Date 6/11/1992 SCOPE * Settle the Finding of Alleged Violation (FOAV) and Order of November 1, 1990, and the FOAV of June 24, 1991, related to the TRU waste storage pad at Area 5 of the NTS. ESTABLISHING MILESTONES * Within 90 days of the effective date of this Agreement, DOE will provide to NDEP documentation of why the current inventory of TRU mixed waste cannot be removed

300

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

J.K. Knudson

2003-10-02T23:59:59.000Z

302

Dry Storage of Research Reactor Spent Nuclear Fuel - 13321  

SciTech Connect (OSTI)

Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage to dry storage requires integration with current facility operations, and selection of equipment that will allow safe operation within the constraints of existing facility conditions. Examples of such constraints that are evaluated and addressed by the dry storage program include limited basin depth, varying fuel lengths up to 4 m, (13 ft), fissile loading limits, canister closure design, post-load drying and closure of the canisters, instrument selection and installation, and movement of the canisters to storage casks. The initial pilot phase restricts the fuels to shorter length fuels that can be loaded to the canister directly underwater; subsequent phases will require use of a shielded transfer system. Removal of the canister from the basin, followed by drying, inerting, closure of the canister, and transfer of the canister to the storage cask are completed with remotely operated equipment and appropriate shielding to reduce personnel radiation exposure. (authors)

Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)] [Moore Nuclear Energy, LLC (United States)

2013-07-01T23:59:59.000Z

303

Energy Department and Catholic University Improve Safety of Nuclear Waste |  

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

Catholic University Improve Safety of Nuclear Catholic University Improve Safety of Nuclear Waste Energy Department and Catholic University Improve Safety of Nuclear Waste January 30, 2013 - 12:51pm Addthis Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. David Sheeley David Sheeley Editor/Writer What does this project do? Hanford treats and immobilizes significant quantities of legacy nuclear waste left from the manufacture of plutonium during World War II and the Cold War. Secretary Steven Chu recently visited Catholic University's Vitreous

304

U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 20042009  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 2004­2009 (Revised March 2004) Statement of the Board The Nuclear Waste Policy Amendments Act of 1987 directed the U-level radioactive waste. The Act also established the U.S. Nuclear Waste Technical Review Board as an indepen dent

305

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

SciTech Connect (OSTI)

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1994-06-01T23:59:59.000Z

306

France digs deep for nuclear waste  

Science Journals Connector (OSTI)

... town of Bure in northeast France, the country is preparing to dispose of its radioactive waste. In a €1-billion (US$1.3 billion) underground laboratory, the French ... a €1-billion (US$1.3 billion) underground laboratory, the French National Radioactive Waste Management Agency (ANDRA) is testing the soundness of the rock and the technologies to ...

Declan Butler

2010-08-10T23:59:59.000Z

307

Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF...  

Open Energy Info (EERE)

Treatment, Storage and Disposal Facilities (TSDF) Guidance Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

308

Solid-state NMR characterisation of transition-metal bearing nuclear waste glasses.  

E-Print Network [OSTI]

??Alkali borosilicate glass is used to immobilise high-level radioactive waste generated from the reprocessing of spent nuclear fuel. However, poorly soluble waste products such as… (more)

Greer, Brandon

2012-01-01T23:59:59.000Z

309

An Investigation into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste Glass Compositions  

E-Print Network [OSTI]

An Investigation into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste of Mo in glasses containing simplified simulated high level nuclear waste (HLW) streams has been originating from the reprocessing of spent nuclear fuel. Experiments using simulated nuclear waste streams

Sheffield, University of

310

ULTRASONIC ARRAY TECHNIQUE FOR THE INSPECTION OF COPPER LINED CANISTERS FOR NUCLEAR WASTE FUEL  

E-Print Network [OSTI]

ULTRASONIC ARRAY TECHNIQUE FOR THE INSPECTION OF COPPER LINED CANISTERS FOR NUCLEAR WASTE FUEL and Waste Management Co.) for encapsulation of nuclear waste. Due to the radiation emitted by the nuclear, and characterization. The applicability of linear array technique for inspection of copper lined canisters for nuclear

311

Basis for Section 3116 Determination for Salt Waste Disposal...  

Office of Environmental Management (EM)

gallons 1 2 (Mgal) of liquid radioactive waste stored in underground waste storage tanks at SRS. Much of this waste resulted from the reprocessing of spent nuclear fuel for...

312

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

Retention in Hanford LAW Glass - Phase 1 Final Report. VSL-rhenium in borosilicate waste glass as determined by X-rayfor NIST SRM 610–617 Glasses Following ISO Guidelines," 35[

McCloy, John S.

2014-01-01T23:59:59.000Z

313

Nuclear Waste Program Faces Political Burial  

Science Journals Connector (OSTI)

...seeking to halt funding for site work in...United States waste disposal Western U.S...choice ofwaste disposal sites. They just...Washington; Yucca Mountain, Nevada; and...list of proposed disposal sites. Titcomb...

ELIOT MARSHALL

1986-08-22T23:59:59.000Z

314

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

315

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

316

Public meetings on nuclear waste management: their function and organization  

SciTech Connect (OSTI)

This report focuses on public meetings as a vehicle for public participation in nuclear waste management. The nature of public meetings is reviewed and the functions served by meetings highlighted. The range of participants and their concerns are addressed, including a review of the participants from past nuclear waste management meetings. A sound understanding of the expected participants allows DOE to tailor elements of the meeting, such as notification, format, and agenda to accommodate the attendees. Finally, the report discusses the organization of public meetings on nuclear waste management in order to enhance the DOE's functions for such meetings. Possible structures are suggested for a variety of elements that are relevant prior to, during and after the public meeting. These suggestions are intended to supplement the DOE Public Participation Manual.

Duvernoy, E.G.; Marcus, A.A.; Overcast, T.; Schilling, A.H.

1981-05-01T23:59:59.000Z

317

Disposal of radioactive waste from nuclear research facilities  

E-Print Network [OSTI]

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Maxeiner, H; Kolbe, E

2003-01-01T23:59:59.000Z

318

Design methodology to develop a conceptual underground facility for the disposal of high-level nuclear waste at Yucca Mountain, Nevada  

SciTech Connect (OSTI)

This paper examines the design methodology employed to develop conceptual underground layouts for a prospective high level nuclear waste repository at Yucca Mountain, Nevada. This study is in conjunction with the Nevada Nuclear Waste Storage Investigations (NNWSI), project studying the disposal of high level waste in densely welded tuff. The fundamental design effort concentraes on the effects of the heat released from the decaying waste forms and the impact of this heat on ventilation, waste emplacement configurations, and rock stability. This effort will perfect the design of the waste emplacement layout including emplacement hole spacing, emplacement drift spacing, and the areal power density (APD) for the installed waste. This paper contains only viewgraphs. 11 figs.

Zerga, D.P.; Badie, A.

1986-12-31T23:59:59.000Z

319

Nuclear Physics Information Needed for Accelerator Driven Transmutation of Nuclear Waste  

Science Journals Connector (OSTI)

There is renewed interest in using accelerator driven neutron sources to address the problem of high level long-lived nuclear waste. Several laboratories have developed systems that may ... a significant impact o...

P. W. Lisowski; C. D. Bowman; E. D. Arthur…

1992-01-01T23:59:59.000Z

320

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

322

Very long term communication intelligence: The case of markers for nuclear waste sites  

Science Journals Connector (OSTI)

Warning markers for long-term nuclear waste storage sites are required to prevent inadvertent human intrusion in the distant future. Two interdisciplinary teams have addressed the issues of physical durability and cognitive intelligibility of such markers for a U.S. government site in New Mexico. Preliminary design criteria have determined which materials are best suited to constitute markers of different sizes and shapes. A variety of linguistic, symbolic, and pictographic approaches to content have been suggested. Additional study and testing of both materials and messages is required. International standardization of marker strategies is extremely desirable.

Jon Lomberg; Stephen C. Hora

1997-01-01T23:59:59.000Z

323

Carbon Sequestration Kinetic and Storage Capacity of Ultramafic Mining Waste  

Science Journals Connector (OSTI)

Mineral carbonation of ultramafic rocks provides an environmentally safe and permanent solution for CO2 sequestration. In order to assess the carbonation potential of ultramafic waste material produced by industrial processing, we designed a laboratory-...

Julie Pronost; Georges Beaudoin; Joniel Tremblay; Faïçal Larachi; Josée Duchesne; Réjean Hébert; Marc Constantin

2011-09-15T23:59:59.000Z

324

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

325

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

SciTech Connect (OSTI)

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.

Sindelar, R.L.

1999-10-21T23:59:59.000Z

326

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

327

Funding cut for US nuclear waste dump  

Science Journals Connector (OSTI)

... is expected to propose spending only the estimated US$40 million needed to let the Nuclear Regulatory Commission (NRC) move forwards in evaluating the licence application for Yucca Mountain. ... three to four years. Tom Kauffman, a spokesman for the industry policy group the Nuclear Energy Institute, says that ...

Amanda Leigh Mascarelli

2009-04-29T23:59:59.000Z

328

Nuclear-waste programme criticized by scientists  

Science Journals Connector (OSTI)

... The report underscores many of the criticisms that have been levelled at the Global Nuclear Energy Partnership since it was unveiled by the White House in 2006, namely that ... . The US Department of Energy (DOE) is seeking $405 million for the Global Nuclear Energy Partnership for the 2008 fiscal year, but key Democrats have vowed to put ...

2007-10-31T23:59:59.000Z

329

Siting America's geologic repository for high-level Nuclear Waste: Implications for environmental Policy  

Science Journals Connector (OSTI)

Siting a geologic repository for isolating highlevel nuclear waste up to 10,000 years is ... before attempted in the United States. The Nuclear Waste Policy Act of 1982 exempted repository siting from ... require...

John Lemons; Charles Malone

330

An Evaluation of Our National Policy to Manage Nuclear Waste from Power Plants  

Science Journals Connector (OSTI)

The current national policy to manage nuclear waste from power plants is to dispose ... of the analysis strongly suggest that our national policy to manage nuclear waste should be changed.

Ralph L. Keeney; Detlof von Winterfeldt

1997-01-01T23:59:59.000Z

331

Development of glass vitrification at SRL as a waste treatment technique for nuclear weapon components  

SciTech Connect (OSTI)

This report discusses the development of vitrification for the waste treatment of nuclear weapons components at the Savannah River Site. Preliminary testing of surrogate nuclear weapon electronic waste shows that glass vitrification is a viable, robust treatment method.

Coleman, J.T.; Bickford, D.F.

1991-01-01T23:59:59.000Z

332

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste...  

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

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Map of the United States of America showing the...

333

Analysis of Influencing Factor on Fracture Energy of Concrete Containers for Nuclear Waste  

Science Journals Connector (OSTI)

The anti-fracture property of concrete container for nuclear waste was investigated to ensure its long-time ... the materials used to make concrete containers for nuclear waste.

Li Yi; Zhao Wen; Qujie

2012-01-01T23:59:59.000Z

334

DESIGN OF THE PROTOTYPICAL CRYOMODULE FOR THE EUROTRANS SUPERCONDUCTING LINAC FOR NUCLEAR WASTE  

E-Print Network [OSTI]

DESIGN OF THE PROTOTYPICAL CRYOMODULE FOR THE EUROTRANS SUPERCONDUCTING LINAC FOR NUCLEAR WASTE of the accelerator workpackage of the EUROTRANS program for the design of a nuclear waste transmutation system

Boyer, Edmond

335

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

336

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

337

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 7 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs. The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard.

FOWLER KD

2007-12-27T23:59:59.000Z

338

METHODOLOGY AND CALCULATIONS FOR THE ASSIGNMENT OF WASTE GROUPS FOR THE LARGE UNDERGROUND WASTE STORAGE TANKS AT THE HANFORD SITE  

SciTech Connect (OSTI)

The Hanford Site contains 177 large underground radioactive waste storage tanks (28 double-shell tanks and 149 single-shell tanks). These tanks are categorized into one of three waste groups (A, B, and C) based on their waste and tank characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement gas release event. Assignments of waste groups to the 177 double-shell tanks and single-shell tanks, as reported in this document, are based on a Monte Carlo analysis of three criteria. The first criterion is the headspace flammable gas concentration following release of retained gas. This criterion determines whether the tank contains sufficient retained gas such that the well-mixed headspace flammable gas concentration would reach 100% of the lower flammability limit if the entire tank's retained gas were released. If the volume of retained gas is not sufficient to reach 100% of the lower flammability limit, then flammable conditions cannot be reached and the tank is classified as a waste group C tank independent of the method the gas is released. The second criterion is the energy ratio and considers whether there is sufficient supernatant on top of the saturated solids such that gas-bearing solids have the potential energy required to break up the material and release gas. Tanks that are not waste group C tanks and that have an energy ratio < 3.0 do not have sufficient potential energy to break up material and release gas and are assigned to waste group B. These tanks are considered to represent a potential induced flammable gas release hazard, but no spontaneous buoyant displacement flammable gas release hazard. Tanks that are not waste group C tanks and have an energy ratio {ge} 3.0, but that pass the third criterion (buoyancy ratio < 1.0, see below) are also assigned to waste group B. Even though the designation as a waste group B (or A) tank identifies the potential for an induced flammable gas release hazard, the hazard only exists for specific operations that can release the retained gas in the tank at a rate and quantity that results in reaching 100% of the lower flammability limit in the tank headspace. The identification and evaluation of tank farm operations that could cause an induced flammable gas release hazard in a waste group B (or A) tank are included in other documents. The third criterion is the buoyancy ratio. This criterion addresses tanks that are not waste group C double-shell tanks and have an energy ratio {ge} 3.0. For these double-shell tanks, the buoyancy ratio considers whether the saturated solids can retain sufficient gas to exceed neutral buoyancy relative to the supernatant layer and therefore have buoyant displacement gas release events. If the buoyancy ratio is {ge} 1.0, that double-shell tank is assigned to waste group A. These tanks are considered to have a potential spontaneous buoyant displacement flammable gas release hazard in addition to a potential induced flammable gas release hazard. This document categorizes each of the large waste storage tanks into one of several categories based on each tank's waste characteristics. These waste group assignments reflect a tank's propensity to retain a significant volume of flammable gases and the potential of the waste to release retained gas by a buoyant displacement event. Revision 8 is the annual update of the calculations of the flammable gas Waste Groups for DSTs and SSTs.

WEBER RA

2009-01-16T23:59:59.000Z

339

GEOHYDROLOGICAL STUDIES FOR NUCLEAR WASTE ISOLATION AT THE HANFORD RESERVATION -- Vol. I: Executive Summary; Vol. II: Final Report  

E-Print Network [OSTI]

NUCLEAR WASTE ISOLATION AT THE HANFORD RESERVATION Volume I:of Washington state." Rockwell Hanford Operations Topicalmodel evaluation at the Hanford nuclear waste facility."

Apps, J.

2010-01-01T23:59:59.000Z

340

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

to develop a proposed repository for the permanent disposal of such waste at Yucca Mountain in Nevada the DOE's methods of scientific and engineering analysis of the Yucca Mountain site. Those meetings This has been an eventful year for the Yucca Mountain program, during which important changes have been

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

) activities related to evaluating the suitability of the Yucca Mountain site and takes a long-term view the DOE's viability assessment (VA) of the Yucca Mountain site, design of the repository and waste package considerable progress in characterizing the Yucca Mountain site. We also appreciate recent efforts by OCRWM

342

Special report: Nuclear waste - under new management  

SciTech Connect (OSTI)

This article is an overview of the effort to provide a long-term disposal site at Yucca Mountain for high-level wastes. Previous financial and technical problems are discussed, as are current funding initiatives. The final decision on the suitability of the site is scheduled for 1998, and a license application is scheduled for 2001.

NONE

1994-12-31T23:59:59.000Z

343

Energy storage for desalination processes powered by renewable energy and waste heat sources  

Science Journals Connector (OSTI)

Abstract Desalination has become imperative as a drinking water source for many parts of the world. Due to the large quantities of thermal energy and high quality electricity requirements for water purification, the desalination industry depends on waste heat resources and renewable energy sources such as solar collectors, photovoltaic arrays, geothermal and wind and tidal energy sources. Considering the mismatch between the source supply and demand and intermittent nature of these energy resources, energy storage is a must for reliable and continuous operation of desalination facilities. Thermal energy storage (TES) requires a suitable medium for storage and circulation while the photovoltaic/wind generated electricity needs to be stored in batteries for later use. Desalination technologies that utilize thermal energy and thus require storage for uninterrupted process operation are multi-stage flash distillation (MSF), multi-effect evaporation (MED), low temperature desalination (LTD) and humidification–dehumidification (HD) and membrane distillation (MD). Energy accumulation, storage and supply are the key components of energy storage concept which improve process performance along with better resource economics, and minimum environmental impact. Similarly, the battery energy storage (BES) is essential to store electrical energy for electrodialysis (ED), reverse osmosis (RO) and mechanical vapor compression (MVC) technologies. This research-review paper provides a critical review on current energy storage options for different desalination processes powered by various renewable energy and waste heat sources with focus on thermal energy storage and battery energy storage systems. Principles of energy storage (thermal and electrical energy) are discussed with details on the design, sizing, and economics for desalination process applications.

Veera Gnaneswar Gude

2014-01-01T23:59:59.000Z

344

STABILIZING GLASS BONDED WASTE FORMS CONTAINING FISSION PRODUCTS SEPARATED FROM SPENT NUCLEAR FUEL  

SciTech Connect (OSTI)

A model has been developed to represent the stresses developed when a molten, glass-bonded brittle cylinder (used to store nuclear material) is cooled from high temperature to working temperature. Large diameter solid cylinders are formed by heating glass or glass-bonded mixtures (mixed with nuclear waste) to high temperature (915°C). These cylinders must be cooled as the final step in preparing them for storage. Fast cooling time is desirable for production; however, if cooling is too fast, the cylinder can crack into many pieces. To demonstrate the capability of the model, cooling rate cracking data were obtained on small diameter (7.8 cm diameter) glass-only cylinders. The model and experimental data were combined to determine the critical cooling rate which separates the non-cracking stable glass region from the cracked, non-stable glass regime. Although the data have been obtained so far only on small glass-only cylinders, the data and model were used to extrapolate the critical-cooling rates for large diameter ceramic waste form (CWF) cylinders. The extrapolation estimates long term cooling requirements. While a 52-cm diameter cylinder (EBR-II-waste size) can be cooled to 100°C in 70 hours without cracking, a 181.5-cm diameter cylinder (LWR waste size) requires 35 days to cool to 100°C. These cooling times are long enough that verification of these estimates are required so additional experiments are planned on both glass only and CWF material.

Kenneth J. Bateman; Charles W. Solbrig

2008-07-01T23:59:59.000Z

345

Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

2013-07-01T23:59:59.000Z

346

Economics and policies in nuclear waste disposal  

Science Journals Connector (OSTI)

The controversy over the comparative merits of nuclear energy and fossil fuels has been raging ... important economic, environmental and ethical dimensions puzzling policy-makers as well as the general public...

E. Kula

1994-01-01T23:59:59.000Z

347

Senate poised to act on nuclear waste bills  

Science Journals Connector (OSTI)

On Nov. 30 the Senate committees on Energy & Natural Resources and Environment & Public Works issued a joint report on legislation dealing with the long-term disposal of nuclear waste. But, although the report carries the names of both committees, there ...

1981-12-14T23:59:59.000Z

348

Nuclear Waste Technical Review Board Strategic Plan FY 20082013  

E-Print Network [OSTI]

on compliance activities, in conduct- ing its evaluation, the Board will encourage DOE through its science its review of DOE activities into three technical areas: preclosure operations, including surface-facility design and operations and the transport of spent nuclear fuel and high-level radioactive waste from

349

Backfill composition for secondary barriers in nuclear waste repositories  

DOE Patents [OSTI]

A backfill composition for sorbing and retaining hazardous elements of nuclear wastes comprises 50 to 70% by weight of quartz, 10 to 30% by weight of montmorillonite, 1 to 10% by weight of phosphate mineral, 1 to 10% by weight of ferrous mineral, 1 to 10% by weight of sulfate mineral and 1 to 10% by weight of attapulgite.

Beall, G.W.; Allard, B.M.

1980-05-30T23:59:59.000Z

350

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing Plant  

E-Print Network [OSTI]

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing: There is concern about the health of populations living close to nuclear waste reprocessing plants. We conducted a comparative study on reproductive life events in the general population living near the nuclear waste

Paris-Sud XI, Université de

351

U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan Statement of the Chairman The U.S. Nuclear Waste Technical Review Board was established of Energy Mission The Board's mission, established in the Nuclear Waste Policy Amendments Act (NWPAA

352

Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be  

E-Print Network [OSTI]

Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be sited geological nuclear waste repository. There a suspicion of predetermination because the only district that has. National and international guidance on how best to select potential sites for deep geological nuclear waste

353

Communication Between the U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Appendix F Appendix F Communication Between the U.S. Nuclear Waste Technical Review Board on Energy and Air Quality on March 25, 2004 143 #12;#12;Appendix F UNITED STATES NUCLEAR WASTE TECHNICAL much for your written questions related to my testimony on behalf of the Nuclear Waste Technical Review

354

A ThreeDimensional Finite Element Simulation for Transport of Nuclear Waste Contamination in Porous Media  

E-Print Network [OSTI]

A Three­Dimensional Finite Element Simulation for Transport of Nuclear Waste Contamination of South Carolina, Columbia, South Carolina ABSTRACT: Model equations for transport of nuclear­waste based up on the inherent physics. A three­dimensional finite element method for nuclear waste

Ewing, Richard E.

355

CORROSION OF NUCLEAR WASTE GLASSES IN NON-SATURATED CONDITIONS: TIME-TEMPERATURE BEHAVIOUR  

E-Print Network [OSTI]

CORROSION OF NUCLEAR WASTE GLASSES IN NON-SATURATED CONDITIONS: TIME-TEMPERATURE BEHAVIOUR Michael borosilicate glasses intended for nuclear waste immobilisation based on experimental data obtained during long the corrosion of nuclear waste glasses in terms of time-temperature (t, T) parameters. A linear (non

Sheffield, University of

356

Numerical Zoom for Multiscale Problems with an Application to Nuclear Waste Disposal  

E-Print Network [OSTI]

Numerical Zoom for Multiscale Problems with an Application to Nuclear Waste Disposal Jean of a nuclear waste repository site. Key words: Multiscale, Finite Element, Domain Decomposition, Chimera, Numerical Zoom, Nuclear Waste. PACS: 02.30.Jr, 47.11.Fg, 28.41.Kw, 47.55.P- 1 Introduction The present paper

357

Mass Tracking System Software [Nuclear Waste Management using  

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

Mass Tracking System Mass Tracking System Software Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Mass Tracking System Software Bookmark and Share The NE Division has developed a computer-based Mass Tracking (MTG) system, which is used at the Idaho National Laboratory Fuel Conditioning Facility (FCF) to maintain a real-time accounting of the inventory of containers and

358

Thermoeconomic optimization of sensible heat thermal storage for cogenerated waste-to-energy recovery  

SciTech Connect (OSTI)

This paper investigates the feasibility of employing thermal storage for cogenerated waste-to-energy recovery such as using mass-burning water-wall incinerators and topping steam turbines. Sensible thermal storage is considered in rectangular cross-sectioned channels through which is passed unused process steam at 1,307 kPa/250 C (175 psig/482 F) during the storage period and feedwater at 1,307 kPa/102 C (175 psig/216 F) during the recovery period. In determining the optimum storage configuration, it is found that the economic feasibility is a function of mass and specific heat of the material and surface area of the channel as well as cost of material and fabrication. Economic considerations included typical cash flows of capital charges, energy revenues, operation and maintenance, and income taxes. Cast concrete is determined to be a potentially attractive storage medium.

Abdul-Razzak, H.A. [Texas A and M Univ., Kingsville, TX (United States). Dept. of Mechanical and Industrial Engineering; Porter, R.W. [Illinois Inst. of Tech., chicago, IL (United States). Dept. of Mechanical and Aerospace Engineering

1995-10-01T23:59:59.000Z

359

Radioactive Waste Management in Non-Nuclear Countries - 13070  

SciTech Connect (OSTI)

This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services, comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)

Kubelka, Dragan; Trifunovic, Dejan [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)] [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)

2013-07-01T23:59:59.000Z

360

Evaluation of the transport and resuspension of a simulated nuclear waste slurry: Nuclear Waste Treatment Program  

SciTech Connect (OSTI)

The Department of Chemical Engineering at the University of Idaho conducted research on the transport and resuspension of a simulated high-level nuclear waste slurry. In the United States, the reference process for treating both defense and civilian HLLW is vitrification using the liquid-fed ceramic melter process. The non-Newtonian behavior of the slurry complicates the evaluation of the transport and resuspension characteristics of the slurry. The resuspension of a simulated (nonradioactive) melter feed slurry was evaluated using a slurry designated as WV-205. The simulated slurry was developed for the West Valley Demonstration Project and was used during a pilot-scale ceramic melter (PSCM) experiment conducted at PNL in July 1985 (PSCM-21). This study involved determining the transport characteristics of a fully suspended slurry and the resuspension characteristics of settled solids in a pilot-scale pipe loop. The goal was to predict the transport and resuspension of a full-scale system based on rheological data for a specific slurry. The rheological behavior of the slurry was evaluated using a concentric cylinder rotational viscometer, a capillary tube viscometer, and the pilot-scale pipe loop. The results obtained from the three approaches were compared. 40 refs., 74 figs., 15 tabs.

Carleson, T.E.; Drown, D.C.; Hart, R.E.; Peterson, M.E.

1987-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

2727-S Nonradioactive Dangerous Waste Storage Facility Closure Plan. Revision 3A  

SciTech Connect (OSTI)

This report contains Sections 4 and 5 of the Nonradioactive Dangerous Waste Storage Facility Closure Plan, which summarizes closure activities for the site. Sampling procedures for the building, concrete and soils are given. Plans for building disposal, equipment decontamination, site restoration, and providing cost estimates are outlined. Section 5 discusses plans to develop a health and safety contingency plan before initiation of sampling activities.

Not Available

1992-10-01T23:59:59.000Z

362

Thermal Energy Storage/Waste Heat Recovery Applications in the Cement Industry  

E-Print Network [OSTI]

, and the Portland Cement Association have studied the potential benefits of using waste heat recovery methods and thermal energy storage systems in the cement manufacturing process. This work was performed under DOE Contract No. EC-77-C-01-50S4. The study has been...

Beshore, D. G.; Jaeger, F. A.; Gartner, E. M.

1979-01-01T23:59:59.000Z

363

Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112  

SciTech Connect (OSTI)

This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities.

Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

1994-11-01T23:59:59.000Z

364

High-level waste canister storage final design, installation, and testing. Topical report  

SciTech Connect (OSTI)

This report is a description of the West Valley Demonstration Project`s radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project`s vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access.

Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

1998-04-01T23:59:59.000Z

365

A visual assessment of the concrete vaults which surround underground waste storage tanks  

SciTech Connect (OSTI)

Radioactive waste produced at the Savannah River Site (SRS) is stored in underground tanks. There are four different waste tank designs. For each waste tank design the outermost containment shield between the waste and the soil is a concrete vault surrounding the carbon steel liner(s). Should the primary and/or secondary liner be breached, the concrete vault would slow transport of the waste so that contamination of the soil is minimized. The type 3 waste tanks have a stated design life of 40--60 years. With the uncertainty of the schedule for transfer of the waste to the Defense Waste Processing Facility, it is conceivable that the tanks will be required to function past their design life. The Department of Energy formed a Waste Tank Structural Integrity Panel to investigate the potential for aging and degradation of underground radioactive waste storage tanks employed in the weapons complex. The panel is focusing on how each site in the complex: (1) inspects the waste tanks for degradation, (2) understands the potential degradation mechanisms which may occur at their sites, and (3) mitigates the known potential degradation mechanisms. In addition to the carbon steel liners, the degradation of the concrete vault has also been addressed by the panel. High Level Waste Engineering (HLWE) at SRS has formed a task team to identify key issues that determine and/or effect the condition of the concrete. In June 1993, slides were reviewed which showed the inside of the concrete vault in Type 1, 2, and 4 tanks. The authors subsequently visited the tank farm and assessed the visible portions of the outer concrete vault. Later a team of engineers knowledgeable in concrete degradation performed a walk-down. Photographs showing the concrete condition were taken at this time. This report summarizes the findings of these walk-downs and reinforces previous recommendations.

Wiersma, B.J.; Shurrab, M.S.

1993-12-01T23:59:59.000Z

366

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOE Patents [OSTI]

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16T23:59:59.000Z

367

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

368

Behavior of Spent Nuclear Fuel in Water Pool Storage  

Office of Scientific and Technical Information (OSTI)

Behavior of Spent Nuclear Behavior of Spent Nuclear Fuel in Water Pool Storage A. 0; Johnson, jr. , I ..: . Prepared Cor the Energy Research and Development Administration under Contract EY-76-C-06-1830 ---- Pat t i ~ < N ~ ~ r ~ t b w t ~ - ! I , ~ I ~ ~ ~ I . I I ~ ) ~ I I ~ ~ N O T I C E T€& - was prepad pnpn4. m w n t of w k spon-d by the Unitd S t . & ) C a u n m ~ (*WU ij*. M t e d $tam w the Wqy R e s e w & a d Ohrsropmcnt ~dmhirmlion, nor m y d thair ewhew,,nq Pny @fw a n t r ~ ~ t 0 ~ 1 , s ~ k m r i t r i l t t q r , ~ , m r tWf ernpfQw, r(tLltm any wartany, s x p r e s or kWld,= w w aAql -9 . o r r w p a m l ~ ~ t y for e~ o r uodruincvr of any infomutim, 9 F p d + d - , or repratants that -would nat 1 d - e privately owned rfghas. ,i PAQFIC NORTHWEST UBORATORY operated b ;"' SArnLLE ' fw the E M R m RESEARCH AND DEVELOPMENT ADMINISTRAT1QN Wk.Cwfraa rv-76c-ts-is38

369

CSER 94-004: Criticality safety of double-shell waste storage tanks  

SciTech Connect (OSTI)

This criticality safety evaluation covers double-shell waste storage tanks (DSTs), double-contained receiver tanks (DCRTs), vault tanks, and the 242-A Evaporator located in the High Level Waste (HLW) Tank Farms on the Hanford Site. Limits and controls are specified and the basis for ensuring criticality safety is discussed. A minimum limit of 1,000 is placed upon the solids/plutonium mass ratio in incoming waste. The average solids/Pu mass ratio over all waste in tank farms is estimated to be about 74,500, about 150 times larger than required to assure subcriticality in homogeneous waste. PFP waste in Tank-102-SY has an estimated solids/Pu mass ratio of 10,000. Subcriticality is assured whenever the plutonium concentration is less than 2.6 g. The median reported plutonium concentration for 200 samples of waste solids is about 0.01 g (0.038 g/gal). A surveillance program is proposed to increase the knowledge of the waste and provide added assurance of the high degree of subcriticality.

Rogers, C.A.

1994-09-22T23:59:59.000Z

370

The National Nuclear Laboratory's Approach to Processing Mixed Wastes and Residues - 13080  

SciTech Connect (OSTI)

The National Nuclear Laboratory (NNL) treats a wide variety of materials produced as by-products of the nuclear fuel cycle, mostly from uranium purification and fuel manufacture but also including materials from uranium enrichment and from the decommissioning of obsolete plants. In the context of this paper, treatment is defined as recovery of uranium or other activity from residues, the recycle of uranium to the fuel cycle or preparation for long term storage and the final disposal or discharge to the environment of the remainder of the material. NNL's systematic but flexible approach to residue assessment and treatment is described in this paper. The approach typically comprises up to five main phases. The benefits of a systematic approach to waste and residue assessments and processing are described in this paper with examples used to illustrate each phase of work. Benefits include early identification of processing routes or processing issues and the avoidance of investment in inappropriate and costly plant or processes. (authors)

Greenwood, Howard; Docrat, Tahera; Allinson, Sarah J.; Coppersthwaite, Duncan P.; Sultan, Ruqayyah; May, Sarah [National Nuclear Laboratory, Springfields, Preston, UK, PR4 0XJ (United Kingdom)] [National Nuclear Laboratory, Springfields, Preston, UK, PR4 0XJ (United Kingdom)

2013-07-01T23:59:59.000Z

371

Shipping Radioactive Waste by Rail from Brookhaven National Laboratory...  

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

Documents & Publications West Valley Demonstration Project Low-Level Waste Shipment Nuclear Fuel Storage and Transportation Planning Project Overview Prairie Island Indian...

372

Summary: Workshop Recommendations—Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management

A. M. Friedman; D. J. Lam; M. G. Seitz

373

Modification and expansion of X-7725A Waste Accountability Facility for storage of polychlorinated biphenyl wastes at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio  

SciTech Connect (OSTI)

The US Department of Energy (DOE) must manage wastes containing polychlorinated biphenyls (PCBs) in accordance with Toxic Substances Control Act (TSCA) requirements and as prescribed in a Federal Facilities Compliance Agreement (FFCA) between DOE and the U.S. Environmental Protection Agency (EPA). PCB-containing wastes are currently stored in the PORTS process buildings where they are generated. DOE proposes to modify and expand the Waste Accountability facility (X-7725A) at the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio, to provide a central storage location for these wastes. The proposed action is needed to eliminate the fire and safety hazards presented by the wastes. In this EA, DOE considers four alternatives: (1) no action, which requires storing wastes in limited storage areas in existing facilities; (2) modifying and expanding the X-7725A waste accountability facility; (3) constructing a new PCB waste storage building; and (4) shipping PCB wastes to the K-25 TSCA incinerator. If no action is taken, PCB-contaminated would continue to be stored in Bldgs X-326, X-330, and X-333. As TSCA cleanup activities continue, the quantity of stored waste would increase, which would subsequently cause congestion in the three process buildings and increase fire and safety hazards. The preferred alternative is to modify and expand Bldg. X-7725A to store wastes generated by TSCA compliance activities. Construction, which could begin as early as April 1996, would last approximately five to seven months, with a total peak work force of 70.

NONE

1995-11-01T23:59:59.000Z

374

The High-Level Radioactive Waste Act (Manitoba, Canada)  

Broader source: Energy.gov [DOE]

Manitoba bars the storage of high-level radioactive wastes from spent nuclear fuel, not intended for research purposes, that was produced at a nuclear facility or in a nuclear reactor outside the...

375

Innovative systems for sustainable nuclear energy generation and waste management  

Science Journals Connector (OSTI)

The limited amount of fossil resources, the impact of green-house gas emissions on the world climate, the rising demand of primary energy projected to 2050, lead to a potentially critical situation for the world energy supply. The need for alternative (to fossil energies) massive energy production is evaluated to 10 Gtoe. The potential of Nuclear Energy generation at the level of 5 Gtoe is examined. Such a sustainable production can only be met by a breeder reactor fleet for which a deployment scenario is described with the associated constraints. Waste management is discussed in connection with different nuclear energy development scenarios according to the point in time when breeder reactors are started. At the world level, it appears that the optimal handling of today's wastes rests on an early decision to develop tomorrow's breeder reactors.

Jm Loiseaux; S David

2006-01-01T23:59:59.000Z

376

Alcohol-free alkoxide process for containing nuclear waste  

DOE Patents [OSTI]

Disclosed is a method of containing nuclear waste. A composition is first prepared of about 25 to about 80%, calculated as SiO.sub.2, of a partially hydrolyzed silicon compound, up to about 30%, calculated as metal oxide, of a partially hydrolyzed aluminum or calcium compound, about 5 to about 20%, calculated as metal oxide, of a partially hydrolyzed boron or calcium compound, about 3 to about 25%, calculated as metal oxide, of a partially hydrolyzed sodium, potassium or lithium compound, an alcohol in a weight ratio to hydrolyzed alkoxide of about 1.5 to about 3% and sufficient water to remove at least 99% of the alcohol as an azeotrope. The azeotrope is boiled off and up to about 40%, based on solids in the product, of the nuclear waste, is mixed into the composition. The mixture is evaporated to about 25 to about 45% solids and is melted and cooled.

Pope, James M. (Monroeville, PA); Lahoda, Edward J. (Edgewood, PA)

1984-01-01T23:59:59.000Z

377

USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?  

SciTech Connect (OSTI)

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable (“assets”) to worthless (“wastes”). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or – in the case of high level waste – awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site’s (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as “waste” include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

Magoulas, V.

2013-06-03T23:59:59.000Z

378

Transmutation of nuclear waste in accelerator-driven systems  

E-Print Network [OSTI]

Today more than ever energy is not only a cornerstone of human development, but also a key to the environmental sustainability of economic activity. In this context, the role of nuclear power may be emphasized in the years to come. Nevertheless, the problems of nuclear waste, safety and proliferation still remain to be solved. It is believed that the use of accelerator-driven systems (ADSs) for nuclear waste transmutation and energy production would address these problems in a simple, clean and economically viable, and therefore sustainable, manner. This thesis covers the major nuclear physics aspects of ADSs, in particular the spallation process and the core neutronics specific to this type of systems. The need for accurate nuclear data is described, together with a detailed analysis of the specific isotopes and energy ranges in which this data needs to be improved and the impact of their uncertainty. Preliminary experimental results for some of these isotopes, produced by the Neutron Time-of-Flight (n_TOF) ...

Herrera-Martínez, A

2004-01-01T23:59:59.000Z

379

Simulation of Self-Irradiation of High-Sodium Content Nuclear Waste Glasses  

SciTech Connect (OSTI)

Alkali-borosilicate glasses are widely used in nuclear industry as a matrix for immobilisation of hazardous radioactive wastes. Durability or corrosion resistance of these glasses is one of key parameters in waste storage and disposal safety. It is influenced by many factors such as composition of glass and surrounding media, temperature, time and so on. As these glasses contain radioactive elements most of their properties including corrosion resistance are also impacted by self-irradiation. The effect of external gamma-irradiation on the short-term (up to 27 days) dissolution of waste borosilicate glasses at moderate temperatures (30 deg. to 60 deg. C) was studied. The glasses studied were Magnox Waste glass used for immobilisation of HLW in UK, and K-26 glass used in Russia for ILW immobilisation. Glass samples were irradiated under {gamma}-source (Co-60) up to doses 1 and 11 MGy. Normalised rates of elemental release and activation energy of release were measured for Na, Li, Ca, Mg, B, Si and Mo before and after irradiation. Irradiation up to 1 MGy results in increase of leaching rate of almost all elements from both MW and K-26 with the exception of Na release from MW glass. Further irradiation up to a dose of 11 MGy leads to the decrease of elemental release rates to nearly initial value. Another effect of irradiation is increase of activation energies of elemental release. (authors)

Pankov, Alexey S.; Ojovan, Michael I. [Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Sir Robert Hadfield Building, Mappin Street, Sheffield, S1 3JD (United Kingdom); Batyukhnova, Olga G. [International Education Training Centre, SUE SIA 'Radon', The 7-th Rostovsky Lane 2/14, Moscow, 119121 (Russian Federation); Lee, William E. [Department of Materials, Imperial College London, South Kensington Campus, Exhibition Road, London, SW7 2AZ (United Kingdom)

2007-07-01T23:59:59.000Z

380

Large Scale Computing and Storage Requirements for Nuclear Physics Research  

E-Print Network [OSTI]

a strong program of research in theoretical nuclear physics,Research     12.1 Overview   The Nuclear Physics programan extensive program of experimental research in nuclear

Gerber, Richard A.

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Potential applications of nanostructured materials in nuclear waste management.  

SciTech Connect (OSTI)

This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

2003-09-01T23:59:59.000Z

382

Method of determining a content of a nuclear waste container  

DOE Patents [OSTI]

A method and apparatus are provided for identifying contents of a nuclear waste container. The method includes the steps of forming an image of the contents of the container using digital radiography, visually comparing contents of the image with expected contents of the container and performing computer tomography on the container when the visual inspection reveals an inconsistency between the contents of the image and the expected contents of the container.

Bernardi, Richard T. (Prospect Heights, IL); Entwistle, David (Buffalo Grove, IL)

2003-04-22T23:59:59.000Z

383

Accelerator-driven transmutation of plutonium and nuclear waste  

SciTech Connect (OSTI)

The ultimate disposition of spent reactor fuel and processed high-level nuclear waste (HLW) has been a subject of much concern and little progress since the dawn of the nuclear era. In the United States today, the spent fuel from more than 110 commercial light water reactors continues to be stored onsite while highly toxic liquid HLW continues to be stored in tanks at several U.S. Department of Energy sites. The management policy that has been followed in the United States for the past 12 yr is defined by the Nuclear Waste Policy Act (NWPA) of 1982 and its subsequent amendment of 1987. The NWPA requires the disposal of spent fuel assemblies in geologic waste repositories, the first of which will presumably be located at Yucca Mountain, Nevada. The pace of the process for implementing the Yucca Mountain repository discussed in a recent General Accounting Office (GAO) assessment, remains frustratingly slow. By GAO estimation, an operational permanent waste repository at Yucca Mountain could be delayed beyond the 2020 time frame. The approach to formulating an acceptable HLW disposal strategy has always involved serious consideration of nonproliferation issues. Most recently, the nuclear weapon build-down following the Cold War has stimulated the need for the United States and Russia to dispose of surplus plutonium. Consideration of this has motivated (a) a recognition that all plutonium is a proliferation hazard and (b) a renewed debate on the best approach to dispose of plutonium in general. From an international perspective, there is little agreement on the best strategy for the ultimate disposition of HLW and plutonium. This paper discusses the concept of transmutation of plutonium.

Berwald, D.H. [Grumman Aerospace Corp., Bethpage, NY (United States)

1995-12-31T23:59:59.000Z

384

Evaluation of existing Hanford buildings for the storage of solid wastes  

SciTech Connect (OSTI)

Existing storage space at the Hanford Site for solid low-level mixed waste (LLMW) will be filled up by 1997. Westinghouse Hanford Company (WHC) has initiated the project funding cycle for additional storage space to assure that new facilities are available when needed. In the course of considering the funding request, the US Department of Energy (DOE) has asked WHC to identify and review any existing Hanford Site facilities that could be modified and used as an alternative to constructing the proposed W-112 Project. This report documents the results of that review. In summary, no buildings exist at the Hanford Site that can be utilized for storage of solid LLMW on a cost-effective basis when compared to new construction. The nearest approach to an economically sensible conversion would involve upgrade of 100,000 ft{sup 2} of space in the 2101-M Building in the 200 East Area. Here, modified storage space is estimated to cost about $106 per ft{sup 2} while new construction will cost about $50 per ft{sup 2}. Construction costs for the waste storage portion of the W-112 Project are comparable with W-016 Project actual costs, with escalation considered. Details of the cost evaluation for this building and for other selected candidate facilities are presented in this report. All comparisons presented address the potential decontamination and decommissioning (D&D) cost avoidances realized by using existing facilities.

Carlson, M.C.; Hodgson, R.D.; Sabin, J.C.

1993-05-01T23:59:59.000Z

385

GEOHYDROLOGICAL STUDIES FOR NUCLEAR WASTE ISOLATION AT THE HANFORD RESERVATION -- Vol. I: Executive Summary; Vol. II: Final Report  

E-Print Network [OSTI]

long-term feasibility study conducted by Rockwell's Basalt Waste Isolation Program for the National Waste Terminal Storagelong-term feasibility study conducted by Rockwell's Basalt Waste Isolation Program for the National Was~e Terminal Storage

Apps, J.

2010-01-01T23:59:59.000Z

386

High-level waste storage tank farms/242-A evaporator standards/requirements identification document (S/RID), Vol. 7  

SciTech Connect (OSTI)

This Requirements Identification Document (RID) describes an Occupational Health and Safety Program as defined through the Relevant DOE Orders, regulations, industry codes/standards, industry guidance documents and, as appropriate, good industry practice. The definition of an Occupational Health and Safety Program as specified by this document is intended to address Defense Nuclear Facilities Safety Board Recommendations 90-2 and 91-1, which call for the strengthening of DOE complex activities through the identification and application of relevant standards which supplement or exceed requirements mandated by DOE Orders. This RID applies to the activities, personnel, structures, systems, components, and programs involved in maintaining the facility and executing the mission of the High-Level Waste Storage Tank Farms.

Not Available

1994-04-01T23:59:59.000Z

387

Nuclear Waste Technical Review Board Correspondence with the Department of Energy  

E-Print Network [OSTI]

85 Appendix E Nuclear Waste Technical Review Board Correspondence with the Department of Energy #12;#12;Appendix E 87 Nuclear Waste Technical Review Board Correspondence with the Department of Energy I n of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The letters typically provide

388

CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

2003-02-27T23:59:59.000Z

389

HEAT TRANSFER ANALYSIS FOR NUCLEAR WASTE SOLIDIFICATION CONTAINER  

SciTech Connect (OSTI)

The Nuclear Nonproliferation Programs Design Authority is in the design stage of the Waste Solidification Building (WSB) for the treatment and solidification of the radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility (PDCF) and Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The waste streams will be mixed with a cementitious dry mix in a 55-gallon waste container. Savannah River National Laboratory (SRNL) has been performing the testing and evaluations to support technical decisions for the WSB. Engineering Modeling & Simulation Group was requested to evaluate the thermal performance of the 55-gallon drum containing hydration heat source associated with the current baseline cement waste form. A transient axi-symmetric heat transfer model for the drum partially filled with waste form cement has been developed and heat transfer calculations performed for the baseline design configurations. For this case, 65 percent of the drum volume was assumed to be filled with the waste form, which has transient hydration heat source, as one of the baseline conditions. A series of modeling calculations has been performed using a computational heat transfer approach. The baseline modeling results show that the time to reach the maximum temperature of the 65 percent filled drum is about 32 hours when a 43 C initial cement temperature is assumed to be cooled by natural convection with 27 C external air. In addition, the results computed by the present model were compared with analytical solutions. The modeling results will be benchmarked against the prototypic test results. The verified model will be used for the evaluation of the thermal performance for the WSB drum. Detailed results and the cases considered in the calculations will be discussed here.

Lee, S.

2009-06-01T23:59:59.000Z

390

Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident  

Science Journals Connector (OSTI)

......people living in long-term-contaminated...Radioactive waste management in...longer-term storage and appropriate...appropriate for the long-term assessment...long-lived radioactive wastes in planned exposure...People Living in Long-term Contaminated...from Radioactive Waste Management in......

Daisuke Sugiyama; Takatoshi Hattori

2013-01-01T23:59:59.000Z

391

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron  

E-Print Network [OSTI]

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron John and reduction of pertechnetate anions (TcO4 -) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams

392

A ground-coupled storage heat pump system with waste heat recovery  

SciTech Connect (OSTI)

This paper reports on an experimental single-family residence that was constructed to demonstrate integration of waste heat recovery and seasonal energy storage using both a ventilating and a ground-coupled heat pump. Called the Idaho energy Conservation Technology House, it combines superinsulated home construction with a ventilating hot water heater and a ground coupled water-to-water heat pump system. The ground heat exchangers are designed to economically promote seasonal and waste heat storage. Construction of the house was completed in the spring of 1989. Located in Moscow, Idaho, the house is occupied by a family of three. The 3,500 ft{sup 2} (325 m{sup 2}) two-story house combines several unique sub-systems that all interact to minimize energy consumption for space heating and cooling, and domestic hot water.

Drown, D.C.; Braven, K.R.D. (Univ. of Idaho, ID (US)); Kast, T.P. (Thermal Dynamic Towers, Boulder, CO (US))

1992-02-01T23:59:59.000Z

393

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1  

SciTech Connect (OSTI)

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14T23:59:59.000Z

394

Safety of interim storage solutions of used nuclear fuel during extended term  

SciTech Connect (OSTI)

In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

2013-07-01T23:59:59.000Z

395

Long-term changes in nitrogen loads of a stream in the vicinity of an earthen waste storage pond  

Science Journals Connector (OSTI)

It is not sufficiently known for how long earthen waste storage ponds that are no more in use continue to affect surface water quality. In 2006, we carried out an investigation on the water quality and hydrolo...

T. Kato; H. Kuroda; H. Nakasone

2008-09-01T23:59:59.000Z

396

Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2  

SciTech Connect (OSTI)

This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P. [and others

1997-09-01T23:59:59.000Z

397

Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel  

Science Journals Connector (OSTI)

Stainless steel-zirconium waste-form alloys have been developed for the disposal of metallic wastes recovered from spent nuclear fuel using the electrometallurgical process developed by Argonne National Laborator...

S. M. McDeavitt; D. P. Abraham; J. Y. Park; D. D. Keiser

1997-07-01T23:59:59.000Z

398

Idaho Site Taps Old World Process to Treat Nuclear Waste | Department of  

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

Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste September 9, 2013 - 12:00pm Addthis The Idaho site's sodium distillation system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. The top of a sodium distillation vessel, where waste enters the system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. IDAHO FALLS, Idaho - The EM program at the Idaho site is using an age-old process to treat transuranic (TRU) waste left over from nuclear reactor experiments. Developed in the first century and perfected by moonshiners in the 19th century, distillation will be used at the Idaho Nuclear Technology and

399

Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).  

SciTech Connect (OSTI)

This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

2010-09-01T23:59:59.000Z

400

Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan  

SciTech Connect (OSTI)

The following recommendations have been abstracted from the body of this report. The Office of Nuclear Waste Isolation's Socioeconomic Program Plan for the Establishment of Mined Geologic Repositories to Isolate Nuclear Waste should be modified to: (1) encourage active public participation in the decision-making processes leading to repository site selection; (2) clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process. In addition, the Office of Nuclear Waste Isolation should carefully review the overall role that these persons and groups, including local pressure groups organized in the face of potential repository development, will play in the siting process; (3) place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; (4) include additional approaches to solving socioeconomic problems. For example, a reluctance to acknowledge that solutions to socioeconomic problems need to be found jointly with interested parties is evident in the plan; (5) recognize that mitigation mechanisms other than compensation and incentives may be effective; (6) as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and (7) comply fully with the pertinent provisions of NWPA.

Winter, R.; Fenster, D.; O'Hare, M.; Zillman, D.; Harrison, W.; Tisue, M.

1984-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

402

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

403

Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities  

SciTech Connect (OSTI)

In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

Sasser, K.

1994-06-01T23:59:59.000Z

404

Large Scale Computing and Storage Requirements for Nuclear Physics Research  

E-Print Network [OSTI]

Low-Energy Nuclear Physics National Joseph Carlson / HPC Initiative: Building a Universal Joseph Carlson Jonathan Engel Nuclear Energy Density Functional Structure and Reactions

Gerber, Richard A.

2012-01-01T23:59:59.000Z

405

EIS-0109: Long-Term Management of the Existing Radioactive Wastes and Residues at the Niagara Falls Storage Site  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this statement to evaluate the environmental impacts of several alternatives for management and control of the radioactive wastes and residues at the Niagara Falls Storage Site, including a no action alternative, an alternative to manage wastes on-site, and two off-site management alternatives.

406

Feasibility of very deep borehole disposal of US nuclear defense wastes .  

E-Print Network [OSTI]

??This thesis analyzes the feasibility of emplacing DOE-owned defense nuclear waste from weapons production into a permanent borehole repository drilled ~4 km into granite basement… (more)

Dozier, Frances Elizabeth

2011-01-01T23:59:59.000Z

407

E-Print Network 3.0 - automated nuclear waste Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: automated nuclear waste Page: << < 1 2 3 4 5 > >> 1 Marc Bachman Amanda Lawing Summary: begins 1982...

408

E-Print Network 3.0 - active nuclear wastes Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: active nuclear wastes Page: << < 1 2 3 4 5 > >> 1 THE UNIVERSITY OF WESTERN ONTARIO RADIATION SAFETY...

409

Synthesis of a triblock polymer system for separation of actinides for nuclear waste remediation.  

E-Print Network [OSTI]

??Nuclear power waste contains radioactive isotopes with long half lives and the problem lies in the fact that the lanthanides and actinides must be separated… (more)

Hamilton, Doris Finley

2011-01-01T23:59:59.000Z

410

Public Participation in Nuclear Waste Management : a Comparative Analysis of the Swedish and Canadian Processes.  

E-Print Network [OSTI]

??This thesis addresses the issue of public participation in the implementation of nuclear waste management (NWM) strategies by comparing the NWM programs of Sweden and… (more)

Camacho, Rosanne

2005-01-01T23:59:59.000Z

411

Feasibility of lateral emplacement in very deep borehole disposal of high level nuclear waste .  

E-Print Network [OSTI]

??The U.S. Department of Energy recently filed a motion to withdraw the Nuclear Regulatory Commission license application for the High Level Waste Repository at Yucca… (more)

Gibbs, Jonathan Sutton

2010-01-01T23:59:59.000Z

412

Cesium and Strontium Specific Exchangers for Nuclear Waste Effluent Remediation  

SciTech Connect (OSTI)

During the past 50 years, nuclear defense activities have produced large quantities of nuclear waste that now require safe and permanent disposal. The general procedure to be implemented involves the removal of cesium and strontium from the waste solutions for disposal in permanently vitrified media. This requires highly selective sorbents or ion exchangers. Further, at the high radiation doses present in the solution, organic exchangers or sequestrants are likely to decompose over time. Inorganic ion exchangers are resistant to radiation damage and can exhibit remarkably high selectivities. We have synthesized three families of tunnel-type ion exchangers. The crystal structures of these compounds as well as their protonated phases, coupled with ion exchange titrations, were determined and this information was used to develop an understanding of their ion exchange behavior. The ion exchange selectivities of these phases could be regulated by isomorphous replacement of the framework metals by larger or smaller radius metals. In the realm of layered compounds, we prepared alumina, silica, and zirconia pillared clays and sodium micas. The pillared clays yielded very high Kd values for Cs+ and were very effective in removing Cs+ from groundwaters. The sodium micas also had a high affinity for Cs+ but an even greater attraction for S42+. They also possess the property of trapping these ions permanently as the layers slowly decrease their interlayer distance as loading occurs. Sodium nonatitanate exhibited extremely high Kd values for Sr2+ in alkaline tank wastes and should be considered for removal of Sr2+ in such cases. For tank wastes containing complexing agents, we have found that adding Ca2+ to the solution releases the complexed Sr2+ which may then be removed with the CST exchanger.

A. Clearfield; A. I. Bortun; L. A. Bortun; E. A. Bhlume; P. Sylvester; G. M. Graziano

2000-09-01T23:59:59.000Z

413

Blending mining and nuclear industries at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

At the Waste Isolation Pilot Plant (WIPP) traditional procedures for underground mining activities have been significantly altered in order to assure underground safety and project adherence to numerous regulatory requirements. Innovative techniques have been developed for WIPP underground procedures, mining equipment, and operating environments. The mining emphasis at WIPP is upon the quality of the excavation, not (as in conventional mines) on the production of ore. The WIPP is a United States Department of Energy (DOE) project that is located 30 miles southeast of Carlsbad, New Mexico, where the nation's first underground engineered nuclear repository is being constructed. The WIPP site was selected because of its location amidst a 607 meter thick salt bed, which provides a remarkably stable rock formation for the permanent storage of nuclear waste. The underground facility is located 655 meters below the earth's surface, in the Salado formation, which comprises two-hundred million year old halites with minor amounts of clay and anhydrites. When completed, the WIPP underground facility will consist of two components: approximately 81 square kilometers of experimental areas, and approximately 405 square kilometers of repository. 3 figs.

Walls, J.R.

1990-01-01T23:59:59.000Z

414

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1  

SciTech Connect (OSTI)

This document analyzes at a pregrammatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For pregrammatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

Not Available

1994-06-01T23:59:59.000Z

415

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs draft environmental impact statement. Summary  

SciTech Connect (OSTI)

This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management, this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum treatment, storage, and disposal of US Department of Energy wastes.

Not Available

1994-06-01T23:59:59.000Z

416

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 2, Part A  

SciTech Connect (OSTI)

This document analyzes at a programmatic level the potential environmental consequences over the next 40 years of alternatives related to the transportation, receipt, processing, and storage of spent nuclear fuel under the responsibility of the US Department of Energy. It also analyzes the site-specific consequences of the Idaho National Engineering Laboratory sitewide actions anticipated over the next 10 years for waste and spent nuclear fuel management and environmental restoration. For programmatic spent nuclear fuel management this document analyzes alternatives of no action, decentralization, regionalization, centralization and the use of the plans that existed in 1992/1993 for the management of these materials. For the Idaho National Engineering Laboratory, this document analyzes alternatives of no action, ten-year plan, minimum and maximum and maximum treatment, storage, and disposal of US Department of Energy wastes.

Not Available

1994-06-01T23:59:59.000Z

417

EIS-0062: Double-Shell Tanks for Defense High Level Waste Storage, Savannah River Site, Aiken, SC  

Broader source: Energy.gov [DOE]

This EIS analyzes the impacts of the various design alternatives for the construction of fourteen 1.3 million gallon high-activity radioactive waste tanks. The EIS further evaluates the effects of these alternative designs on tank durability, on the ease of waste retrieval from such tanks, and the choice of technology and timing for long-term storage or disposal of the wastes.

418

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

419

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, October 1--December 31, 1991  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities. (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State. (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987. (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State. (4) Work closely and consult with affected local governments and State agencies. (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1991-12-31T23:59:59.000Z

420

Thermodynamic data management system for nuclear waste disposal performance assessment  

SciTech Connect (OSTI)

Thermodynamic property values for use in assessing the performance of a nuclear waste repository are described. More emphasis is on a computerized data base management system which facilitates use of the thermodynamic data in sensitivity analysis and other studies which critically assess the performance of disposal sites. Examples are given of critical evaluation procedures; comparison of apparent equilibrium constants calculated from the data base, with other work; and of correlations useful in estimating missing values of both free energy and enthalpy of formation for aqueous species. 49 refs., 11 figs., 6 tabs.

Phillips, S.L.; Hale, F.V.; Siegel, M.D.

1988-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

THERMODYNAMIC TABLES FOR NUCLEAR WASTE ISOLATION, V.1: AQUEOUSSOLUTIONS DATABASE  

SciTech Connect (OSTI)

Tables of consistent thermodynamic property values for nuclear waste isolation are given. The tables include critically assessed values for Gibbs energy of formation. enthalpy of formation, entropy and heat capacity for minerals; solids; aqueous ions; ion pairs and complex ions of selected actinide and fission decay products at 25{sup o}C and zero ionic strength. These intrinsic data are used to calculate equilibrium constants and standard potentials which are compared with typical experimental measurements and other work. Recommendations for additional research are given.

Phillips, S.L.; Hale, F.V.; Silvester, L.F.

1988-05-01T23:59:59.000Z

422

Realization of the German Concept for Interim Storage of Spent Nuclear Fuel - Current Situation and Prospects  

SciTech Connect (OSTI)

The German government has determined a phase out of nuclear power. With respect to the management of spent fuel it was decided to terminate transports to reprocessing plants by 2005 and to set up interim storage facilities on power plant sites. This paper gives an overview of the German concept for spent fuel management focused on the new on-site interim storage concept and the applied interim storage facilities. Since the end of the year 1998, the utilities have applied for permission of on-site interim storage in 13 storage facilities and 5 storage areas; one application for the interim storage facility Stade was withdrawn due to the planned final shut down of Stade nuclear power plant in autumn 2003. In 2001 and 2002, 3 on-site storage areas and 2 on-site storage facilities for spent fuel were licensed by the Federal Office for Radiation Protection (BfS). A main task in 2002 and 2003 has been the examination of the safety and security of the planned interim storage facilities and the verification of the licensing prerequisites. In the aftermath of September 11, 2001, BfS has also examined the attack with a big passenger airplane. Up to now, these aircraft crash analyses have been performed for three on-site interim storage facilities; the fundamental results will be presented. It is the objective of BfS to conclude the licensing procedures for the applied on-site interim storage facilities in 2003. With an assumed construction period for the storage buildings of about two years, the on-site interim storage facilities could then be available in the year 2005.

Thomauske, B. R.

2003-02-25T23:59:59.000Z

423

Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)  

Broader source: Energy.gov [DOE]

GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

424

Novel Problems Associated with Accounting and Control of Nuclear Material from Decontamination and Decommissioning and in Waste  

SciTech Connect (OSTI)

Abstract The reduction in nuclear arms and the production facilities that supported the weapons programs have produced some unique problems for nuclear material control and accountability (MC&A). Many of these problems are not limited to the weapons complex, but have the potential to appear in many legacy facilities as they undergo dismantlement and disposal. Closing facilities find that what was previously defined as product has become a waste stream bringing regulatory, human, and technological conflict. The sometimes unique compositions of these materials produce both storage and measurement problems. The nuclear material accounting and control programs have had to become very adaptive and preemptive to ensure control and protection is maintained. This paper examines some of the challenges to Safeguards generated by deinventory, decontamination decommissioning, dismantlement, demolition, and waste site remediation from predictable sources and some from unpredictable sources. 1.0 Introduction The United States is eliminating many facilities that support the nuclear weapons program. With the changing political conditions around the world and changes in military capabilities, the decreased emphasis on nuclear weapons has eliminated the need for many of the aging facilities. Additionally, the recovery of plutonium from dismantled weapons and reuse of components has eliminated the need to produce more plutonium for the near future. Because the nuclear weapons program and commercial applications generally do not mix in the United States, the facilities in the DOE complex that no longer have a weapon mission are being deinventoried, decontaminated, decommissioned, and dismantled/demolished. The materials from these activities are then disposed of in various ways but usually in select waste burial sites. Additionally, the waste in many historical burial sites associated with the weapons complex are being recovered, repackaged if necessary, and disposed of in either geological sites or low-level waste sites. The type of waste from the decontamination and decommissioning (D&D) activities varies from uncontaminated construction materials to nuclear weapon components. This variety of forms, types, and composition of nuclear material presents many challenges to MC&A. It requires the creative application of regulations, but current regulations are adequate to ensure the security and control of the nuclear material. This paper examines some of the approaches used to meet regulatory requirements and problems that occurred during D&D. Experiences are drawn for the Hanford site and elsewhere in the DOE complex.

Schlegel, Steven C.

2007-07-10T23:59:59.000Z

425

Characterising encapsulated nuclear waste using cosmic-ray muon tomography  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons have been shown previously to successfully identify and characterise low- and high-Z materials within an air matrix using a prototype scintillating-fibre tracker system. Those studies were performed as the first in a series to assess the feasibility of this technology and image reconstruction techniques in characterising the potential high-Z contents of legacy nuclear waste containers for the UK Nuclear Industry. The present work continues the feasibility study and presents the first images reconstructed from experimental data collected using this small-scale prototype system of low- and high-Z materials encapsulated within a concrete-filled stainless-steel container. Clear discrimination is observed between the thick steel casing, the concrete matrix and the sample materials assayed. These reconstructed objects are presented and discussed in detail alongside the implications for future industrial scenarios.

Anthony Clarkson; David J. Hamilton; Matthias Hoek; David G. Ireland; John R. Johnstone; Ralf Kaiser; Tibor Keri; Scott Lumsden; David F. Mahon; Bryan McKinnon; Morgan Murray; Siân Nutbeam-Tuffs; Craig Shearer; Guangliang Yang; Colin Zimmerman

2014-10-27T23:59:59.000Z

426

Characterising encapsulated nuclear waste using cosmic-ray muon tomography  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons have been shown previously to successfully identify and characterise low- and high-Z materials within an air matrix using a prototype scintillating-fibre tracker system. Those studies were performed as the first in a series to assess the feasibility of this technology and image reconstruction techniques in characterising the potential high-Z contents of legacy nuclear waste containers for the UK Nuclear Industry. The present work continues the feasibility study and presents the first images reconstructed from experimental data collected using this small-scale prototype system of low- and high-Z materials encapsulated within a concrete-filled stainless-steel container. Clear discrimination is observed between the thick steel casing, the concrete matrix and the sample materials assayed. These reconstructed objects are presented and discussed in detail alongside the implications for future industrial scenarios.

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, John R; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Siân; Shearer, Craig; Yang, Guangliang; Zimmerman, Colin

2014-01-01T23:59:59.000Z

427

Improving the Estimates of Waste from the Recycling of Used Nuclear Fuel - 13410  

SciTech Connect (OSTI)

Estimates are presented of wastes arising from the reprocessing of 50 GWD/tonne, 5 year and 50 year cooled used nuclear fuel (UNF) from Light Water Reactors (LWRs), using the 'NUEX' solvent extraction process. NUEX is a fourth generation aqueous based reprocessing system, comprising shearing and dissolution in nitric acid of the UNF, separation of uranium and mixed uranium-plutonium using solvent extraction in a development of the PUREX process using tri-n-butyl phosphate in a kerosene diluent, purification of the plutonium and uranium-plutonium products, and conversion of them to uranium trioxide and mixed uranium-plutonium dioxides respectively. These products are suitable for use as new LWR uranium oxide and mixed oxide fuel, respectively. Each unit process is described and the wastes that it produces are identified and quantified. Quantification of the process wastes was achieved by use of a detailed process model developed using the Aspen Custom Modeler suite of software and based on both first principles equilibrium and rate data, plus practical experience and data from the industrial scale Thermal Oxide Reprocessing Plant (THORP) at the Sellafield nuclear site in the United Kingdom. By feeding this model with the known concentrations of all species in the incoming UNF, the species and their concentrations in all product and waste streams were produced as the output. By using these data, along with a defined set of assumptions, including regulatory requirements, it was possible to calculate the waste forms, their radioactivities, volumes and quantities. Quantification of secondary wastes, such as plant maintenance, housekeeping and clean-up wastes, was achieved by reviewing actual operating experience from THORP during its hot operation from 1994 to the present time. This work was carried out under a contract from the United States Department of Energy (DOE) and, so as to enable DOE to make valid comparisons with other similar work, a number of assumptions were agreed. These include an assumed reprocessing capacity of 800 tonnes per year, the requirement to remove as waste forms the volatile fission products carbon-14, iodine-129, krypton-85, tritium and ruthenium-106, the restriction of discharge of any water from the facility unless it meets US Environmental Protection Agency drinking water standards, no intentional blending of wastes to lower their classification, and the requirement for the recovered uranium to be sufficiently free from fission products and neutron-absorbing species to allow it to be re-enriched and recycled as nuclear fuel. The results from this work showed that over 99.9% of the radioactivity in the UNF can be concentrated via reprocessing into a fission-product-containing vitrified product, bottles of compressed krypton storage and a cement grout containing the tritium, that together have a volume of only about one eighth the volume of the original UNF. The other waste forms have larger volumes than the original UNF but contain only the remaining 0.1% of the radioactivity. (authors)

Phillips, Chris; Willis, William; Carter, Robert [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States)] [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Baker, Stephen [UK National Nuclear Laboratory, Warrington, Cheshire (United Kingdom)] [UK National Nuclear Laboratory, Warrington, Cheshire (United Kingdom)

2013-07-01T23:59:59.000Z

428

Destruction of Plutonium and Other Nuclear Waste Materials Using the Accelerator-Driven Transmutation of Waste Concept  

Science Journals Connector (OSTI)

Each large nuclear power plant produces about 300 kilograms of ... about 120 kilograms of long-lived fission product wastes per year, with major constituents in terms ... humans either directly or by clandestine ...

F. Venneri

1997-01-01T23:59:59.000Z

429

Myth of nuclear explosions at waste disposal sites  

SciTech Connect (OSTI)

Approximately 25 years ago, an event is said to have occurred in the plains immediately west of the southern Ural mountains of the Soviet Union that is being disputed to this very day. One person says it was an explosion of nuclear wastes buried in a waste disposal site; other people say it was an above-ground test of an atomic weapon; still others suspect that an alleged contaminated area (of unknown size or even existence) is the result of a series of careless procedures. Since the event, a number of articles about the disposal-site explosion hypothesis written by a Soviet exile living in the United Kingdom have been published. Although the Soviet scientist's training and background are in the biological sciences and his knowledge of nuclear physics or chemistry is limited, people who oppose the use of nuclear energy seem to want to believe what he says without question. The work of this Soviet biologist has received wide exposure both in the United Kingdom and the United States. This report presents arguments against the disposal-site explosion hypothesis. Included are discussions of the amounts of plutonium that would be in a disposal site, the amounts of plutonium that would be needed to reach criticality in a soil-water-plutonium mixture, and experiments and theoretical calculations on the behavior of such mixtures. Our quantitative analyses show that the postulated nuclear explosion is so improbable that it is essentially impossible and can be found only in the never-never land of an active imagination. 24 references, 14 figures, 5 tables.

Stratton, W.R.

1983-10-01T23:59:59.000Z

430

Equipment design guidance document for flammable gas waste storage tank new equipment  

SciTech Connect (OSTI)

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas.

Smet, D.B.

1996-04-11T23:59:59.000Z

431

Fusion–fission hybrids for nuclear waste transmutation: A synergistic step between Gen-IV fission and fusion reactors  

Science Journals Connector (OSTI)

Energy demand and GDP per capita are strongly correlated, while public concern over the role of energy in climate change is growing. Nuclear power plants produce 16% of world electricity demands without greenhouse gases. Generation-IV advanced nuclear energy systems are being designed to be safe and economical. Minimizing the handling and storage of nuclear waste is important. NIF and ITER are bringing sustainable fusion energy closer, but a significant gap in fusion technology development remains. Fusion–fission hybrids could be a synergistic step to a pure fusion economy and act as a technology bridge. We discuss how a pulsed power-driven Z-pinch hybrid system producing only 20 MW of fusion yield can drive a sub-critical transuranic blanket that transmutes 1280 kg of actinide wastes per year and produces 3000 MW. These results are applicable to other inertial and magnetic fusion energy systems. A hybrid system could be introduced somewhat sooner because of the modest fusion yield requirements and can provide both a safe alternative to fast reactors for nuclear waste transmutation and a maturation path for fusion technology. The development and demonstration of advanced materials that withstand high-temperature, high-irradiation environments is a fundamental technology issue that is common to both fusion–fission hybrids and Generation-IV reactors.

T.A. Mehlhorn; B.B. Cipiti; C.L. Olson; G.E. Rochau

2008-01-01T23:59:59.000Z

432

Fusion-fission hybrids for nuclear waste transmutation : a synergistic step between Gen-IV fission and fusion reactors.  

SciTech Connect (OSTI)

Energy demand and GDP per capita are strongly correlated, while public concern over the role of energy in climate change is growing. Nuclear power plants produce 16% of world electricity demands without greenhouse gases. Generation-IV advanced nuclear energy systems are being designed to be safe and economical. Minimizing the handling and storage of nuclear waste is important. NIF and ITER are bringing sustainable fusion energy closer, but a significant gap in fusion technology development remains. Fusion-fission hybrids could be a synergistic step to a pure fusion economy and act as a technology bridge. We discuss how a pulsed power-driven Z-pinch hybrid system producing only 20 MW of fusion yield can drive a sub-critical transuranic blanket that transmutes 1280 kg of actinide wastes per year and produces 3000 MW. These results are applicable to other inertial and magnetic fusion energy systems. A hybrid system could be introduced somewhat sooner because of the modest fusion yield requirements and can provide both a safe alternative to fast reactors for nuclear waste transmutation and a maturation path for fusion technology. The development and demonstration of advanced materials that withstand high-temperature, high-irradiation environments is a fundamental technology issue that is common to both fusion-fission hybrids and Generation-IV reactors.

Olson, Craig Lee; Mehlhorn, Thomas Alan; Cipiti, Benjamin B.; Rochau, Gary Eugene

2007-09-01T23:59:59.000Z

433

DOE Completes Annual Determination of the Adequacy of the Nuclear Waste  

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

Completes Annual Determination of the Adequacy of the Nuclear Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee November 2, 2010 - 7:41pm Addthis As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. Addthis Related Articles GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions

434

Evaluation of Radiation Impacts of Spent Nuclear Fuel Storage (SNFS-2) of Chernobyl NPP - 13495  

SciTech Connect (OSTI)

Radiation effects are estimated for the operation of a new dry storage facility for spent nuclear fuel (SNFS-2) of Chernobyl NPP RBMK reactors. It is shown that radiation exposure during normal operation, design and beyond design basis accidents are minor and meet the criteria for safe use of radiation and nuclear facilities in Ukraine. (authors)

Paskevych, Sergiy; Batiy, Valiriy; Sizov, Andriy [Institute for Safety Problems of Nuclear Power Plants, National Academy of Sciences of Ukraine, 36 a Kirova str. Chornobyl, Kiev region, 07200 (Ukraine)] [Institute for Safety Problems of Nuclear Power Plants, National Academy of Sciences of Ukraine, 36 a Kirova str. Chornobyl, Kiev region, 07200 (Ukraine); Schmieman, Eric [Battelle Memorial Institute, PO Box 999 MSIN K6-90, Richland, WA 99352 (United States)] [Battelle Memorial Institute, PO Box 999 MSIN K6-90, Richland, WA 99352 (United States)

2013-07-01T23:59:59.000Z

435

FATE Unified Modeling Method for Spent Nuclear Fuel and Sludge Processing, Shipping and Storage - 13405  

SciTech Connect (OSTI)

A unified modeling method applicable to the processing, shipping, and storage of spent nuclear fuel and sludge has been incrementally developed, validated, and applied over a period of about 15 years at the US DOE Hanford site. The software, FATE{sup TM}, provides a consistent framework for a wide dynamic range of common DOE and commercial fuel and waste applications. It has been used during the design phase, for safety and licensing calculations, and offers a graded approach to complex modeling problems encountered at DOE facilities and abroad (e.g., Sellafield). FATE has also been used for commercial power plant evaluations including reactor building fire modeling for fire PRA, evaluation of hydrogen release, transport, and flammability for post-Fukushima vulnerability assessment, and drying of commercial oxide fuel. FATE comprises an integrated set of models for fluid flow, aerosol and contamination release, transport, and deposition, thermal response including chemical reactions, and evaluation of fire and explosion hazards. It is one of few software tools that combine both source term and thermal-hydraulic capability. Practical examples are described below, with consideration of appropriate model complexity and validation. (authors)

Plys, Martin; Burelbach, James; Lee, Sung Jin; Apthorpe, Robert [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)] [Fauske and Associates, LLC, 16W070 83rd St., Burr Ridge, IL, 60527 (United States)

2013-07-01T23:59:59.000Z

436

Separation of technetium from nuclear waste stream simulants. Final report  

SciTech Connect (OSTI)

The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

1995-09-11T23:59:59.000Z

437

GEOTECHNICAL ASSESSMENT AND INSTRUMENTATION NEEDS FOR NUCLEAR WASTE ISOLATION IN CRYSTALLINE AND ARGILLACEOUS ROCKS SYMPOSIUM  

E-Print Network [OSTI]

active waste storage glass. AERE-R 8706, May. Hall, A. R. ,from dispersed blocks, AERE-R 8763, June. Holdoway, M. J. (to the FINGAL process. AERE-R 6418, May. Jenkins, I. L. (

Authors, Various

2011-01-01T23:59:59.000Z

438

Measurement of Atmospheric Sea Salt Concentration in the Dry Storage Facility of the Spent Nuclear Fuel  

SciTech Connect (OSTI)

Spent nuclear fuel coming from a Japanese nuclear power plant is stored in the interim storage facility before reprocessing. There are two types of the storage methods which are wet and dry type. In Japan, it is anticipated that the dry storage facility will increase compared with the wet type facility. The dry interim storage facility using the metal cask has been operated in Japan. In another dry storage technology, there is a concrete overpack. Especially in USA, a lot of concrete overpacks are used for the dry interim storage. In Japan, for the concrete cask, the codes of the Japan Society of Mechanical Engineers and the governmental technical guidelines are prepared for the realization of the interim storage as well as the code for the metal cask. But the interim storage using the concrete overpack has not been in progress because the evaluation on the stress corrosion cracking (SCC) of the canister is not sufficient. Japanese interim storage facilities would be constructed near the seashore. The metal casks and concrete overpacks are stored in the storage building in Japan. On the other hand, in USA they are stored outside. It is necessary to remove the decay heat of the spent nuclear fuel in the cask from the storage building. Generally, the heat is removed by natural cooling in the dry storage facility. Air including the sea salt particles goes into the dry storage facility. Concerning the concrete overpack, air goes into the cask body and cools the canister. Air goes along the canister surface and is in contact with the surface directly. In this case, the sea salt in the air attaches to the surface and then there is the concern about the occurrence of the SCC. For the concrete overpack, the canister including the spent fuel is sealed by the welding. The loss of sealability caused by the SCC has to be avoided. To evaluate the SCC for the canister, it is necessary to make clear the amount of the sea salt particles coming into the storage building and the concentration on the canister. In present, the evaluation on that point is not sufficient. In this study, the concentration of the sea salt particles in the air and on the surface of the storage facility are measured inside and outside of the building. For the measurement, two sites of the dry storage facility using the metal cask are chosen. This data is applicable for the evaluation on the SCC of the canister to realize the interim storage using the concrete overpack. (authors)

Masumi Wataru; Hisashi Kato; Satoshi Kudo; Naoko Oshima; Koji Wada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Hirofumi Narutaki [Electric Power Engineering Systems Co. Ltd. (Japan)

2006-07-01T23:59:59.000Z

439

Corrective Action Investigation Plan for Corrective Action Unit 140: Waste Dumps, Burn Pits, and Storage Area, Nevada Test Site, Nevada, July 2002, Rev. No. 0  

SciTech Connect (OSTI)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 140 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 140 consists of nine Corrective Action Sites (CASs): 05-08-01, Detonation Pits; 05-08-02, Debris Pits; 05-17-01, Hazardous Waste Accumulation Site (Buried); 05-19-01, Waste Disposal Site; 05-23-01, Gravel Gertie; 05-35-01, Burn Pit; 05-99-04, Burn Pit; 22-99-04, Radioactive Waste Dump; 23-17-01, Hazardous Waste Storage Area. All nine of these CASs are located within Areas 5, 22, and 23 of the Nevada Test Site (NTS) in Nevada, approximately 65 miles northwest of Las Vegas. This CAU is being investigated because disposed waste may be present without appropriate controls (i.e., use restrictions, adequate cover) and hazardous and/or radioactive constituents may be present or migrating at concentrations and locations that could potentially pose a threat to human health and the environment. The NTS has been used for various research and development projects including nuclear weapons testing. The CASs in CAU 140 were used for testing, material storage, waste storage, and waste disposal. A two-phase approach has been selected to collect information and generate data to satisfy needed resolution criteria and resolve the decision statements. Phase I will determine if contaminants of potential concern (COPCs) are present in concentrations exceeding preliminary action levels. This data will be evaluated at all CASs. Phase II will determine the extent of the contaminant(s) of concern (COCs). This data will only be evaluated for CASs with a COC identified during Phase I. Based on process knowledge, the COPCs for CAU 140 include volatile organics, semivolatile organics, petroleum hydrocarbons, explosive residues, herbicides, pesticides, polychlorinated biphenyls, metals, and radionuclides. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

NNSA /NV

2002-07-18T23:59:59.000Z

440

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 HYDROGEN STORAGE FOR MIXED WIND-NUCLEAR POWER PLANTS IN  

E-Print Network [OSTI]

INTERNATIONAL JOURNAL OF HYDROGEN ENERGY Accepted June 2008 1 HYDROGEN STORAGE FOR MIXED WIND-NUCLEAR evaluation of hydrogen production and storage for a mixed wind-nuclear power plant considering some new of a combined nuclear-wind-hydrogen system is discussed first, where the selling and buying of electricity

Cañizares, Claudio A.

Note: This page contains sample records for the topic "nuclear waste storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Radiation consequences of seawater contamination during floating storage of reactor-compartment units from salvaged nuclear-powered submarines  

Science Journals Connector (OSTI)

The storage time before salvaging of decommissioned nuclear-powered submarines and the floating storage time of reactor units from salvaged submarines ... decades. During this time, radioactive contamination of seawater

A. Ya. Blekher; N. L. Kuchin; I. V. Sergeev

442

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

2011-01-01T23:59:59.000Z

443

Radiolytic effects on ion exchangers during the storage of radioactive wastes  

SciTech Connect (OSTI)

Radiolytic effects on ion exchangers are being recognized as a significant problem in the processing and storage of high-specific-activity radioactive waste forms. Two major literature surveys and a series of scoping experiments conducted during this investigation indicate that radiation decomposition of ion exchange materials has the potential for a variety of undesirable consequences. These include the ready dispersion of adsorbed radionuclides to the environment, corrosion and pressurization of waste canisters, and generation of flammable and explosive gases, as well as agglomeration of ion exchangers to a rigid monolith with the partitioning of a liquid phase. Some of the highlights of the literature surveys and the major findings of the experimental studies are reported here.

Pillay, K.K.S.; Palau, G.L.

1982-01-01T23:59:59.000Z

444

Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations  

SciTech Connect (OSTI)

This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

1996-12-01T23:59:59.000Z

445

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, Lien-Mow (North Augusta, SC); Kilpatrick, Lester L. (Aiken, SC)

1984-01-01T23:59:59.000Z

446

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, L.M.; Kilpatrick, L.L.

1982-05-19T23:59:59.000Z

447

ADMINISTRATIVE AND ENGINEERING CONTROLS FOR THE OPERATION OF VENTILATION SYSTEMS FOR UNDERGROUND RADIOACTIVE WASTE STORAGE TANKS  

SciTech Connect (OSTI)

Liquid radioactive wastes from the Savannah River Site are stored in large underground carbon steel tanks. The majority of the waste is confined in double shell tanks, which have a primary shell, where the waste is stored, and a secondary shell, which creates an annular region between the two shells, that provides secondary containment and leak detection capabilities should leakage from the primary shell occur. Each of the DST is equipped with a purge ventilation system for the interior of the primary shell and annulus ventilation system for the secondary containment. Administrative flammability controls require continuous ventilation to remove hydrogen gas and other vapors from the waste tanks while preventing the release of radionuclides to the atmosphere. Should a leak from the primary to the annulus occur, the annulus ventilation would also serve this purpose. The functionality of the annulus ventilation is necessary to preserve the structural integrity of the primary shell and the secondary. An administrative corrosion control program is in place to ensure integrity of the tank. Given the critical functions of the purge and annulus ventilation systems, engineering controls are also necessary to ensure that the systems remain robust. The system consists of components that are constructed of metal (e.g., steel, stainless steel, aluminum, copper, etc.) and/or polymeric (polypropylene, polyethylene, silicone, polyurethane, etc.) materials. The performance of these materials in anticipated service environments (e.g., normal waste storage, waste removal, etc.) was evaluated. The most aggressive vapor space environment occurs during chemical cleaning of the residual heels by utilizing oxalic acid. The presence of NO{sub x} and mercury in the vapors generated from the process could potentially accelerate the degradation of aluminum, carbon steel, and copper. Once identified, the most susceptible materials were either replaced and/or plans for discontinuing operations are executed.

Wiersma, B.; Hansen, A.

2013-11-13T23:59:59.000Z

448

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.  

SciTech Connect (OSTI)

Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.

Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory (Raytheon Ktech, Albuquerque, NM)

2011-11-01T23:59:59.000Z

449

Storage  

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

Storage Storage DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Storage A discussion of depleted UF6 cylinder storage activities and associated risks. Management Activities for Cylinders in Storage The long-term management of the existing DUF6 storage cylinders and the continual effort to remediate and maintain the safe condition of the DUF6 storage cylinders will remain a Departmental responsibility for many years into the future. The day to day management of the DUF6 cylinders includes actions designed to cost effectively maintain and improve their storage conditions, such as: General storage cylinder and storage yard maintenance; Performing regular inspections of cylinders; Restacking and respacing the cylinders to improve drainage and to

450

Storage  

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

Environmental Risks » Storage Environmental Risks » Storage Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Storage Discussion of the potential environmental impacts from storage of depleted UF6 at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts Analyzed in the PEIS The PEIS included an analysis of the potential environmental impacts from continuing to store depleted UF6 cylinders at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts from Continued Storage of UF6 Cylinders Continued storage of the UF6 cylinders would require extending the use of a

451

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

452

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

453

The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL  

E-Print Network [OSTI]

Report t The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Web site. #12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie Mellon. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson National Science

454

Assessment of degradation concerns for spent fuel, high-level wastes, and transuranic wastes in monitored retrievalbe storage  

SciTech Connect (OSTI)

It has been concluded that there are no significant degradation mechanisms that could prevent the design, construction, and safe operation of monitored retrievable storage (MRS) facilities. However, there are some long-term degradation mechanisms that could affect the ability to maintain or readily retrieve spent fuel (SF), high-level wastes (HLW), and transuranic wastes (TRUW) several decades after emplacement. Although catastrophic failures are not anticipated, long-term degradation mechanisms have been identified that could, under certain conditions, cause failure of the SF cladding and/or failure of TRUW storage containers. Stress rupture limits for Zircaloy-clad SF in MRS range from 300 to 440/sup 0/C, based on limited data. Additional tests on irradiated Zircaloy (3- to 5-year duration) are needed to narrow this uncertainty. Cladding defect sizes could increase in air as a result of fuel density decreases due to oxidation. Oxidation tests (3- to 5-year duration) on SF are also needed to verify oxidation rates in air and to determine temperatures below which monitoring of an inert cover gas would not be required. Few, if any, changes in the physical state of HLW glass or canisters or their performance would occur under projected MRS conditions. The major uncertainty for HLW is in the heat transfer through cracked glass and glass devitrification above 500/sup 0/C. Additional study of TRUW is required. Some fraction of present TRUW containers would probably fail within the first 100 years of MRS, and some TRUW would be highly degraded upon retrieval, even in unfailed containers. One possible solution is the design of a 100-year container. 93 references, 28 figures, 17 tables.

Guenther, R.J.; Gilbert, E.R.; Slate, S.C.; Partain, W.L.; Divine, J.R.; Kreid, D.K.

1984-01-01T23:59:59.000Z

455

GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions |  

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

GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions February 26, 2010 - 3:17pm Addthis Consistent with the Administration's commitment to transparency, DOE General Counsel Scott Blake Harris has decided that all future determinations as to the adequacy of the Nuclear Waste Fund fee will be made available to the public on DOE's website shortly after DOE makes a determination. The report relied upon in determining fee adequacy for 2008, the most recent year for which DOE has made a determination, is available here: (2008 Fee Adequacy Letter Report). Addthis Related Articles DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee Department of Energy Files Motion to Withdraw Yucca Mountain License

456

Record of Cycling Operation of the Natural Nuclear Reactor in the Oklo/Okelobondo Area in Gabon  

E-Print Network [OSTI]

of variability of the long-term fundamental physical constants [5,6] to storage of nuclear wastes in geological on how to retain nuclear wastes, including fission Xe and Kr, and prevent uncontrolled runaway chain

457

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010  

Broader source: Energy.gov [DOE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010

458

Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)  

SciTech Connect (OSTI)

The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

COVEY, L.I.

2000-11-28T23:59:59.000Z

459

Degradation of transuranic waste drums in underground storage at the Hanford Site  

SciTech Connect (OSTI)

In situ inspections were performed on tarp-covered 55-gallon drums of transuranic (TRU) waste stored underground at the Hanford Site. These inspections were part of a task to characterize TRU drums for extent of corrosion degradation and uncertainty in TRU designation (inaccuracy in earlier assay determinations may have led to drums that actually were low-level waste to be termed TRU), and to attempt to correlate accuracy of existing records with actual drum contents. Two separate storage trench sites were investigated; a total of 90 drums were inspected with ultrasonic techniques and 104 additional drums were visually inspected. A high-humidity environment in the underground storage trenches had been reported in earlier investigations and was expected to result in substantial corrosion degradation. However, corrosion was much less than expected. Only a small percentage of drums had significant corrosion (with one breach) and the maximum rate was estimated at 0.051 mm/yr (2 mils/yr). The corrosion time of underground exposure was 14 to 15 years. These inspection results should be applicable to other similar environments (this applicability should be restricted to arid climates such as the Hanford Site) where drums are stored underground but shielded from direct soil contact by a tarp or other means. Soil contact would lead to more rapid corrosion.

Duncan, D.R.

1996-05-07T23:59:59.000Z

460

A ThreeDimensional Finite Element Simulation for Transport of Nuclear Waste Contamination in Porous Media \\Lambda  

E-Print Network [OSTI]

A Three­Dimensional Finite Element Simulation for Transport of Nuclear Waste Contamination for transport of nuclear­waste contamination in three­dimensional porous media are presented with a description of contamination of groundwater by high­level nuclear waste and a wide variety of other sources makes a proper

Ewing, Richard E.