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1

License for the Konrad Deep Geological Repository  

SciTech Connect (OSTI)

Deep geological disposal of long-lived radioactive waste is currently considered a major challenge. Until present, only three deep geological disposal facilities have worldwide been operated: the Asse experimental repository (1967-1978) and the Morsleben repository (1971-1998) in Germany as well as the Waste Isolation Pilot Plant (WIPP) in the USA (1999 to present). Recently, the licensing procedure for the fourth such facility, the German Konrad repository, ended with a positive ''Planfeststellung'' (plan approval). With its plan approval decision, the licensing authority, the Ministry of the Environment of the state of Lower Saxony, approved the single license needed pursuant to German law to construct, operate, and later close down this facility.

Biurrun, E.; Hartje, B.

2003-02-24T23:59:59.000Z

2

Current Status of The Romanian National Deep Geological Repository Program  

SciTech Connect (OSTI)

Construction of a deep geological repository is a very demanding and costly task. By now, countries that have Candu reactors, have not processed the spent fuel passing to the interim storage as a preliminary step of final disposal within the nuclear fuel cycle back-end. Romania, in comparison to other nations, represents a rather small territory, with high population density, wherein the geological formation areas with radioactive waste storage potential are limited and restricted not only from the point of view of the selection criteria due to the rocks natural characteristics, but also from the point of view of their involvement in social and economical activities. In the framework of the national R and D Programs, series of 'Map investigations' have been made regarding the selection and preliminary characterization of the host geological formation for the nation's spent fuel deep geological repository. The fact that Romania has many deposits of natural gas, oil, ore and geothermal water, and intensively utilizes soil and also is very forested, cause some of the apparent acceptable sites to be rejected in the subsequent analysis. Currently, according to the Law on the spent fuel and radioactive waste management, including disposal, The National Agency of Radioactive Waste is responsible and coordinates the national strategy in the field and, subsequently, further actions will be decided. The Romanian National Strategy, approved in 2004, projects the operation of a deep geological repository to begin in 2055. (authors)

Radu, M.; Nicolae, R.; Nicolae, D. [Center of Technology and Engineering for Nuclear Objectives (CITON), ILFOV County (Romania)

2008-07-01T23:59:59.000Z

3

Development of an Integrated Natural Barrier Database System for Site Evaluation of a Deep Geologic Repository in Korea - 13527  

SciTech Connect (OSTI)

Korea Radioactive-waste Management Corporation (KRMC) established in 2009 has started a new project to collect information on long-term stability of deep geological environments on the Korean Peninsula. The information has been built up in the integrated natural barrier database system available on web (www.deepgeodisposal.kr). The database system also includes socially and economically important information, such as land use, mining area, natural conservation area, population density, and industrial complex, because some of this information is used as exclusionary criteria during the site selection process for a deep geological repository for safe and secure containment and isolation of spent nuclear fuel and other long-lived radioactive waste in Korea. Although the official site selection process has not been started yet in Korea, current integrated natural barrier database system and socio-economic database is believed that the database system will be effectively utilized to narrow down the number of sites where future investigation is most promising in the site selection process for a deep geological repository and to enhance public acceptance by providing readily-available relevant scientific information on deep geological environments in Korea. (authors)

Jung, Haeryong; Lee, Eunyong; Jeong, YiYeong; Lee, Jeong-Hwan [Korea Radioactive-waste Management Corportation - KRMC, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)] [Korea Radioactive-waste Management Corportation - KRMC, 1045 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

4

New developments in measurement technology relevant to the studies of deep geological repositories in domed salt and basalt  

SciTech Connect (OSTI)

This report briefly describes recent geophysical and geotechnical instrumentation developments relevant to the studies of deep geologic repositories. Special emphasis has been placed on techniques that appear to minimize measurement problems associated with repositories constructed in basalt or domed salt. Included in the listing are existing measurement capabilities and deficiencies that have been identified by a few authors and instrumentation workshops that have assessed the capabilities of existing instrumentation with respect to repository applications. These deficiencies have been compared with the reported advantages and limitations of the new developments described. Based on these comparisons, areas that merit further research and development have been identified. The report is based on a thorough literature review and on discussions with several instrumentation specialists involved in instrumentation development.

Ramirez, A.L.; Mao, N.H.

1980-05-21T23:59:59.000Z

5

The Aespoe Hard Rock Laboratory -- A preparation for the licensing of the deep geological repository for spent fuel in Sweden  

SciTech Connect (OSTI)

The Aespoe Hard Rock Laboratory is being constructed in preparation for the deep geological repository for demonstration deposition of spent fuel in Sweden. This paper describes the main and stage goals of the project. The site characterization prior to construction of the laboratory is described, as well as the on-going studies during construction of the laboratory. Excavation of the laboratory is planned to reach the final depth of 460 m below the surface in 1994. The program for the Operating Phase is in progress. It will be developed in cooperation with the seven organizations from six countries that are now participating in the Aespoe Hard Rock Laboratory.

Backblom, G. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

1993-12-31T23:59:59.000Z

6

The Waste Isolation Pilot Plant Deep Geological Repository: A Domestic and Global Blueprint for Safe Disposal of High-Level Radioactive Waste - 12081  

SciTech Connect (OSTI)

At the end of 2011, the world's first used/spent nuclear fuel and other long-lived high-level radioactive waste (HLW) repository is projected to open in 2020, followed by two more in 2025. The related pre-opening periods will be at least 40 years, as it also would be if USA's candidate HLW-repository is resurrected by 2013. If abandoned, a new HLW-repository site would be needed. On 26 March 1999, USA began disposing long-lived radioactive waste in a deep geological repository in salt at the Waste Isolation Pilot Plant (WIPP) site. The related pre-opening period was less than 30 years. WIPP has since been re-certified twice. It thus stands to reason the WIPP repository is the global proof of principle for safe deep geological disposal of long-lived radioactive waste. It also stands to reason that the lessons learned since 1971 at the WIPP site provide a unique, continually-updated, blueprint for how the pre-opening period for a new HLW repository could be shortened both in the USA and abroad. (authors)

Eriksson, Leif G. [Nuclear Waste Dispositions, Winter Park, Florida 32789 (United States); Dials, George E. [B and W Conversion Services, LLC, Lexington, Kentucky 40513 (United States)

2012-07-01T23:59:59.000Z

7

Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository  

SciTech Connect (OSTI)

In the present energy dilemma in which we find ourselves, the magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. Nuclear energy must be a major portion of the distribution. One often-cited strategic hurdle to the commercial production of nuclear energy is the apparent lack of an acceptable nuclear waste repository. This issue has been quietly addressed at the U. S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP; see http://www.wipp.energy.gov), the closest population center of significant size being Carlsbad, New Mexico. WIPP has been operating for about nine years, disposing of over 250,000 drum-equivalents of nuclear waste. From the standpoint of addressing operational and environmental risk, as well as public fear, WIPP has had extensive human health and environmental monitoring. The Carlsbad Environmental Monitoring and Research Center is in the Institute for Energy and the Environment, in the College of Engineering at New Mexico State University. Located in Carlsbad, NM, CEMRC has been the independent monitoring facility for the area around WIPP from 1993 to the present, i.e., from six years before disposal operations began to nine years of waste disposal operations (www.cemcr.org). Based on the radiological analyses of monitoring samples completed to date for area residents and site workers, and for selected aerosols, soils, sediments, drinking water and surface waters, there is no evidence of increases in radiological contaminants in the region of WIPP that could be attributed to releases from WIPP. Levels of radiological and non-radiological analytes measured since operations began in 1999 have been within the range of baseline levels measured previously, and are within the ranges measured by other entities at the State and local levels since well before disposal phase operations began in 1999. (authors)

Conca, J.; Kirchner, Th.; Monk, J.; Sage, S. [Carlsbad Environmental Monitoring and Research Center, IEE NMSU, 1400 University Drive, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

8

Use of groundwater lifetime expectancy for the performance assessment of a deep geologic radioactive waste repository:2. Application to a Canadian Shield environment  

E-Print Network [OSTI]

Cornaton et al. [2007] introduced the concept of lifetime expectancy as a performance measure of the safety of subsurface repositories, based upon the travel time for contaminants released at a certain point in the subsurface to reach the biosphere or compliance area. The methodologies are applied to a hypothetical but realistic Canadian Shield crystalline rock environment, which is considered to be one of the most geologically stable areas on Earth. In an approximately 10\\times10\\times1.5 km3 hypothetical study area, up to 1000 major and intermediate fracture zones are generated from surface lineament analyses and subsurface surveys. In the study area, mean and probability density of lifetime expectancy are analyzed with realistic geologic and hydrologic shield settings in order to demonstrate the applicability of the theory and the numerical model for optimally locating a deep subsurface repository for the safe storage of spent nuclear fuel. The results demonstrate that, in general, groundwater lifetime exp...

Park, Y -J; Normani, S D; Sykes, J F; Sudicky, E A

2011-01-01T23:59:59.000Z

9

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

10

Salt Disposal Investigations to Study Thermally Hot Radioactive Waste In A Deep Geologic Repository in Bedded Rock Salt - 12488  

SciTech Connect (OSTI)

A research program is proposed to investigate the behavior of salt when subjected to thermal loads like those that would be present in a high-level waste repository. This research would build upon results of decades of previous salt repository program efforts in the US and Germany and the successful licensing and operation of a repository in salt for disposal of defense transuranic waste. The proposal includes a combination of laboratory-scale investigations, numerical simulations conducted to develop validated models that could be used for future repository design and safety case development, and a thermal field test in an underground salt formation with a configuration that replicates a small portion of a conceptual repository design. Laboratory tests are proposed to measure salt and brine properties across and beyond the range of possible repository conditions. Coupled numerical models will seek to describe phenomenology (thermal, mechanical, and hydrological) observed in the laboratory tests. Finally, the field test will investigate many phenomena that have been variously cited as potential issues for disposal of thermally hot waste in salt, including buoyancy effects and migration of pre-existing trapped brine up the thermal gradient (including vapor phase migration). These studies are proposed to be coordinated and managed by the Carlsbad Field Office of DOE, which is also responsible for the operation of the Waste Isolation Pilot Plant (WIPP) within the Office of Environmental Management. The field test portion of the proposed research would be conducted in experimental areas of the WIPP underground, far from disposal operations. It is believed that such tests may be accomplished using the existing infrastructure of the WIPP repository at a lower cost than if such research were conducted at a commercial salt mine at another location. The phased field test is proposed to be performed over almost a decade, including instrumentation development, several years of measurements during heating and then subsequent cooling periods, and the eventual forensic mining back of the test bed to determine the multi-year behavior of the simulated waste/rock environment. Funding possibilities are described, and prospects for near term start-up are discussed. Mining of the access drifts required to create the test area in the WIPP underground began in November 2011. Because this mining uses existing WIPP infrastructure and labor, it is estimated to take about two years to complete the access drifts. WIPP disposal operations and facility maintenance activities will take priority over the SDI field test area mining. Funding of the SDI proposal was still being considered by DOE's Offices of Environmental Management and Nuclear Energy at the time this paper was written, so no specific estimates of the progress in 2012 have been included. (authors)

Nelson, Roger A. [DOE, Carlsbad Field Office, Carlsbad NM (United States); Buschman, Nancy [DOE, Office of Environmental Management, Washington DC (United States)

2012-07-01T23:59:59.000Z

11

MONITORED GEOLOGIC REPOSITORY SYSTEMS REQUIREMENTS DOCUMENT  

SciTech Connect (OSTI)

This document establishes the Monitored Geologic Repository system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are based on the ''Civilian Radioactive Waste Management System Requirements Document'' (CRD) (DOE 2004a). The ''Monitored Geologic Repository Systems Requirements Document'' (MGR-RD) is developed in accordance with LP-3.3 SQ-OCRWM, ''Preparation, Review, and Approval of Office of Repository Development Requirements Document''. As illustrated in Figure 1, the MGR-RD forms part of the DOE Office of Civilian Radioactive Waste Management Technical Requirements Baseline. Revision 0 of this document identifies requirements for the current phase of repository design that is focused on developing a preliminary design for the repository and will be included in the license application submitted to the U.S. Nuclear Regulatory Commission for a repository at Yucca Mountain in support of receiving a construction authorization and subsequent operating license. As additional information becomes available, more detailed requirements will be identified in subsequent revisions to this document.

V. Trebules

2006-06-02T23:59:59.000Z

12

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (CRWMS M&O 2000b) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) engineering design basis in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The engineering design basis documented in the PDD is to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the engineering design basis from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the engineering design basis captured in the SDDs and the design requirements captured in U.S. Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 2-1, the MGR Architecture (Section 4.1),the Engineering Design Bases (Section 5), and the Controlled Project Assumptions (Section 6).

P. Curry

2000-06-01T23:59:59.000Z

13

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).

P. M. Curry

2001-01-30T23:59:59.000Z

14

Cigeo, the French Geological Repository Project - 13022  

SciTech Connect (OSTI)

The Cigeo industrial-scale geological disposal centre is designed for the disposal of the most highly-radioactive French waste. It will be built in an argillite formation of the Callovo-Oxfordian dating back 160 million years. The Cigeo project is located near the Bure village in the Paris Basin. The argillite formation was studied since 1974, and from the Meuse/Haute-Marne underground research laboratory since end of 1999. Most of the waste to be disposed of in the Cigeo repository comes from nuclear power plants and from reprocessing of their spent fuel. (authors)

Labalette, Thibaud; Harman, Alain; Dupuis, Marie-Claude; Ouzounian, Gerald [ANDRA, 1-7, rue Jean Monnet, 92298 Chatenay-Malabry Cedex (France)] [ANDRA, 1-7, rue Jean Monnet, 92298 Chatenay-Malabry Cedex (France)

2013-07-01T23:59:59.000Z

15

Monitored Geologic Repository Project Description Document  

SciTech Connect (OSTI)

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the Yucca Mountain Site Characterization Project Requirements Document (YMP RD) (YMP 2001a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M&O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6).

P. Curry

2001-06-26T23:59:59.000Z

16

Constructing Hydraulic Barriers in Deep Geologic Formations  

SciTech Connect (OSTI)

Many construction methods have been developed to create hydraulic barriers to depths of 30 to 50 meters, but few have been proposed for depths on the order of 500 meters. For these deep hydraulic barriers, most methods are potentially feasible for soil but not for hard rock. In the course of researching methods of isolating large subterranean blocks of oil shale, the authors have developed a wax thermal permeation method for constructing hydraulic barriers in rock to depths of over 500 meters in competent or even fractured rock as well as soil. The technology is similar to freeze wall methods, but produces a permanent barrier; and is potentially applicable in both dry and water saturated formations. Like freeze wall barriers, the wax thermal permeation method utilizes a large number of vertical or horizontal boreholes around the perimeter to be contained. However, instead of cooling the boreholes, they are heated. After heating these boreholes, a specially formulated molten wax based grout is pumped into the boreholes where it seals fractures and also permeates radially outward to form a series of columns of wax-impregnated rock. Rows of overlapping columns can then form a durable hydraulic barrier. These barriers can also be angled above a geologic repository to help prevent influx of water due to atypical rainfall events. Applications of the technique to constructing containment structures around existing shallow waste burial sites and water shutoff for mining are also described. (authors)

Carter, E.E.; Carter, P.E. [Technologies Co, Texas (United States); Cooper, D.C. [Ph.D. Idaho National Laboratory, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

17

GEOLOGY, January 2007 1 GSA Data Repository item 2007010, Figures  

E-Print Network [OSTI]

GEOLOGY, January 2007 1 1 GSA Data Repository item 2007010, Figures DR1A (photo of speleothem PP1 and methods for uranium-series chronology), and DR2, (18 O and 13 C data), is available online at www 9140, Boulder, CO 80301, USA. Geology, January 2007; v. 35; no. 1; p.1­4; doi: 10.1130/G22865A.1; 3

Massachusetts at Amherst, University of

18

Diffusion Dominant Solute Transport Modelling In Deep Repository Under The Effect of Emplacement Media Degradation - 13285  

SciTech Connect (OSTI)

Deep geologic disposal of high activity and long-lived radioactive waste is being actively considered and pursued in many countries, where low permeability geological formations are used to provide long term waste contaminant with minimum impact to the environment and risk to the biosphere. A multi-barrier approach that makes use of both engineered and natural barriers (i.e. geological formations) is often used to further enhance the containment performance of the repository. As the deep repository system subjects to a variety of thermo-hydro-chemo-mechanical (THCM) effects over its long 'operational' lifespan (e.g. 0.1 to 1.0 million years, the integrity of the barrier system will decrease over time (e.g. fracturing in rock or clay)). This is broadly referred as media degradation in the present study. This modelling study examines the effects of media degradation on diffusion dominant solute transport in fractured media that are typical of deep geological environment. In particular, reactive solute transport through fractured media is studied using a 2-D model, that considers advection and diffusion, to explore the coupled effects of kinetic and equilibrium chemical processes, while the effects of degradation is studied using a pore network model that considers the media diffusivity and network changes. Model results are presented to demonstrate the use of a 3D pore-network model, using a novel architecture, to calculate macroscopic properties of the medium such as diffusivity, subject to pore space changes as the media degrade. Results from a reactive transport model of a representative geological waste disposal package are also presented to demonstrate the effect of media property change on the solute migration behaviour, illustrating the complex interplay between kinetic biogeochemical processes and diffusion dominant transport. The initial modelling results demonstrate the feasibility of a coupled modelling approach (using pore-network model and reactive transport model) to examine the long term behaviour of deep geological repositories with media property change under complex geochemical conditions. (authors)

Kwong, S. [National Nuclear Laboratory (United Kingdom)] [National Nuclear Laboratory (United Kingdom); Jivkov, A.P. [Research Centre for Radwaste and Decommissioning and Modelling and Simulation Centre, University of Manchester (United Kingdom)] [Research Centre for Radwaste and Decommissioning and Modelling and Simulation Centre, University of Manchester (United Kingdom)

2013-07-01T23:59:59.000Z

19

SciTech Connect: Deep Borehole Disposal Research: Geological...  

Office of Scientific and Technical Information (OSTI)

Deep Borehole Disposal Research: Geological Data Evaluation Alternative Waste Forms and Borehole Seals Citation Details In-Document Search Title: Deep Borehole Disposal Research:...

20

Adapting Dry Cask Storage for Aging at a Geologic Repository  

SciTech Connect (OSTI)

A Spent Nuclear Fuel (SNF) Aging System is a crucial part of operations at the proposed Yucca Mountain repository in the United States. Incoming commercial SNF that does not meet thermal limits for emplacement will be aged on outdoor pads. U.S. Department of Energy SNF will also be managed using the Aging System. Proposed site-specific designs for the Aging System are closely based upon designs for existing dry cask storage (DCS) systems. This paper evaluates the applicability of existing DCS systems for use in the SNF Aging System at Yucca Mountain. The most important difference between existing DCS facilities and the Yucca Mountain facility is the required capacity. Existing DCS facilities typically have less than 50 casks. The current design for the aging pad at Yucca Mountain calls for a capacity of over 2,000 casks (20,000 MTHM) [1]. This unprecedented number of casks poses some unique problems. The response of DCS systems to off-normal and accident conditions needs to be re-evaluated for multiple storage casks. Dose calculations become more complicated, since doses from multiple or very long arrays of casks can dramatically increase the total boundary dose. For occupational doses, the geometry of the cask arrays and the order of loading casks must be carefully considered in order to meet ALARA goals during cask retrieval. Due to the large area of the aging pad, skyshine must also be included when calculating public and worker doses. The expected length of aging will also necessitate some design adjustments. Under 10 CFR 72.236, DCS systems are initially certified for a period of 20 years [2]. Although the Yucca Mountain facility is not intended to be a storage facility under 10 CFR 72, the operational life of the SNF Aging System is 50 years [1]. Any cask system selected for use in aging will have to be qualified to this design lifetime. These considerations are examined, and a summary is provided of the adaptations that must be made in order to use DCS technologies successfully at a geologic repository.

C. Sanders; D. Kimball

2005-08-02T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Considerations of human inturison in U.S. programs for deep geologic disposal of radioactive waste.  

SciTech Connect (OSTI)

Regulations in the United States that govern the permanent disposal of spent nuclear fuel and high-level radioactive waste in deep geologic repositories require the explicit consideration of hypothetical future human intrusions that disrupt the waste. Specific regulatory requirements regarding the consideration of human intrusion differ in the two sets of regulations currently in effect in the United States; one defined by the Environmental Protection Agency's 40 Code of Federal Regulations part 197, applied only to the formerly proposed geologic repository at Yucca Mountain, Nevada, and the other defined by the Environmental Protection Agency's 40 Code of Federal Regulations part 191, applied to the Waste Isolation Pilot Plant in New Mexico and potentially applicable to any repository for spent nuclear fuel and high-level radioactive waste in the United States other than the proposed repository at Yucca Mountain. This report reviews the regulatory requirements relevant to human intrusion and the approaches taken by the Department of Energy to demonstrating compliance with those requirements.

Swift, Peter N.

2013-01-01T23:59:59.000Z

22

Minor actinide waste disposal in deep geological boreholes  

E-Print Network [OSTI]

The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. ...

Sizer, Calvin Gregory

2006-01-01T23:59:59.000Z

23

Evaluation of Five Sedimentary Rocks Other Than Salt for Geologic Repository Siting Purposes  

SciTech Connect (OSTI)

The US Department of Energy (DOE), in order to increase the diversity of rock types under consideration by the geologic disposal program, initiated the Sedimary ROck Program (SERP), whose immediate objectiv eis to evaluate five types of secimdnary rock - sandstone, chalk, carbonate rocks (limestone and dolostone), anhydrock, and shale - to determine the potential for siting a geologic repository. The evaluation of these five rock types, together with the ongoing salt studies, effectively results in the consideration of all types of relatively impermeable sedimentary rock for repository purposes. The results of this evaluation are expressed in terms of a ranking of the five rock types with respect to their potential to serve as a geologic repository host rock. This comparative evaluation was conducted on a non-site-specific basis, by use of generic information together with rock evaluation criteria (RECs) derived from the DOE siting guidelines for geologic repositories (CFR 1984). An information base relevant to rock evaluation using these RECs was developed in hydrology, geochemistry, rock characteristics (rock occurrences, thermal response, rock mechanics), natural resources, and rock dissolution. Evaluation against postclosure and preclosure RECs yielded a ranking of the five subject rocks with respect to their potential as repository host rocks. Shale was determined to be the most preferred of the five rock types, with sandstone a distant second, the carbonate rocks and anhydrock a more distant third, and chalk a relatively close fourth.

Croff, A.G.; Lomenick, T.F.; Lowrie, R.S.; Stow, S.H.

2003-11-15T23:59:59.000Z

24

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

25

Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea  

E-Print Network [OSTI]

Biogeochemical changes at early stage after the closure of radioactive waste geological repository e Korea Radioactive Waste Agency (KORAD), 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon 305 Organic waste a b s t r a c t Permanent disposal of low- and intermediate-level radioactive wastes

Ohta, Shigemi

26

Biogeochemical Changes at Early Stage After the Closure of Radioactive Waste Geological Repository in South Korea  

SciTech Connect (OSTI)

Permanent disposal of low- and intermediate-level radioactive wastes in the subterranean environment has been the preferred method of many countries, including Korea. A safety issue after the closure of a geological repository is that biodegradation of organic materials due to microbial activities generates gases that lead to overpressure of the waste containers in the repository and its disintegration with the release of radionuclides. As part of an ongoing large-scale in situ experiment using organic wastes and groundwater to simulate geological radioactive waste repository conditions, we investigated the geochemical alteration and microbial activities at an early stage (~63 days) intended to be representative of the initial period after repository closure. The increased numbers of both aerobes and facultative anaerobes in waste effluents indicate that oxygen content could be the most significant parameter to control biogeochemical conditions at very early periods of reaction (<35 days). Accordingly, the values of dissolved oxygen and redox potential were decreased. The activation of anaerobes after 35 days was supported by the increased concentration to ~50 mg L-1 of ethanol. These results suggest that the biogeochemical conditions were rapidly altered to more reducing and anaerobic conditions within the initial 2 months after repository closure. Although no gases were detected during the study, activated anaerobic microbes will play more important role in gas generation over the long term.

Choung, Sungwook [Pohang Univ. of Science and Technology (Korea, Republic of); Um, Wooyong [Pohang Univ. of Science and Technology (Korea, Republic of); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Choi, Seho [Pohang Univ. of Science and Technology (Korea, Republic of); Francis, Arokiasamy J. [Pohang Univ. of Science and Technology (Korea, Republic of); Brookhaven National Laboratory (BNL), Upton, NY (United States); Kim, Sungpyo [Korea Univ., Sejong (Korea, Republic of); Park, Jin beak [Korea Radioactive Waste Agency (KORAD), Daejeon (Korea, Republic of); Kim, Suk-Hoon [FNC Technology Co., Seoul National University (Korea, Republic of)

2014-03-18T23:59:59.000Z

27

Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal  

E-Print Network [OSTI]

1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

28

Limits on the thermal energy release from radioactive wastes in a mined geologic repository  

SciTech Connect (OSTI)

The theraml energy release of nuclear wastes is a major factor in the design of geologic repositories. Thermal limits need to be placed on various aspets of the geologic waste disposal system to avoid or retard the degradation of repository performance because of increased temperatures. The thermal limits in current use today are summarized in this report. These limits are placed in a hierarchial structure of thermal criteria consistent with the failure mechanism they are trying to prevent. The thermal criteria hierarchy is used to evaluate the thermal performance of a sample repository design. The design consists of disassembled BWR spent fuel, aged 10 years, close packed in a carbon steel canister with 15 cm of crushed salt backfill. The medium is bedded salt. The most-restrictive temperature for this design is the spent-fuel centerline temperature limit of 300/sup 0/C. A sensitivity study on the effects of additional cooling prior to disposal on repository thermal limits and design is performed.

Scott, J.A.

1983-03-01T23:59:59.000Z

29

Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $  

E-Print Network [OSTI]

Numerical methods for the simulation of a corrosion model in a nuclear waste deep repository $ C of the French nuclear waste management agency ANDRA, investigations are conducted to optimize and finalize by the Nuclear Waste Management Agency ANDRA Corresponding author. Phone: +49 30 20372 560, Fax: +49 30 2044975

Paris-Sud XI, Université de

30

NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft  

SciTech Connect (OSTI)

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

none,

1982-07-01T23:59:59.000Z

31

TEMP: A finite line heat transfer code for geologic repositories for nuclear waste  

SciTech Connect (OSTI)

TEMP is a FORTRAN computer code for calculating temperatures in a geologic repository for nuclear waste. It will calculate the incremental temperature contributed by a single heat source, by an infinite array of heat sources, or by heat sources geometrically arranged in a finite array. In the finite array geometry, different types of heat sources can be placed in different regions at different times to more closely approximate the emplacement of waste in a repository. TEMP uses a semi-analytical technique for solving the equation for a heat producing finite length line source in an infinite and isotropic medium. Temperature contributions from individual heat sources are superimposed to determine the temperature at a specific location and time in a repository of multiple heat sources. Thermal conductivity of the geologic medium can be a function of temperature, and, when it is, an approximation is made for the temperature dependence of thermal diffusivity. This report derives the equations solved by TEMP and documents its accuracy by comparing its results to known analytical solutions and to the finite-difference and finite-element heat transfer codes HEATING5, HEATING6, THAC-SIP-3D, SPECTROM-41, and STEALTH-2D. The temperature results from TEMP are shown to be very accurate when compared to the analytical solutions and to the results from the finite-difference and finite-element codes. 8 refs., 97 figs., 39 tabs.

Wurm, K.J.; Bloom, S.G.; Atterbury, W.G.; Hetteberg, J.R.

1987-10-01T23:59:59.000Z

32

Assessment of Effectiveness of Geologic Isolation Systems: REFERENCE SITE INITIAL ASSESSMENT FOR A SALT DOME REPOSITORY  

SciTech Connect (OSTI)

As a methodology demonstration for the Office of Nuclear Waste Isolation (ONWI), the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program conducted an initial reference site analysis of the long-term effectiveness of a salt dome repository. The Hainesville Salt Dome in Texas was chosen to be representative of the Gulf Coast interior salt domes; however, the Hainesville Site has been eliminated as a possible nuclear waste repository site. The data used for this exercise are not adequate for an actual assessment, nor have all the parametric analyses been made that would adequately characterize the response of the geosystem surrounding the repository. Additionally, because this was the first exercise of the complete AEGIS and WASTE Rock Interaction Technology (WRIT) methodology, this report provides the initial opportunity for the methodology, specifically applied to a site, to be reviewed by the community outside the AEGIS. The scenario evaluation, as a part of the methodology demonstration, involved consideration of a large variety of potentially disruptive phenomena, which alone or in concert could lead to a breach in a salt dome repository and to a subsequent transport of the radionuclides to the environment. Without waste- and repository-induced effects, no plausible natural geologic events or processes which would compromise the repository integrity could be envisioned over the one-million-year time frame after closure. Near-field (waste- and repository-induced) effects were excluded from consideration in this analysis, but they can be added in future analyses when that methodology development is more complete. The potential for consequential human intrusion into salt domes within a million-year time frame led to the consideration of a solution mining intrusion scenario. The AEGIS staff developed a specific human intrusion scenario at 100 years and 1000 years post-closure, which is one of a whole suite of possible scenarios. This scenario resulted in the delivery of radionuclidecontaminated brine to the surface, where a portion was diverted to culinary salt for direct ingestion by the existing population. Consequence analyses indicated calculated human doses that would be highly deleterious. Additional analyses indicated that doses well above background would occur from such a scenario t even if it occurred a million years into the future. The way to preclude such an intrusion is for continued control over the repository sitet either through direct institutional control or through the effective passive transfer of information. A secondary aspect of the specific human intrusion scenario involved a breach through the side of the salt dome t through which radionuclides migrated via the ground-water system to the accessible environment. This provided a demonstration of the geotransport methodology that AEGIS can use in actual site evaluations, as well as the WRIT program's capabilities with respect to defining the source term and retardation rates of the radionuclides in the repository. This reference site analysis was initially published as a Working Document in December 1979. That version was distributed for a formal peer review by individuals and organizations not involved in its development. The present report represents a revisiont based in part on the responses received from the external reviewers. Summaries of the comments from the reviewers and responses to these comments by the AEGIS staff are presented. The exercise of the AEGIS methodology was sUGcessful in demonstrating the methodologyt and thus t in providing a basis for substantive peer review, in terms of further development of the AEGIS site-applications capability and in terms of providing insight into the potential for consequential human intrusion into a salt dome repository.

Harwell,, M. A.; Brandstetter,, A.; Benson,, G. L.; Raymond,, J. R.; Brandley,, D. J.; Serne,, R. J.; Soldat,, J. K.; Cole,, C. R.; Deutsch,, W. J.; Gupta,, S. K.; Harwell,, C. C.; Napier,, B. A.; Reisenauer,, A. E.; Prater,, L. S.; Simmons,, C. S.; Strenge,, D. L.; Washburn,, J. F.; Zellmer,, J. T.

1982-06-01T23:59:59.000Z

33

Assessment of Effectiveness of Geologic Isolation Systems: REFERENCE SITE INITIAL ASSESSMENT FOR A SALT DOME REPOSITORY  

SciTech Connect (OSTI)

As a methodology demonstration for the Office of Nuclear Waste Isolation (ONWI), the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program conducted an initial reference site analysis of the long-term effectiveness of a salt dome repository. The Hainesville Salt Dome in Texas was chosen to be representative of the Gulf Coast interior salt domes; however, the Hainesville Site has been eliminated as a possible nuclear waste repository site. The data used for this exercise are not adequate for an actual assessment, nor have all the parametric analyses been made that would adequately characterize the response of the geosystem surrounding the repository. Additionally, because this was the first exercise of the complete AEGIS and WASTE Rock Interaction Technology (WRIT) methodology, this report provides the initial opportunity for the methodology, specifically applied to a site, to be reviewed by the community outside the AEGIS. The scenario evaluation, as a part of the methodology demonstration, involved consideration of a large variety of potentially disruptive phenomena, which alone or in concert could lead to a breach in a salt dome repository and to a subsequent transport of the radionuclides to the environment. Without waste- and repository-induced effects, no plausible natural geologic events or processes which would compromise the repository integrity could be envisioned over the one-million-year time frame after closure. Near-field (waste- and repository-induced) effects were excluded from consideration in this analysis, but they can be added in future analyses when that methodology development is more complete. The potential for consequential human intrusion into salt domes within a million-year time frame led to the consideration of a solution mining intrusion scenario. The AEGIS staff developed a specific human intrusion scenario at 100 years and 1000 years post-closure, which is one of a whole suite of possible scenarios. This scenario resulted in the delivery of radionuclidecontaminated brine to the surface, where a portion was diverted to culinary salt for direct ingestion by the existing population. Consequence analyses indicated calculated human doses that would be highly deleterious. Additional analyses indicated that doses well above background would occur from such a scenario t even if it occurred a million years into the future. The way to preclude such an intrusion is for continued control over the repository sitet either through direct institutional control or through the effective passive transfer of information. A secondary aspect of the specific human intrusion scenario involved a breach through the side of the salt dome t through which radionuclides migrated via the ground-water system to the accessible environment. This provided a demonstration of the geotransport methodology that AEGIS can use in actual site evaluations, as well as the WRIT program's capabilities with respect to defining the source term and retardation rates of the radionuclides in the repository. This reference site analysis was initially published as a Working Document in December 1979. That version was distributed for a formal peer review by individuals and organizations not involved in its development. The present report represents a revisiont based in part on the responses received from the external reviewers. Summaries of the comments from the reviewers and responses to these comments by the AEGIS staff are presented. The exercise of the AEGIS methodology was successful in demonstrating the methodologyt and thus t in providing a basis for substantive peer review, in terms of further development of the AEGIS site-applications capability and in terms of providing insight into the potential for consequential human intrusion into a salt dome repository.

Harwell,, M. A.; Brandstetter,, A.; Benson,, G. L.; Bradley,, D. J.; Serne,, R. J.; Soldat, J. K; Cole,, C. R.; Deutsch,, W. J.; Gupta,, S. K.; Harwell,, C. C.; Napier,, B. A.; Reisenauer,, A. E.; Prater,, L. S.; Simmons,, C. S.; Strenge,, D. L.; Washburn,, J. F.; Zellmer,, J. T.

1982-06-01T23:59:59.000Z

34

Performance assessment for the geological disposal of Deep Burn spent fuel using TTBX  

SciTech Connect (OSTI)

The behavior of Deep Burn Modular High Temperature Reactor Spent Fuel (DBSF) is investigated in the Yucca Mountain geological repository (YMR) with respect to the annual dose (Sv/yr) delivered to the Reasonably Maximally Exposed Individual (RMEI) from the transport of radionuclides released from the graphite waste matrix. Transport calculations are performed with a novel computer code, TTBX which is capable of modeling transport pathways that pass through heterogeneous geological formations. TTBX is a multi-region extension of the existing single region TTB transport code. Overall the peak annual dose received by the RMEI is seen to be four orders of magnitude lower than the regulatory threshold for exposure, even under pessimistic scenarios. A number of factors contribute to the favorable performance of DBSF. A reduction of one order of magnitude in the peak annual dose received by the RMEI is observed for every order of magnitude increase in the waste matrix lifetime, highlighting the importance of the waste matrix durability and suggesting graphite's utility as a potential waste matrix for the disposal of high-level waste. Furthermore, we see that by incorporating a higher fidelity far-field model the peak annual dose calculated to be received by the RMEI is reduced by two orders of magnitude. By accounting for the heterogeneities of the far field we have simultaneously removed unnecessary conservatisms and improved the fidelity of the transport model. (authors)

Van den Akker, B.P.; Ahn, J. [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States)

2013-07-01T23:59:59.000Z

35

Viability Assessment of a Repository at Yucca Mountain  

Broader source: Energy.gov [DOE]

The Viability Assessment of a Repository at Yucca Mountain describes the nuclear waste problem and explains why the United States and other nations are considering deep geologic disposal as the solution.

36

GEOLOGY, August 2007 683Geology, August 2007; v. 35; no. 8; p. 683686; doi: 10.1130/G23675A.1; 4 figures; Data Repository item 2007176. 2007 The Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosoci  

E-Print Network [OSTI]

GEOLOGY, August 2007 683Geology, August 2007; v. 35; no. 8; p. 683­686; doi: 10.1130/G23675A.1; 4 figures; Data Repository item 2007176. © 2007 The Geological Society of America. For permission to copy

Demouchy, Sylvie

37

Evaluating variable switching and flash methods in modeling carbon sequestration in deep geologic formations  

E-Print Network [OSTI]

Evaluating variable switching and flash methods in modeling carbon sequestration in deep geologic performance computing to assess the risks involved in carbon sequestration in deep geologic formations-thermal- chemical processes in variably saturated, non-isothermal porous media is applied to sequestration

Mills, Richard

38

Preclosure seismic design methodology for a geologic repository at Yucca Mountain. Topical report YMP/TR-003-NP  

SciTech Connect (OSTI)

This topical report describes the methodology and criteria that the U.S. Department of Energy (DOE) proposes to use for preclosure seismic design of structures, systems, and components (SSCs) of the proposed geologic repository operations area that are important to safety. Title 10 of the Code of Federal Regulations, Part 60 (10 CFR 60), Disposal of High-Level Radioactive Wastes in Geologic Repositories, states that for a license to be issued for operation of a high-level waste repository, the U.S. Nuclear Regulatory Commission (NRC) must find that the facility will not constitute an unreasonable risk to the health and safety of the public. Section 60.131 (b)(1) requires that SSCs important to safety be designed so that natural phenomena and environmental conditions anticipated at the geologic repository operations area will not interfere with necessary safety functions. Among the natural phenomena specifically identified in the regulation as requiring safety consideration are the hazards of ground shaking and fault displacement due to earthquakes.

NONE

1996-10-01T23:59:59.000Z

39

Analysis on the use of engineered barriers for geologic isolation of spent fuel in a reference salt site repository  

SciTech Connect (OSTI)

A perspective on the potential durability and effectiveness requirements for the waste form, container and other engineered barriers for geologic disposal of spent nuclear fuel has been developed. This perspective is based on calculated potential doses to individuals who may be exposed to radioactivity released from a repository via a groundwater transport pathway. These potential dose commitments were calculated with an integrated geosphere transport and bioshpere transport model. A sensitivity analysis was accomplished by varying four important system parameters, namely the waste radionuclide release rate from the repository, the delay prior to groundwater contact with the waste (leach initiation), aquifer flow velocity and flow path length. The nuclide retarding capacity of the geologic media, a major determinant of the isolation effectiveness, was not varied as a parameter but was held constant for a particular reference site. This analysis is limited to looking only at engineered barriers whose net effect is either to delay groundwater contact with the waste form or to limit the rate of release of radionuclides into the groundwater once contact has occurred. The analysis considers only leach incident scenarios, including a water well intrusion into the groundwater near a repository, but does not consider other human intrusion events or catastrophic events. The analysis has so far been applied to a reference salt site repository system and conclusions are presented.Basically, in nearly all cases, the regional geology is the most effective barrier to release of radionuclides to the biosphere; however, for long-lived isotopes of carbon, technetium and iodine, which were poorly sorbed on the geologic media, the geology is not very effective once a leach incident is initiated.

Cloninger, M.O.; Cole, C.R.; Washburn, J.F.

1980-12-01T23:59:59.000Z

40

Continuous Improvement and the Safety Case for the Waste Isolation Pilot Plant Geologic Repository - 13467  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a geologic repository 2150 feet (650 m) below the surface of the Chihuahuan desert near Carlsbad, New Mexico. WIPP permanently disposes of transuranic waste from national defense programs. Every five years, the U.S. Department of Energy (DOE) submits an application to the U.S. Environmental Protection Agency (EPA) to request regulatory-compliance re-certification of the facility for another five years. Every ten years, DOE submits an application to the New Mexico Environment Department (NMED) for the renewal of its hazardous waste disposal permit. The content of the applications made by DOE to the EPA for re-certification, and to the NMED for permit-renewal, reflect any optimization changes made to the facility, with regulatory concurrence if warranted by the nature of the change. DOE points to such changes as evidence for its having taken seriously its 'continuous improvement' operations and management philosophy. Another opportunity for continuous improvement is to look at any delta that may exist between the re-certification and re-permitting cases for system safety and the consensus advice on the nature and content of a safety case as being developed and published by the Nuclear Energy Agency's Integration Group for the Safety Case (IGSC) expert group. DOE at WIPP, with the aid of its Science Advisor and teammate, Sandia National Laboratories, is in the process of discerning what can be done, in a reasonably paced and cost-conscious manner, to continually improve the case for repository safety that is being made to the two primary regulators on a recurring basis. This paper will discuss some aspects of that delta and potential paths forward to addressing them. (authors)

Van Luik, Abraham; Patterson, Russell; Nelson, Roger [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States)] [US Department of Energy, Carlsbad Field Office, 4021 S. National parks Highway, Carlsbad, NM 88220 (United States); Leigh, Christi [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)] [Sandia National Laboratories Carlsbad Operations, 4100 S. National parks Highway, Carlsbad, NM 88220 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

Broader source: Energy.gov [DOE]

This EIS analyzes DOE's proposed action to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain  for the disposal of spent nuclear fuel and high-level...

42

Thermal Performance of Deep-Burn Fusion-Fission Hybrid Waste in a Repository  

SciTech Connect (OSTI)

The Laser Inertial Confinement Fusion Fission Energy (LIFE) Engine [1] combines a neutron-rich but energy-poor inertial fusion system with an energy-rich but neutron-poor subcritical fission blanket. Because approximately 80% of the LIFE Engine energy is produced from fission, the requirements for laser efficiency and fusion target performance are relaxed, compared to a pure-fusion system, and hence a LIFE Engine prototype can be based on target performance in the first few years of operation of the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL). Similarly, because of the copious fusion neutrons, the fission blanket can be run in a subcritical, driven, mode, without the need for control rods or other sophisticated reactivity control systems. Further, because the fission blanket is inherently subcritical, fission fuels that can be used in LIFE Engine designs include thorium, depleted uranium, natural uranium, spent light water reactor fuel, highly enriched uranium, and plutonium. Neither enrichment nor reprocessing is required for the LIFE Engine fuel cycle, and burnups to 99% fraction of initial metal atoms (FIMA) being fissioned are envisioned. This paper discusses initial calculations of the thermal behavior of spent LIFE fuel following completion of operation in the LIFE Engine [2]. The three time periods of interest for thermal calculations are during interim storage (probably at the LIFE Engine site), during the preclosure operational period of a geologic repository, and after closure of the repository.

Blink, J A; Chipman, V; Farmer, J; Shaw, H; Zhao, P

2008-11-25T23:59:59.000Z

43

Geology of the Yucca Mountain Region, Chapter in Stuckless, J.S., ED., Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste  

SciTech Connect (OSTI)

Yucca Mountain has been proposed as the site for the Nation's first geologic repository for high-level radioactive waste. This chapter provides the geologic framework for the Yucca Mountain region. The regional geologic units range in age from late Precambrian through Holocene, and these are described briefly. Yucca Mountain is composed dominantly of pyroclastic units that range in age from 11.4 to 15.2 Ma. The proposed repository would be constructed within the Topopah Spring Tuff, which is the lower of two major zoned and welded ash-flow tuffs within the Paintbrush Group. The two welded tuffs are separated by the partly to nonwelded Pah Canyon Tuff and Yucca Mountain Tuff, which together figure prominently in the hydrology of the unsaturated zone. The Quaternary deposits are primarily alluvial sediments with minor basaltic cinder cones and flows. Both have been studied extensively because of their importance in predicting the long-term performance of the proposed repository. Basaltic volcanism began about 10 Ma and continued as recently as about 80 ka with the eruption of cones and flows at Lathrop Wells, approximately 10 km south-southwest of Yucca Mountain. Geologic structure in the Yucca Mountain region is complex. During the latest Paleozoic and Mesozoic, strong compressional forces caused tight folding and thrust faulting. The present regional setting is one of extension, and normal faulting has been active from the Miocene through to the present. There are three major local tectonic domains: (1) Basin and Range, (2) Walker Lane, and (3) Inyo-Mono. Each domain has an effect on the stability of Yucca Mountain.

J.S. Stuckless; D. O'Leary

2006-09-25T23:59:59.000Z

44

GEOLOGY, July 2007 623Geology, July 2007; v. 35; no. 7; p. 623626; doi: 10.1130/G23531A.1; 3 figures; Data Repository item 2007165. 2007 The Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.  

E-Print Network [OSTI]

GEOLOGY, July 2007 623Geology, July 2007; v. 35; no. 7; p. 623­626; doi: 10.1130/G23531A.1; 3 figures; Data Repository item 2007165. © 2007 The Geological Society of America. For permission to copy and Hole 1275D in conjunction with geophysical and geological mapping data. Although the mechanisms

Demouchy, Sylvie

45

Assessment of effectiveness of geologic isolation systems. Test case release consequence analysis for a spent fuel repository in bedded salt  

SciTech Connect (OSTI)

Geologic and geohydrologic data for the Paradox Basin have been used to simulate movement of ground water and radioacrtive contaminants from a hypothetical nuclear reactor spent fuel repository after an assumed accidental release. The pathlines, travel times and velocity of the ground water from the repository to the discharge locale (river) were determined after the disruptive event by use of a two-dimensional finite difference hydrologic model. The concentration of radioactive contaminants in the ground water was calculated along a series of flow tubes by use of a one-dimensional mass transport model which takes into account convection, dispersion, contaminant/media interactions and radioactive decay. For the hypothetical site location and specific parameters used in this demonstration, it is found that Iodine-129 (I-129) is tthe only isotope reaching the Colorado River in significant concentration. This concentration occurs about 8.0 x 10/sup 5/ years after the repository has been breached. This I-129 ground-water concentration is about 0.3 of the drinking water standard for uncontrolled use. The groundwater concentration would then be diluted by the Colorado River. None of the actinide elements reach more than half the distance from the repository to the Colorado River in the two-million year model run time. This exercise demonstrates that the WISAP model system is applicable for analysis of contaminant transport. The results presented in this report, however, are valid only for one particular set of parameters. A complete sensitivity analysis must be performed to evaluate the range of effects from the release of contaminants from a breached repository.

Raymond, J.R.; Bond, F.W.; Cole, C.R.; Nelson, R.W.; Reisenauer, A.E.; Washburn, J.F.; Norman, N.A.; Mote, P.A.; Segol, G.

1980-01-01T23:59:59.000Z

46

AEGIS technology demonstration for a nuclear waste repository in basalt. Assessment of effectiveness of geologic isolation systems  

SciTech Connect (OSTI)

A technology demonstration of current performance assessment techniques as applied to a nuclear waste repository in the Columbia Plateau Basalts was conducted. Hypothetical repository coordinates were selected for an actual geographical setting on the Hanford Reservation in the state of Washington. Published hydrologic and geologic data used in the analyses were gathered in 1979 or earlier. The following report documents the technology demonstration in basalt. Available information has been used to establish the data base and initial hydrologic and geologic interpretations for this site-specific application. A simplified diagram of the AEGIS analyses is shown. Because an understanding of the dynamics of ground-water flow is essential to the development of release scenarios and consequence analyses, a key step in the demonstration is the systems characterization contained in the conceptual model. Regional and local ground-water movement patterns have been defined with the aid of hydrologic computer models. Hypothetical release scenarios have been developed and evaluated by a process involving expert opinion and a Geologic Simulation Model for basalt. (The Geologic Simulation Model can also be used to forecast future boundary conditions for the hydrologic simulation.) Chemical reactivity of the basalt with ground water will influence the leaching and transport of radionuclides; solubility equilibria based on available data are estimated with geochemical models. After the radionuclide concentrations are mathematically introduced into the ground-water movement patterns, waste movement patterns are outlined over elapsed time. Contaminant transport results are summarized for significant radionuclides that are hypothetically released to the accessible environment and to the biosphere.

Dove, F.H.; Cole, C.R.; Foley, M.G.

1982-09-01T23:59:59.000Z

47

Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

SciTech Connect (OSTI)

The purpose of this environmental impact statement (EIS) is to provide information on potential environmental impacts that could result from a Proposed Action to construct, operate and monitor, and eventually close a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at the Yucca Mountain site in Nye County, Nevada. The EIS also provides information on potential environmental impacts from an alternative referred to as the No-Action Alternative, under which there would be no development of a geologic repository at Yucca Mountain.

N /A

2002-10-25T23:59:59.000Z

48

Generic Deep Geologic Disposal Safety Case | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeatMulti-Dimensional Subject: Guidance for naturalGeneral Service LED LampsDeep

49

Draft Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

SciTech Connect (OSTI)

The Proposed Action addressed in this EIS is to construct, operate and monitor, and eventually close a geologic repository at Yucca Mountain in southern Nevada for the disposal of spent nuclear fuel and high-level radioactive waste currently in storage at 72 commercial and 5 DOE sites across the United States. The EIS evaluates (1) projected impacts on the Yucca Mountain environment of the construction, operation and monitoring, and eventual closure of the geologic repository; (2) the potential long-term impacts of repository disposal of spent nuclear fuel and high-level radioactive waste; (3) the potential impacts of transporting these materials nationally and in the State of Nevada; and (4) the potential impacts of not proceeding with the Proposed Action.

N /A

1999-08-13T23:59:59.000Z

50

Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1) Introduction  

SciTech Connect (OSTI)

Yucca Mountain in Nevada represents the proposed solution to what has been a lengthy national effort to dispose of high-level radioactive waste, waste which must be isolated from the biosphere for tens of thousands of years. This chapter reviews the background of that national effort and includes some discussion of international work in order to provide a more complete framework for the problem of waste disposal. Other chapters provide the regional geologic setting, the geology of the Yucca Mountain site, the tectonics, and climate (past, present, and future). These last two chapters are integral to prediction of long-term waste isolation.

R.A. Levich; J.S. Stuckless

2006-09-25T23:59:59.000Z

51

Radiological Aspects of Deep-Burn Fusion-Fission Hybrid Waste in a Repository  

SciTech Connect (OSTI)

The quantity, radioactivity, and isotopic characteristics of the spent fission fuel from a hybrid fusion-fission system capable of extremely high burnups are described. The waste generally has higher activity per unit mass of heavy metal, but much lower activity per unit energy generated. The very long-term radioactivity is dominated by fission products. Simple scaling calculations suggest that the dose from a repository containing such waste would be dominated by {sup 129}I, {sup 135}Cs, and {sup 242}Pu. Use of such a system for generating energy would greatly reduce the need for repository capacity.

Shaw, H F; Blink, J A; Farmer, J C; Karmer, K J; Latkowski, J F; Zhao, P

2008-11-25T23:59:59.000Z

52

Status of Proposed Repository for Latin-American Spent Fuel  

SciTech Connect (OSTI)

This report compiles preliminary information that supports the premise that a repository is needed in Latin America and analyzes the nuclear situation (mainly in Argentina and Brazil) in terms of nuclear capabilities, inventories, and regional spent-fuel repositories. The report is based on several sources and summarizes (1) the nuclear capabilities in Latin America and establishes the framework for the need of a permanent repository, (2) the International Atomic Energy Agency (IAEA) approach for a regional spent-fuel repository and describes the support that international institutions are lending to this issue, (3) the current situation in Argentina in order to analyze the Argentinean willingness to find a location for a deep geological repository, and (4) the issues involved in selecting a location for the repository and identifies a potential location. This report then draws conclusions based on an analysis of this information. The focus of this report is mainly on spent fuel and does not elaborate on other radiological waste sources.

Ferrada, J.J.

2004-10-04T23:59:59.000Z

53

EIS-0250-S1: Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada  

Broader source: Energy.gov [DOE]

The Proposed Action defined in the Yucca Mountain FEIS is to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain to dispose of spent nuclear fuel and high-level radioactive waste. The Proposed Action includes transportation of these materials from commercial and DOE sites to the repository.

54

Potential role of ABC-assisted repositories in U.S. plutonium and high-level waste disposition  

SciTech Connect (OSTI)

This paper characterizes the issues involving deep geologic disposal of LWR spent fuel rods, then presents results of an investigation to quantify the potential role of Accelerator-Based Conversion (ABC) in an integrated national nuclear materials and high level waste disposition strategy. The investigation used the deep geological repository envisioned for Yucca Mt., Nevada as a baseline and considered complementary roles for integrated ABC transmutation systems. The results indicate that although a U.S. geologic waste repository will continue to be required, waste partitioning and accelerator transmutation of plutonium, the minor actinides, and selected long-lived fission products can result in the following substantial benefits: plutonium burndown to near zero levels, a dramatic reduction of the long term hazard associated with geologic repositories, an ability to place several-fold more high level nuclear waste in a single repository, electricity sales to compensate for capital and operating costs.

Berwald, David; Favale, Anthony; Myers, Timothy; McDaniel, Jerry [Grumman Aerospace Corporation, Bethpage New York 11714 (United States); Bechtel Corporation, 50 Beal St., San Francisco, California 94105 (United States)

1995-09-15T23:59:59.000Z

55

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

SciTech Connect (OSTI)

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

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

1998-10-01T23:59:59.000Z

56

OPERATION OF A PUBLIC GEOLOGIC CORE AND SAMPLE REPOSITORY IN HOUSTON, TEXAS  

SciTech Connect (OSTI)

The Bureau of Economic Geology's Houston Research Center (HRC) is well established as a premier regional research center for geologic research serving not only Houston, but geoscientists from around Texas, the U. S., and even the world. As reported in the 2003-2004 technical progress report to the DOE, the HRC provides a state-of-the-art core viewing facility, two fully equipped conference rooms, and a comprehensive technical library, all available for public use. In addition, the HRC currently houses over 500,000 boxes of rock material, and has space to hold approximately 400,000 more boxes. Use of the facility has continued to increase during this third year of operation; over the past twelve months the HRC has averaged approximately 200 patrons per month. This usage is a combination of individuals describing core, groups of geoscientists holding seminars and workshops, and various industry and government-funded groups holding short courses, workshops, and seminars. The BEG/HRC secured several substantial donations of rock materials and/or cash during this operating period. All of these funds went directly into the endowment. Outreach during 2004 and 2005 included many technical presentations and several publications on the HRC. Several field trips to the facility were held for geoscience professionals and grade school students alike. Goals for the upcoming year involve securing more donations of rock material and cash in order to fully fund the HRC endowment. BEG will also continue to increase the number of patrons using the facility, and we will strive to raise awareness of the HRC's 100,000-volume geoscience technical library.

Scott W. Tinker; Beverly Blakeney DeJarnett; Laura C. Zahm

2005-04-01T23:59:59.000Z

57

Report to Congress on the potential use of lead in the waste packages for a geologic repository at Yucca Mountain, Nevada  

SciTech Connect (OSTI)

In the Report of the Senate Committee on Appropriations accompanying the Energy and Water Appropriation Act for 1989, the Committee directed the Department of Energy (DOE) to evaluate the use of lead in the waste packages to be used in geologic repositories for spent nuclear fuel and high-level waste. The evaluation that was performed in response to this directive is presented in this report. This evaluation was based largely on a review of the technical literature on the behavior of lead, reports of work conducted in other countries, and work performed for the waste-management program being conducted by the DOE. The initial evaluation was limited to the potential use of lead in the packages to be used in the repository. Also, the focus of this report is post closure performance and not on retrievability and handling aspects of the waste package. 100 refs., 8 figs., 15 tabs.

NONE

1989-12-01T23:59:59.000Z

58

Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories  

SciTech Connect (OSTI)

The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

Not Available

1983-06-01T23:59:59.000Z

59

MANAGING THE RISKS IN THE VADOSE ZONE ASSOCIATED WITH THE LEAKAGE OF CO2 FROM A DEEP GEOLOGICAL STORAGE  

E-Print Network [OSTI]

-term storage (depleted natural gas and oil fields, deep aquifers and unmineable coal seams). CO2 is injected correspond to a storage reservoir depth of about 800 m (Law et al., 1996). Since the 1990's, the CCS" in case of "abnormal behaviour" of the reservoir has been outlined by the European directive on geological

Paris-Sud XI, Université de

60

Cost analysis of German waste repositories  

SciTech Connect (OSTI)

In forecasting costs of final disposal for radioactive waste, the determined disposal concept and operational aspects such as the necessary amount for personnel to operate the repository are important. Even for the German deep geological concept, there are large differences resulting from the assessment to select an already existing mine or a completely new formation as a disposal site. Based on actual planning, the expected total costs of the running waste repository projects in the Federal Republic of Germany are presented including their distribution to single aspects like project management, underground investigation, licensing work and construction. Moreover, the actual expenditures for the different waste repositories are given and as far as possible the prices per m{sup 3}.

Berg, H.P.; Debski, H.J. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Comparison of potential radiological consequences from a spent-fuel repository and natural uranium deposits  

SciTech Connect (OSTI)

A general criterion has been suggested for deep geological repositories containing spent fuel - the repositories should impose no greater radiological risk than due to naturally occurring uranium deposits. The following analysis investigates the rationale of that suggestion and determines whether current expectations of spent-fuel repository performance are consistent with such a criterion. In this study, reference spent-fuel repositories were compared to natural uranium-ore deposits. Comparisons were based on intrinsic characteristics, such as radionuclide inventory, depth, proximity to aquifers, and regional distribution, and actual and potential radiological consequences that are now occurring from some ore deposits and that may eventually occur from repositories and other ore deposits. The comparison results show that the repositories are quite comparable to the natural ore deposits and, in some cases, present less radiological hazard than their natural counterparts. On the basis of the first comparison, placing spent fuel in a deep geologic repository apparently reduces the hazard from natural radioactive materials occurring in the earth's crust by locating the waste in impermeable strata without access to oxidizing conditions. On the basis of the second comparison, a repository constructed within reasonable constraints presents no greater hazard than a large ore deposit. It is recommended that if the naturally radioactive environment is to be used as a basis for a criterion regarding repositories, then this criterion should be carefully constructed. The criterion should be based on the radiological quality of the waters in the immediate region of a specific repository, and it should be in terms of an acceptable potential increase in the radiological content of those waters due to the existence of the repository.

Wick, O.J.; Cloninger, M.O.

1980-09-01T23:59:59.000Z

62

Applying insights from repository safety assessments.  

SciTech Connect (OSTI)

Despite decades of international consensus that deep geological disposal is the best option for permanent management of long-lived high-level radioactive wastes, no repositories for used nuclear fuel or high-level waste are in operation. Detailed long-term safety assessments have been completed worldwide for a wide range of repository designs and disposal concepts, however, and valuable insights from these assessments are available to inform future decisions about managing radioactive wastes. Qualitative comparisons among the existing safety assessments for disposal concepts in clay, granite, salt, and unsaturated volcanic tuff show how different geologic settings can be matched with appropriate engineered barrier systems to provide a high degree of confidence in the long-term safety of geologic disposal. Review of individual assessments provides insights regarding the release pathways and radionuclides that are most likely to contribute to estimated doses to humans in the far future for different disposal concepts, and can help focus research and development programs to improve management and disposal technologies. Lessons learned from existing safety assessments may be particularly relevant for informing decisions during the process of selecting potential repository sites.

Swift, Peter N.

2010-03-01T23:59:59.000Z

63

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 1. Main report  

SciTech Connect (OSTI)

Evaluation of the geologic isolation of radioactive materials from the biosphere requires an intimate knowledge of site geologic conditions, which is gained through precharacterization and site characterization studies. This report presents the results of an intensive literature review, analysis and compilation to delineate the information needs, applicable techniques and evaluation criteria for programs to adequately characterize a site in six geologic media. These media, in order of presentation, are: granite, shale, basalt, tuff, bedded salt and dome salt. Guidelines are presented to assess the efficacy (application, effectiveness, and resolution) of currently used exploratory and testing techniques for precharacterization or characterization of a site. These guidelines include the reliability, accuracy and resolution of techniques deemed acceptable, as well as cost estimates of various field and laboratory techniques used to obtain the necessary information. Guidelines presented do not assess the relative suitability of media. 351 refs., 10 figs., 31 tabs.

NONE

1985-05-01T23:59:59.000Z

64

Lessons Learned from Natural and Industrial Analogues for Storage of Carbon Dioxide in Deep Geological Formations  

E-Print Network [OSTI]

reservoirs: abandoned and producing oil and gas reservoirs,geological reservoirs, including abandoned and producing oiloil and/or gas reservoir; Salt: Salt dome or bedded salt; Coal: Abandoned

Benson, Sally M.; Hepple, Robert; Apps, John; Tsang, Chin-Fu; Lippmann, Marcelo

2002-01-01T23:59:59.000Z

65

EIS-0250-S2: Supplemental EIS for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada- Nevada Rail Transportation Corridor  

Broader source: Energy.gov [DOE]

This SEIS is to evaluate the potential environmental impacts of constructing and operating a railroad for shipments of spent nuclear fuel and high-level radioactive waste from an existing rail line in Nevada to a geologic repository at Yucca Mountain. The purpose of the evaluation is to assist the Department in deciding whether to construct and operate a railroad in Nevada, and if so, in which corridor and along which specific alignment within the selected corridor.

66

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

SciTech Connect (OSTI)

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

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

1998-10-01T23:59:59.000Z

67

Development of Earthquake Ground Motion Input for Preclosure Seismic Design and Postclosure Performance Assessment of a Geologic Repository at Yucca Mountain, NV  

SciTech Connect (OSTI)

This report describes a site-response model and its implementation for developing earthquake ground motion input for preclosure seismic design and postclosure assessment of the proposed geologic repository at Yucca Mountain, Nevada. The model implements a random-vibration theory (RVT), one-dimensional (1D) equivalent-linear approach to calculate site response effects on ground motions. The model provides results in terms of spectral acceleration including peak ground acceleration, peak ground velocity, and dynamically-induced strains as a function of depth. In addition to documenting and validating this model for use in the Yucca Mountain Project, this report also describes the development of model inputs, implementation of the model, its results, and the development of earthquake time history inputs based on the model results. The purpose of the site-response ground motion model is to incorporate the effects on earthquake ground motions of (1) the approximately 300 m of rock above the emplacement levels beneath Yucca Mountain and (2) soil and rock beneath the site of the Surface Facilities Area. A previously performed probabilistic seismic hazard analysis (PSHA) (CRWMS M&O 1998a [DIRS 103731]) estimated ground motions at a reference rock outcrop for the Yucca Mountain site (Point A), but those results do not include these site response effects. Thus, the additional step of applying the site-response ground motion model is required to develop ground motion inputs that are used for preclosure and postclosure purposes.

I. Wong

2004-11-05T23:59:59.000Z

68

Regional Examples of Geological Settings for Nuclear Waste Disposal in Deep Boreholes  

E-Print Network [OSTI]

This report develops and exercises broad-area site selection criteria for deep boreholes suitable for disposal of spent nuclear fuel and/or its separated constituents. Three candidates are examined: a regional site in the ...

Sapiie, B.

69

Estimating the supply and demand for deep geologic CO2 storage capacity over the course of the 21st Century: A meta-analysis of the literature  

SciTech Connect (OSTI)

Whether there is sufficient geologic CO2 storage capacity to allow CCS to play a significant role in mitigating climate change has been the subject of debate since the 1990s. This paper presents a meta- analysis of a large body of recently published literature to derive updated estimates of the global deep geologic storage resource as well as the potential demand for this geologic CO2 storage resource over the course of this century. This analysis reveals that, for greenhouse gas emissions mitigation scenarios that have end-of-century atmospheric CO2 concentrations of between 350 ppmv and 725 ppmv, the average demand for deep geologic CO2 storage over the course of this century is between 410 GtCO2 and 1,670 GtCO2. The literature summarized here suggests that -- depending on the stringency of criteria applied to calculate storage capacity – global geologic CO2 storage capacity could be: 35,300 GtCO2 of “theoretical” capacity; 13,500 GtCO2 of “effective” capacity; 3,900 GtCO2, of “practical” capacity; and 290 GtCO2 of “matched” capacity for the few regions where this narrow definition of capacity has been calculated. The cumulative demand for geologic CO2 storage is likely quite small compared to global estimates of the deep geologic CO2 storage capacity, and therefore, a “lack” of deep geologic CO2 storage capacity is unlikely to be an impediment for the commercial adoption of CCS technologies in this century.

Dooley, James J.

2013-08-05T23:59:59.000Z

70

Modelling and Numerical Simulation of Gas Migration in a Nuclear Waste Repository  

E-Print Network [OSTI]

We present a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological radioactive waste repository. This model includes capillary effects and the gas diffusivity. The choice of the main variables in this model, Total or Dissolved Hydrogen Mass Concentration and Liquid Pressure, leads to a unique and consistent formulation of the gas phase appearance and disappearance. After introducing this model, we show computational evidences of its adequacy to simulate gas phase appearance and disappearance in different situations typical of underground radioactive waste repository.

Bourgeat, Alain; Smai, Farid

2010-01-01T23:59:59.000Z

71

20 y 50 y 500 y Geological characterization of the TEEP study area is based on the examination of two deep wells,  

E-Print Network [OSTI]

Geological characterization of the TEEP study area is based on the examination of two deep by 360 km2) structural basin, bounded by the Big Horn Mountains and Casper Arch on the west, Miles City to the south, located in northeast Wyoming and eastern The Two Elk Energy Park (TEEP) is a commercialscale

Stanford University

72

Summary of four release consequence analyses for hypothetical nuclear waste repositories in salt and granite  

SciTech Connect (OSTI)

Release consequence methology developed under the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) program has now been applied to four hypothetical repository sites. This paper summarizes the results of these four studies in order to demonstrate that the far-field methodology developed under the AEGIS program offers a practical approach to the post-closure safety assessment of nuclear waste repositories sited in deep continental geologic formations. The four studies are briefly described and compared according to the following general categories: physical description of the repository (size, inventory, emplacement depth); geologic and hydrologic description of the site and the conceptual hydrologic model for the site; description of release scenario; hydrologic model implementation and results; engineered barriers and leach rate modeling; transport model implementation and results; and dose model implementation and results. These studies indicate the following: numerical modeling is a practical approach to post-closure safety assessment analysis for nuclear waste repositories; near-field modeling capability needs improvement to permit assessment of the consequences of human intrusion and pumping well scenarios; engineered barrier systems can be useful in mitigating consequences for postulated release scenarios that short-circuit the geohydrologic system; geohydrologic systems separating a repository from the natural biosphere discharge sites act to mitigate the consequences of postulated breaches in containment; and engineered barriers of types other than the containment or absorptive type may be useful.

Cole, C.R.; Bond, F.W.

1980-12-01T23:59:59.000Z

73

Development of an object-oriented simulation code for repository performance assessment  

SciTech Connect (OSTI)

As understanding for mechanisms of radioactivity confinement by a deep geologic repository improves at the individual process level, it has become imperative to evaluate consequences of individual processes to the performance of the whole repository system. For this goal, the authors have developed a model for radionuclide transport in, and release from, the repository region by incorporating multiple-member decay chains and multiple waste canisters. A computer code has been developed with C++, an object-oriented language. By utilizing the feature that a geologic repository consists of thousands of objects of the same kind, such as the waste canister, the repository region is divided into multiple compartments and objects for simulation of radionuclide transport. Massive computational tasks are distributed over, and executed by, multiple networked workstations, with the help of parallel virtual machine (PVM) technology. Temporal change of the mass distribution of 28 radionuclides in the repository region for the time period of 100 million yr has been successfully obtained by the code.

Tsujimoto, Keiichi; Ahn, J.

1999-07-01T23:59:59.000Z

74

Leveraging Regional Exploration to Develop Geologic Framework for CO2 Storage in Deep Formations in Midwestern United States  

SciTech Connect (OSTI)

Obtaining subsurface data for developing a regional framework for geologic storage of CO{sub 2} can require drilling and characterization in a large number of deep wells, especially in areas with limited pre-existing data. One approach for achieving this objective, without the prohibitive costs of drilling costly standalone test wells, is to collaborate with the oil and gas drilling efforts in a piggyback approach that can provide substantial cost savings and help fill data gaps in areas that may not otherwise get characterized. This leveraging with oil/gas drilling also mitigates some of the risk involved in standalone wells. This collaborative approach has been used for characterizing in a number of locations in the midwestern USA between 2005 and 2009 with funding from U.S. Department of Energy's National Energy Technology Laboratory (DOE award: DE-FC26-05NT42434) and in-kind contributions from a number of oil and gas operators. The results are presented in this final technical report. In addition to data collected under current award, selected data from related projects such as the Midwestern Regional Carbon Sequestration Partnership (MRCSP), the Ohio River Valley CO{sub 2} storage project at and near the Mountaineer Plant, and the drilling of the Ohio Stratigraphic well in Eastern Ohio are discussed and used in the report. Data from this effort are also being incorporated into the MRCSP geologic mapping. The project activities were organized into tracking and evaluation of characterization opportunities; participation in the incremental drilling, basic and advanced logging in selected wells; and data analysis and reporting. Although a large number of opportunities were identified and evaluated, only a small subset was carried into the field stage. Typical selection factors included reaching an acceptable agreement with the operator, drilling and logging risks, and extent of pre-existing data near the candidate wells. The region of study is primarily along the Ohio River Valley corridor in the Appalachian Basin, which underlies large concentrations of CO{sub 2} emission sources. In addition, some wells in the Michigan basin are included. Assessment of the geologic and petrophysical properties of zones of interest has been conducted. Although a large number of formations have been evaluated across the geologic column, the primary focus has been on evaluating the Cambrian sandstones (Mt. Simon, Rose Run, Kerbel) and carbonates layers (Knox Dolomite) as well as on the Silurian-Devonian carbonates (Bass Island, Salina) and sandstones (Clinton, Oriskany, Berea). Factors controlling the development of porosity and permeability, such as the depositional setting have been explored. In northern Michigan the Bass Islands Dolomite appears to have favorable reservoir development. In west central Michigan the St. Peter sandstone exhibits excellent porosity in the Hart and Feuring well and looks promising. In Southeastern Kentucky in the Appalachian Basin, the Batten and Baird well provided valuable data on sequestration potential in organic shales through adsorption. In central and eastern Ohio and western West Virginia, the majority of the wells provided an insight to the complex geologic framework of the relatively little known Precambrian through Silurian potential injection targets. Although valuable data was acquired and a number of critical data gaps were filled through this effort, there are still many challenges ahead and questions that need answered. The lateral extent to which favorable potential injection conditions exist in most reservoirs is still generally uncertain. The prolongation of the characterization of regional geologic framework through partnership would continue to build confidence and greatly benefit the overall CO{sub 2} sequestration effort.

Neeraj Gupta

2009-09-30T23:59:59.000Z

75

Repository Performance Confirmation - 12119  

SciTech Connect (OSTI)

Repository performance confirmation links the technical bases of repository science and societal acceptance. Among the countless aspects of monitoring, performance confirmation holds a special place, involving distinct activities combining technical and social significance in radioactive waste management. Discussion is divided into four themes: 1. A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives, 2. A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain, 3. A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant, and 4. An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. Experience from two repository programs in the United States sheds light on how performance confirmation has been executed. Lessons learned can help the next generation of performance confirmation. (author)

Hansen, F.D. [Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States)

2012-07-01T23:59:59.000Z

76

MINNESOTA GEOLOGICAL SURVEY Harvey Thorleifson, Director  

E-Print Network [OSTI]

for geologic carbon sequestration in the Midcontinent Rift System in Minnesota, Minnesota Geological Survey IN THE MIDCONTINENT RIFT SYSTEM OF MINNESOTA : ASSESSMENT OF POTENTIAL FOR DEEP GEOLOGIC SEQUESTRATION OF CARBONMINNESOTA GEOLOGICAL SURVEY Harvey Thorleifson, Director POTENTIAL CAPACITY FOR GEOLOGIC CARBON

77

Nuclear waste repository transparency technology test bed demonstrations at WIPP  

SciTech Connect (OSTI)

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

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

2000-01-27T23:59:59.000Z

78

Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository  

E-Print Network [OSTI]

We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

Alain Bourgeat; Mladen Jurak; Farid Smaï

2008-02-29T23:59:59.000Z

79

Two phase partially miscible flow and transport modeling in porous media: application to gas migration in a nuclear waste repository  

E-Print Network [OSTI]

We derive a compositional compressible two-phase, liquid and gas, flow model for numerical simulations of hydrogen migration in deep geological repository for radioactive waste. This model includes capillary effects and the gas high diffusivity. Moreover, it is written in variables (total hydrogen mass density and liquid pressure) chosen in order to be consistent with gas appearance or disappearance. We discuss the well possedness of this model and give some computational evidences of its adequacy to simulate gas generation in a water saturated repository.

Bourgeat, Alain; Smaï, Farid

2008-01-01T23:59:59.000Z

80

Monitoring the Long-Term Safety Performance of a Repository for Used Nuclear Fuel - 12294  

SciTech Connect (OSTI)

The nuclear waste management programs of several nations include plans for the design, construction and operation of deep geological repositories. Some of these programs have initiated the licensing process for their repository designs. Monitoring strategies and systems are at different levels of development in each program and there is common ground with respect to the ultimate goal of the monitoring function. In this context, the primary functions of a monitoring system are considered to be the verification of safety performance and making available information that may be required for implementation of future decisions such as the timing of repository decommissioning and closure or the possible retrieval of waste containers. This study examines some of the relevant issues and outlines a conceptual monitoring system for further study and development during implementation of Adaptive Phased Management, the method selected by the Government of Canada for long-term management of used nuclear fuel. (author)

Villagran, J.E. [Nuclear Waste Management Organization, Toronto (Canada)

2012-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

2001 Geological Society of America. For permission to copy, contact Copyright Clearance Center at www.copyright.com or (978) 750-8400. Geology; September 2001; v. 29; no. 9; p. 803806; 4 figures; Data Repository item 2001091. 803  

E-Print Network [OSTI]

. Radiogenic hydrothermal carbonate can form from these solutions and later weather, releasing silicate Sr; Data Repository item 2001091. 803 Hydrothermal source of radiogenic Sr to Himalayan rivers Matthew J of hydrothermal water ( 1% of total river discharge) have a significant impact on the solute chemistry

Derry, Louis A.

82

Panel Organization 1. Panel on Structural Geology & Geoengineering  

E-Print Network [OSTI]

Appendix A Panel Organization 1. Panel on Structural Geology & Geoengineering Chair: Dr. Clarence R Technical Exchange (open) Panel on Structural Geology & Geoengineering Denver, Colorado Topic: DOE & Performance Analysis and the Panel on Structural Geology & Geoengineering Denver, Colorado Topic: Repository

83

MRS/IS facility co-located with a repository: preconceptual design and life-cycle cost estimates  

SciTech Connect (OSTI)

A program is described to examine the various alternatives for monitored retrievable storage (MRS) and interim storage (IS) of spent nuclear fuel, solidified high-level waste (HLW), and transuranic (TRU) waste until appropriate geologic repository/repositories are available. The objectives of this study are: (1) to develop a preconceptual design for an MRS/IS facility that would become the principal surface facility for a deep geologic repository when the repository is opened, (2) to examine various issues such as transportation of wastes, licensing of the facility, and environmental concerns associated with operation of such a facility, and (3) to estimate the life cycle costs of the facility when operated in response to a set of scenarios which define the quantities and types of waste requiring storage in specific time periods, which generally span the years from 1990 until 2016. The life cycle costs estimated in this study include: the capital expenditures for structures, casks and/or drywells, storage areas and pads, and transfer equipment; the cost of staff labor, supplies, and services; and the incremental cost of transporting the waste materials from the site of origin to the MRS/IS facility. Three scenarios are examined to develop estimates of life cycle costs of the MRS/IS facility. In the first scenario, HLW canisters are stored, starting in 1990, until the co-located repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at various intervals. In the second scenario, spent fuel is stored, starting in 1990, because the reprocessing plants are delayed in starting operations by 10 years, but no HLW is stored because the repositories open on schedule. In the third scenario, HLW is stored, starting in 1990, because the repositories are delayed 10 years, but the reprocessing plants open on schedule.

Smith, R.I.; Nesbitt, J.F.

1982-11-01T23:59:59.000Z

84

Reference repository design concept for bedded salt  

SciTech Connect (OSTI)

A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood.

Carpenter, D.W.; Martin, R.W.

1980-10-08T23:59:59.000Z

85

Status of LANL investigations of temperature constraints on clay in repository environments  

SciTech Connect (OSTI)

The Used Fuel Disposition (UFD) Campaign is presently evaluating various generic options for disposal of used fuel. The focus of this experimental work is to characterize and bound Engineered Barrier Systems (EBS) conditions in high heat load repositories. The UFD now has the ability to evaluate multiple EBS materials, waste containers, and rock types at higher heat loads and pressures (including deep boreholes). The geologic conditions now available to the U.S.A. and the international community for repositories include saturated and reduced water conditions, along with higher pressure and temperature (P, T) regimes. Chemical and structural changes to the clays, in either backfill/buffer or clay-rich host rock, may have significant effects on repository evolution. Reduction of smectite expansion capacity and rehydration potential due to heating could affect the isolation provided by EBS. Processes such as cementation by silica precipitation and authigenic illite could change the hydraulic and mechanical properties of clay-rich materials. Experimental studies of these repository conditions at high P,T have not been performed in the U.S. for decades and little has been done by the international community at high P,T. The experiments to be performed by LANL will focus on the importance of repository chemical and mineralogical conditions at elevated P,T conditions. This will provide input to the assessment of scientific basis for elevating the temperature limits in clay barriers.

Caporuscio, Florie A [Los Alamos National Laboratory; Cheshire, Michael C [Los Alamos National Laboratory; Newell, Dennis L [Los Alamos National Laboratory; McCarney, Mary Kate [Los Alamos National Laboratory

2012-08-22T23:59:59.000Z

86

Geologic Maps Geology 200  

E-Print Network [OSTI]

Geologic Maps Geology 200 Geology for Environmental Scientists #12;Geologic Map of the US #12;Symbols found on geologic maps #12;Horizontal Strata #12;Geologic map of part of the Grand Canyon. Each color represents a different formation. #12;Inclined Strata #12;Dome #12;Geologic map of the Black Hills

Kammer, Thomas

87

Generic repository design concepts and thermal analysis (FY11).  

SciTech Connect (OSTI)

Reference concepts for geologic disposal of used nuclear fuel and high-level radioactive waste in the U.S. are developed, including geologic settings and engineered barriers. Repository thermal analysis is demonstrated for a range of waste types from projected future, advanced nuclear fuel cycles. The results show significant differences among geologic media considered (clay/shale, crystalline rock, salt), and also that waste package size and waste loading must be limited to meet targeted maximum temperature values. In this study, the UFD R&D Campaign has developed a set of reference geologic disposal concepts for a range of waste types that could potentially be generated in advanced nuclear FCs. A disposal concept consists of three components: waste inventory, geologic setting, and concept of operations. Mature repository concepts have been developed in other countries for disposal of spent LWR fuel and HLW from reprocessing UNF, and these serve as starting points for developing this set. Additional design details and EBS concepts will be considered as the reference disposal concepts evolve. The waste inventory considered in this study includes: (1) direct disposal of SNF from the LWR fleet, including Gen III+ advanced LWRs being developed through the Nuclear Power 2010 Program, operating in a once-through cycle; (2) waste generated from reprocessing of LWR UOX UNF to recover U and Pu, and subsequent direct disposal of used Pu-MOX fuel (also used in LWRs) in a modified-open cycle; and (3) waste generated by continuous recycling of metal fuel from fast reactors operating in a TRU burner configuration, with additional TRU material input supplied from reprocessing of LWR UOX fuel. The geologic setting provides the natural barriers, and establishes the boundary conditions for performance of engineered barriers. The composition and physical properties of the host medium dictate design and construction approaches, and determine hydrologic and thermal responses of the disposal system. Clay/shale, salt, and crystalline rock media are selected as the basis for reference mined geologic disposal concepts in this study, consistent with advanced international repository programs, and previous investigations in the U.S. The U.S. pursued deep geologic disposal programs in crystalline rock, shale, salt, and volcanic rock in the years leading up to the Nuclear Waste Policy Act, or NWPA (Rechard et al. 2011). The 1987 NWPA amendment act focused the U.S. program on unsaturated, volcanic rock at the Yucca Mountain site, culminating in the 2008 license application. Additional work on unsaturated, crystalline rock settings (e.g., volcanic tuff) is not required to support this generic study. Reference disposal concepts are selected for the media listed above and for deep borehole disposal, drawing from recent work in the U.S. and internationally. The main features of the repository concepts are discussed in Section 4.5 and summarized in Table ES-1. Temperature histories at the waste package surface and a specified distance into the host rock are calculated for combinations of waste types and reference disposal concepts, specifying waste package emplacement modes. Target maximum waste package surface temperatures are identified, enabling a sensitivity study to inform the tradeoff between the quantity of waste per disposal package, and decay storage duration, with respect to peak temperature at the waste package surface. For surface storage duration on the order of 100 years or less, waste package sizes for direct disposal of SNF are effectively limited to 4-PWR configurations (or equivalent size and output). Thermal results are summarized, along with recommendations for follow-on work including adding additional reference concepts, verification and uncertainty analysis for thermal calculations, developing descriptions of surface facilities and other system details, and cost estimation to support system-level evaluations.

Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); Dupont, Mark (Savannah River Nuclear Solutions, Aiken, SC); Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Fratoni, Massimiliano (Lawrence Livermore National Laboratory, Livermore, CA); Greenberg, Harris (Lawrence Livermore National Laboratory, Livermore, CA); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Hardin, Ernest L.; Sutton, Mark A. (Lawrence Livermore National Laboratory, Livermore, CA)

2011-08-01T23:59:59.000Z

88

Application of Analytical Heat Transfer Models of Multi-layered Natural and Engineered Barriers in Potential High-Level Nuclear Waste Repositories - 12435  

SciTech Connect (OSTI)

A combination of transient heat transfer analytical solutions for a finite line source, a series of point sources, and a series of parallel infinite line sources were combined with a quasi-steady-state multi-layered cylindrical solution to simulate the temperature response of a deep geologic radioactive waste repository with multi-layered natural and engineered barriers. This evaluation was performed to provide information to scientists and decision makers to compare candidate geologic media for a repository (crystalline rock [granite], clay, salt, and deep borehole), and to provide input for the future evaluation of the trade-off between pre-emplacement surface storage time, waste package size, and repository footprint. This approach was selected in favor of the finite element solution typically used to analyze the temperature response because it allowed rapid comparison of a large number of alternative disposal options and design configurations. More than 100 combinations of waste form, geologic environment, repository design configuration, and surface storage times were analyzed and compared. The analytical solution approach used to analyze the repository temperature response allowed rapid comparison of a large number of alternative disposal options and design configurations. More than 100 combinations of waste form, geologic environment, repository design configuration, and surface storage times were analyzed and compared. This approach allowed investigation of the sensitivity of the results to combinations of parameters that show that there is much flexibility to be gained in terms of spent fuel management options by varying a few key parameters. This initial analysis used representative design concepts and thermal constraints based on international design concepts, and it also included waste forms representing future fuel cycles with high burnup fuels. Unlike repository designs with large open tunnels and pre-closure ventilation, all of the disposal concepts analyzed in this study used enclosed emplacement modes, where the waste packages were in direct contact with encapsulating engineered or natural materials. The deep borehole repository concept limits the size of the SNF waste packages and may require rod consolidation to fit within the drill casing diameter. A single assembly waste package, assuming rod consolidation, was evaluated in the current analysis. Similar size restrictions apply for the HLW canisters. At this time no thermal constraints have been defined for the deep borehole repository concept. Representative EBS materials and properties were evaluated. However, changes in EBS design concepts and materials can also have significant effects on the maximum waste package surface temperature. Increased thermal conductivity of the buffer layer can be achieved by using an engineered buffer consisting of a mixture of graphite, sand, and bentonite [14]. One of the advantages of the analytical model is that it highlights the sensitivity of the results to the parameters that define the repository layout, including spacing between axial and lateral neighboring waste packages and drifts. It is clear that repository layout adjustments can be made to reduce the calculated peak temperatures. The results also show that significant reductions in required surface storage times can be achieved if higher thermal constraints can be justified Additional studies are planned to evaluate the trade-offs between surface storage times, repository layout parameters, and variations in EBS design concepts. Model validation and uncertainties will also be addressed. It is expected that shorter surface storage times and more optimized repository design configurations may be achieved. (authors)

Greenberg, Harris R.; Blink, James A.; Fratoni, Massimiliano; Sutton, Mark [Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States); Ross, Amber D. [University of the Sciences in Philadelphia, Philadelphia, PA 19104 (United States)

2012-07-01T23:59:59.000Z

89

E-Print Network 3.0 - analyze repository capacity Sample Search...  

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

and Information Sciences 83 Panel Organization 1. Panel on Structural Geology & Geoengineering Summary: in a repository, are thoroughly analyzed. Appendix E E-5 12;The study...

90

Final Supplemental Environmental Impact Statement for a Geologic...  

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

Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County,...

91

Final Supplemental Environmental Impact Statement for a Geologic...  

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

- Nevada Rail Transportation Corridor DOEEIS-0250F-S2 and Final Env Final Supplemental Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear...

92

TheU-Tube: A Novel System for Acquiring Borehole Fluid Samplesfrom a Deep Geologic CO2 Sequestration Experiment  

SciTech Connect (OSTI)

A novel system has been deployed to obtain geochemical samples of water and gas, at in situ pressure, during a geologic CO2 sequestration experiment conducted in the Frio brine aquifer in Liberty County, Texas. Project goals required high-frequency recovery of representative and uncontaminated aliquots of a rapidly changing two-phase (supercritical CO2-brine) fluid from 1.5 km depth. The datasets collected, using both the liquid and gas portions of the downhole samples, provide insights into the coupled hydro-geochemical issues affecting CO2 sequestration in brine-filled formations. While the basic premise underlying the U-Tube sampler is not new, the system is unique because careful consideration was given to the processing of the recovered two-phase fluids. In particular, strain gauges mounted beneath the high-pressure surface sample cylinders measured the ratio of recovered brine to supercritical CO2. A quadrupole mass spectrometer provided real-time gas analysis for perfluorocarbon and noble gas tracers that were injected along with the CO2. The U-Tube successfully acquired frequent samples, facilitating accurate delineation of the arrival of the CO2 plume, and on-site analysis revealed rapid changes in geochemical conditions.

Freifeld, Barry M.; Trautz, Robert C.; Kharaka, Yousif K.; Phelps, Tommy J.; Myer, Larry R.; Hovorka, Susan D.; Collins, Daniel J.

2005-03-17T23:59:59.000Z

93

Repository performance confirmation.  

SciTech Connect (OSTI)

Repository performance confirmation links the technical bases of repository science and societal acceptance. This paper explores the myriad aspects of what has been labeled performance confirmation in U.S. programs, which involves monitoring as a collection of distinct activities combining technical and social significance in radioactive waste management. This paper is divided into four parts: (1) A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives; (2) A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain; (3) A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant; and (4) An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. A fundamental consideration is the differentiation of confirmation monitoring from the many other testing and monitoring activities. Recently, the license application for Yucca Mountain provided a case study including a technical process for meeting regulatory requirements to confirm repository performance as well as considerations related to the preservation of retrievability. The performance confirmation plan developed as part of the Yucca Mountain license application identified a broad suite of monitoring activities. A revision of the plan was expected to winnow the number of activities down to a manageable size. As a result, an objective process for the next stage of performance confirmation planning was developed as an integral part of an overarching long-term testing and monitoring strategy. The Waste Isolation Pilot Plant compliance monitoring program at once reflects its importance to stakeholders while demonstrating adequate understanding of relevant monitoring parameters. The compliance criteria were stated by regulation and are currently monitored as part of the regulatory rule for disposal. At the outset, the screening practice and parameter selection were not predicated on a direct or indirect correlation to system performance metrics, as was the case for Yucca Mountain. Later on, correlation to performance was established, and the Waste Isolation Pilot Plant continues to monitor ten parameters originally identified in the compliance certification documentation. The monitoring program has proven to be effective for the technical intentions and societal or public assurance. The experience with performance confirmation in the license application process for Yucca Mountain helped identify an objective, quantitative methodology for this purpose. Revision of the existing plan would be based on findings of the total system performance assessment. Identification and prioritization of confirmation activities would then derive from performance metrics associated with performance assessment. Given the understanding of repository performance confirmation, as reviewed in this paper, it is evident that the performance confirmation program for the Yucca Mountain project could be readily re-engaged if licensing activities resumed.

Hansen, Francis D.

2011-09-01T23:59:59.000Z

94

On mobilization of lead and arsenic in groundwater in response to CO2 leakage from deep geological storage  

SciTech Connect (OSTI)

If carbon dioxide stored in deep saline aquifers were to leak into an overlying aquifer containing potable groundwater, the intruding CO{sub 2} would change the geochemical conditions and cause secondary effects mainly induced by changes in pH In particular, hazardous trace elements such as lead and arsenic, which are present in the aquifer host rock, could be mobilized. In an effort to evaluate the potential risks to potable water quality, reactive transport simulations were conducted to evaluate to what extent and mechanisms through which lead and arsenic might be mobilized by intrusion of CO{sub 2}. An earlier geochemical evaluation of more than 38,000 groundwater quality analyses from aquifers throughout the United States and an associated literature review provided the basis for setting up a reactive transport model and examining its sensitivity to model variation. The evaluation included identification of potential mineral hosts containing hazardous trace elements, characterization of the modal bulk mineralogy for an arenaceous aquifer, and augmentation of the required thermodynamic data. The reactive transport simulations suggest that CO{sub 2} ingress into a shallow aquifer can mobilize significant lead and arsenic, contaminating the groundwater near the location of intrusion and further downstream. Although substantial increases in aqueous concentrations are predicted compared to the background values, the maximum permitted concentration for arsenic in drinking water was exceeded in only a few cases, whereas that for lead was never exceeded.

Zheng, L.; Apps, J.A.; Zhang, Y.; Xu, T.; Birkholzer, J.T.

2009-07-01T23:59:59.000Z

95

Geologic Sequestration of CO2 in Deep, Unmineable Coalbeds: An Integrated Researdh and Commercial-Scale Field Demonstration Project  

SciTech Connect (OSTI)

The Coal-Seq consortium is a government-industry collaborative consortium with the objective of advancing industry's understanding of complex coalbed methane and gas shale reservoir behavior in the presence of multi-component gases via laboratory experiments, theoretical model development and field validation studies. This will allow primary recovery, enhanced recovery and CO{sub 2} sequestration operations to be commercially enhanced and/or economically deployed. The project was initially launched in 2000 as a U.S. Department of Energy sponsored investigation into CO{sub 2} sequestration in deep, unmineable coalseams. The initial project accomplished a number of important objectives, which mainly revolved around performing baseline experimental studies, documenting and analyzing existing field projects, and establishing a global network for technology exchange. The results from that Phase have been documented in a series of reports which are publicly available. An important outcome of the initial phase was that serious limitations were uncovered in our knowledge of reservoir behavior when CO{sub 2} is injected into coal. To address these limitations, the project was extended in 2005 as a government-industry collaborative consortium. Selected accomplishments from this phase have included the identification and/or development of new models for multi-component sorption and diffusion, laboratory studies of coal geomechanical and permeability behavior with CO{sub 2} injection, additional field validation studies, and continued global technology exchange. Further continuation of the consortium is currently being considered. Some of the topics that have been identified for investigation include further model development/refinement related to multicomponent equations-of-state, sorption and diffusion behavior, geomechanical and permeability studies, technical and economic feasibility studies for major international coal basins, the extension of the work to gas shale reservoirs, and continued global technology exchange.

Scott Reeves; George Koperna

2008-09-30T23:59:59.000Z

96

Preliminary total-system analysis of a potential high-level nuclear waste repository at Yucca Mountain  

SciTech Connect (OSTI)

The placement of high-level radioactive wastes in mined repositories deep underground is considered a disposal method that would effectively isolate these wastes from the environment for long periods of time. This report describes modeling performed at PNL for Yucca Mountain between May and November 1991 addressing the performance of the entire repository system related to regulatory criteria established by the EPA in 40 CFR Part 191. The geologic stratigraphy and material properties used in this study were chosen in cooperation with performance assessment modelers at Sandia National Laboratories (SNL). Sandia modeled a similar problem using different computer codes and a different modeling philosophy. Pacific Northwest Laboratory performed a few model runs with very complex models, and SNL performed many runs with much simpler (abstracted) models.

Eslinger, P.W.; Doremus, L.A.; Engel, D.W.; Miley, T.B.; Murphy, M.T.; Nichols, W.E.; White, M.D. [Pacific Northwest Lab., Richland, WA (United States); Langford, D.W.; Ouderkirk, S.J. [Westinghouse Hanford Co., Richland, WA (United States)

1993-01-01T23:59:59.000Z

97

Two Approaches to the Geologic Disposal of Long-Lived Nuclear Waste: Yucca Mountain, Nevada and the Waste Isolation Pilot Plant, Carlsbad, New Mexico  

SciTech Connect (OSTI)

A key component of the US energy program is to provide for the safe and permanent isolation of spent nuclear fuel and long-lived radioactive waste produced through programs related to national defense and the generation of electric power by nuclear utilities. To meet this challenge, the US Department of Energy (DOE) has developed a multi-faceted approach to the geologic disposal of long-lived nuclear wastes. Two sites are being developed or studied as current or potential deep geologic repositories for long lived radioactive wastes, the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico and Yucca Mountain, Nevada.

Levich, R. A.; Patterson, R. L.; Linden, R. M.

2002-02-26T23:59:59.000Z

98

Geological SciencesGeological Sciences Geological EngineeringGeological Engineering  

E-Print Network [OSTI]

Geological SciencesGeological Sciences Geological EngineeringGeological Engineering Geosciences Careers in the ik ou ve n ver see t b f rel e y ' e n i e o ! Department of Geological Sciences and Geological Engineering Queen's University See the World Geological Sciences Arts and Science Faculty

Ellis, Randy

99

Geologyy of the Yucca Mountain Site Area, Southwestern Nevada, Chapter in Stuckless, J.S., ED., Yucca Mountain, Nevada - A Proposed Geologic Repository for High-Level Radioactive Waste (Volume 1)  

SciTech Connect (OSTI)

Yucca Mountain in southwestern Nevada is a prominent, irregularly shaped upland formed by a thick apron of Miocene pyroclastic-flow and fallout tephra deposits, with minor lava flows, that was segmented by through-going, large-displacement normal faults into a series of north-trending, eastwardly tilted structural blocks. The principal volcanic-rock units are the Tiva Canyon and Topopah Spring Tuffs of the Paintbrush Group, which consist of volumetrically large eruptive sequences derived from compositionally distinct magma bodies in the nearby southwestern Nevada volcanic field, and are classic examples of a magmatic zonation characterized by an upper crystal-rich (> 10% crystal fragments) member, a more voluminous lower crystal-poor (< 5% crystal fragments) member, and an intervening thin transition zone. Rocks within the crystal-poor member of the Topopah Spring Tuff, lying some 280 m below the crest of Yucca Mountain, constitute the proposed host rock to be excavated for the storage of high-level radioactive wastes. Separation of the tuffaceous rock formations into subunits that allow for detailed mapping and structural interpretations is based on macroscopic features, most importantly the relative abundance of lithophysae and the degree of welding. The latter feature, varying from nonwelded through partly and moderately welded to densely welded, exerts a strong control on matrix porosities and other rock properties that provide essential criteria for distinguishing hydrogeologic and thermal-mechanical units, which are of major interest in evaluating the suitability of Yucca Mountain to host a safe and permanent geologic repository for waste storage. A thick and varied sequence of surficial deposits mantle large parts of the Yucca Mountain site area. Mapping of these deposits and associated soils in exposures and in the walls of trenches excavated across buried faults provides evidence for multiple surface-rupturing events along all of the major faults during Pleistocene and Holocene times; these paleoseismic studies form the basis for evaluating the potential for future earthquakes and fault displacements. Thermoluminescence and U-series analyses were used to date the surficial materials involved in the Quaternary faulting events. The rate of erosional downcutting of bedrock on the ridge crests and hillslopes of Yucca Mountain, being of particular concern with respect to the potential for breaching of the proposed underground storage facility, was studied by using rock varnish cation-ratio and {sup 10}Be and {sup 36}Cl cosmogenic dating methods to determine the length of time bedrock outcrops and hillslope boulder deposits were exposed to cosmic rays, which then served as a basis for calculating long-term erosion rates. The results indicate rates ranging from 0.04 to 0.27 cm/k.y., which represent the maximum downcutting along the summit of Yucca Mountain under all climatic conditions that existed there during most of Quaternary time. Associated studies include the stratigraphy of surficial deposits in Fortymile Wash, the major drainage course in the area, which record a complex history of four to five cut-and-fill cycles within the channel during middle to late Quaternary time. The last 2 to 4 m of incision probably occurred during the last pluvial climatic period, 22 to 18 ka, followed by aggradation to the present time.

W.R. Keefer; J.W. Whitney; D.C. Buesch

2006-09-25T23:59:59.000Z

100

Prepared in cooperation with the Inyo County, California, Yucca Mountain Repository Assessment Office  

E-Print Network [OSTI]

Prepared in cooperation with the Inyo County, California, Yucca Mountain Repository Assessment County, California, Yucca Mountain Repository Assessment Office #12;U.S. Department of the Interior KEN Office Geologic Map of the southern Funeral Mountains including nearby Groundwater Discharge Sites

Fleskes, Joe

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101

Generic Repository Concepts and Thermal Analysis for Advanced Fuel Cycles - 12477  

SciTech Connect (OSTI)

A geologic disposal concept for spent nuclear fuel (SNF) or high-level waste (HLW) consists of three components: waste inventory, geologic setting, and concept of operations. A set of reference geologic disposal concepts has been developed by the U.S. Department of Energy (DOE), Used Fuel Disposition campaign. Reference concepts are identified for crystalline rock, clay/shale, bedded salt, and deep borehole (crystalline basement) geologic settings. These were analyzed for waste inventory cases representing a range of waste types that could be produced by advanced nuclear fuel cycles. Concepts of operation consisting of emplacement mode, repository layout, and engineered barrier descriptions, were selected based on international progress. All of these disposal concepts are enclosed emplacement modes, whereby waste packages are in direct contact with encapsulating engineered or natural materials. Enclosed modes have less capacity to dissipate heat than open modes such as that proposed for a repository at Yucca Mountain. Thermal analysis has identified important relationships between waste package size and capacity, and the duration of surface decay storage needed to meet temperature limits for different disposal concepts. For the crystalline rock and clay/shale repository concepts, a waste package surface temperature limit of 100 deg. C was assumed to prevent changes in clay-based buffer material or clay-rich host rock. Surface decay storage of 50 to 100 years is needed for disposal of high-burnup LWR SNF in 4-PWR packages, or disposal of HLW glass from reprocessing LWR uranium oxide (UOX) fuel. High-level waste (HLW) from reprocessing of metal fuel used in a fast reactor could be disposed after decay storage of 50 years or less. For disposal in salt the rock thermal conductivity is significantly greater, and higher temperatures (200 deg. C) can be tolerated at the waste package surface. Decay storage of 10 years or less is needed for high-burnup LWR SNF in 4-PWR packages, while 12-PWR packages could be emplaced after 40 years or less. HLW from reprocessing LWR UOX fuel or metal fuel from fast reactors, could be disposed of in salt after 10 to 50 years of decay storage depending on the specific composition and other factors. For the deep borehole disposal concept no near-field temperature limits are recognized because no performance credit is taken for waste form or waste package integrity, or containment by the near-field host rock. These results show the key differences in thermal management strategies available to the U.S. repository program, given the range of disposal concepts. A host medium such as salt with greater thermal conductivity and peak temperature tolerance could shorten decay storage by 50 years, or facilitate the use of larger waste packages. The LWR UOX SNF evaluated in this study represents that which could be produced in the coming decades. The existing, lower burnup used fuel that is presently in storage at many LWR locations across the U.S. is significantly cooler, and analyses of this type could be used to show that disposal is possible with less decay storage or larger waste packages. We note that while the temperature limits and waste package capacities used in this study are similar to those used internationally and in past U.S. studies, they might be increased as the result of ongoing research and development activities. This study selected enclosed emplacement modes to conform with disposal concepts developed internationally and previously in the U.S. Open modes (such as that proposed for a repository at Yucca Mountain) afford additional flexibility in waste management and the necessary investment, because the same facility serves both storage and disposal functions. Use of open modes, and combined analysis of storage, transportation, and disposal functions, are appropriate to consider in future studies of this type. (authors)

Hardin, Ernest [Sandia National Laboratories, P.O. Box 5800 MS 0736, Albuquerque, NM 87185 (United States); Blink, James [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551-0808 (United States); Carter, Joe [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Fratoni, Massimiliano; Greenberg, Harris; Sutton, Mark [Lawrence Livermore National Laboratory (United States); Howard, Robert [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)

2012-07-01T23:59:59.000Z

102

Investigations on Repository Near-Field Thermal Modeling - Repository Science/Thermal Load Management & Design Concepts (M41UF033302)  

SciTech Connect (OSTI)

The various layers of material from the waste package (such as components of the engineered barrier system and the host rock surface) to a given distance within the rock wall at a given distance can be described as concentric circles with varying thermal properties (see Figure 5.1-1). The selected model approach examines the contributions of the waste package, axial waste package neighbors and lateral neighboring emplacement drifts (see Section 5.2.1 and Appendix H, Section 2). In clay and deep borehole media, the peak temperature is driven by the central waste package whereas, in granite and salt, the contribution to the temperature rise by adjacent (lateral) waste packages in drift or emplacement borehole lines is dominant at the time of the peak temperature. Mathematical models generated using Mathcad software provide insight into the effects of changing waste package spacing for six waste forms, namely UOX, MOX, co-extraction, new extraction, E-Chem ceramic and E-Chem metal in four different geologic media (granite, clay, salt and deep borehole). Each scenario includes thermal conductivity and diffusivity for each layer between the waste package and the host rock, dimensions of representative repository designs (such as waste package spacing, drift or emplacement borehole spacing, waste package dimensions and layer thickness), and decay heat curves generated from knowledge of the contents of a given waste form after 10, 50, 100 and 200 years of surface storage. Key results generated for each scenario include rock temperature at a given time calculated at a given radius from the central waste package (Section 5.2.1 and Appendix H, Section 3), the corresponding temperature at the interface of the waste package and EBS material, and at each EBS layer in between (Section 5.2.2 and Appendix H, Section 4). This information is vital to understand the implications of repository design (waste package capacity, surface storage time, waste package spacing, and emplacement drift or borehole spacing) by comparing the peak temperature to the thermal limits of the concentric layers surrounding the waste package; specifically 100 C for the bentonite buffer in granite and clay repositories, 100 C for rock wall in a clay repository and 200 C at the rock wall for a salt repository. These thermal limits are both preliminary and approximate, and serve as a means to evaluate design options rather than determining compliance for licensing situations. The thermal behavior of a salt repository is more difficult to model because it is not a concentric geometry and because the crushed salt backfill initially has a much higher thermal resistance than intact salt. Three models were investigated, namely a waste package in complete contact with crushed salt, secondly a waste package in contact with intact salt, and thirdly a waste package in contact with 75% intact and 25% crushed salt. The latter model best depicts emplacement of a waste package in the corner of an intact salt alcove and subsequently covered with crushed salt backfill to the angle of repose. The most conservative model (crushed salt) had temperatures much higher than the other models and although bounding, is too conservative to use. The most realistic model (75/25) had only a small temperature difference from the simplest (non-conservative, intact salt) model, and is the one chosen in this report (see Section 5.2.3). A trade-study investigating three key variables (surface storage time, waste package capacity and waste package spacing) is important to understand and design a repository. Waste package heat can be reduced by storing for longer periods prior to emplacement, or by reducing the number of assemblies or canisters within that waste package. Waste package spacing can be altered to optimize the thermal load without exceeding the thermal limits of the host rock or EBS components. By examining each of these variables, repository footprint (and therefore cost) can be optimized. For this report, the layout was fixed for each geologic medium based on prior published designs in

Sutton, M; Blink, J A; Fratoni, M; Greenberg, H R; Ross, A D

2011-07-15T23:59:59.000Z

103

Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt  

SciTech Connect (OSTI)

Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.

Elders, W.A.; Cohen, L.H.

1983-11-01T23:59:59.000Z

104

The Potential for Increased Atmospheric CO2 Emissions and Accelerated Consumption of Deep Geologic CO2 Storage Resources Resulting from the Large-Scale Deployment of a CCS-Enabled Unconventional Fossil Fuels Industry in the U.S.  

SciTech Connect (OSTI)

Desires to enhance the energy security of the United States have spurred significant interest in the development of abundant domestic heavy hydrocarbon resources including oil shale and coal to produce unconventional liquid fuels to supplement conventional oil supplies. However, the production processes for these unconventional fossil fuels create large quantities of carbon dioxide (CO2) and this remains one of the key arguments against such development. Carbon dioxide capture and storage (CCS) technologies could reduce these emissions and preliminary analysis of regional CO2 storage capacity in locations where such facilities might be sited within the U.S. indicates that there appears to be sufficient storage capacity, primarily in deep saline formations, to accommodate the CO2 from these industries. Nevertheless, even assuming wide-scale availability of cost-effective CO2 capture and geologic storage resources, the emergence of a domestic U.S. oil shale or coal-to-liquids (CTL) industry would be responsible for significant increases in CO2 emissions to the atmosphere. The authors present modeling results of two future hypothetical climate policy scenarios that indicate that the oil shale production facilities required to produce 3MMB/d from the Eocene Green River Formation of the western U.S. using an in situ retorting process would result in net emissions to the atmosphere of between 3000-7000 MtCO2, in addition to storing potentially 900-5000 MtCO2 in regional deep geologic formations via CCS in the period up to 2050. A similarly sized, but geographically more dispersed domestic CTL industry could result in 4000-5000 MtCO2 emitted to the atmosphere in addition to potentially 21,000-22,000 MtCO2 stored in regional deep geologic formations over the same period. While this analysis shows that there is likely adequate CO2 storage capacity in the regions where these technologies are likely to deploy, the reliance by these industries on large-scale CCS could result in an accelerated rate of utilization of the nation’s CO2 storage resource, leaving less high-quality storage capacity for other carbon-producing industries including electric power generation.

Dooley, James J.; Dahowski, Robert T.; Davidson, Casie L.

2009-11-02T23:59:59.000Z

105

2.5 Zeolites 2.5.1 Introduction  

E-Print Network [OSTI]

. The planned siting of the United States' first deep geologic radioactive waste repository at Yucca Mountain

106

Geologic Framework Model (GFM2000)  

SciTech Connect (OSTI)

The purpose of this report is to document the geologic framework model, version GFM2000 with regard to input data, modeling methods, assumptions, uncertainties, limitations, and validation of the model results, and the differences between GFM2000 and previous versions. The version number of this model reflects the year during which the model was constructed. This model supersedes the previous model version, documented in Geologic Framework Model (GFM 3.1) (CRWMS M&O 2000 [DIRS 138860]). The geologic framework model represents a three-dimensional interpretation of the geology surrounding the location of the monitored geologic repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain. The geologic framework model encompasses and is limited to an area of 65 square miles (168 square kilometers) and a volume of 185 cubic miles (771 cubic kilometers). The boundaries of the geologic framework model (shown in Figure 1-1) were chosen to encompass the exploratory boreholes and to provide a geologic framework over the area of interest for hydrologic flow and radionuclide transport modeling through the unsaturated zone (UZ). The upper surface of the model is made up of the surface topography and the depth of the model is constrained by the inferred depth of the Tertiary-Paleozoic unconformity. The geologic framework model was constructed from geologic map and borehole data. Additional information from measured stratigraphic sections, gravity profiles, and seismic profiles was also considered. The intended use of the geologic framework model is to provide a geologic framework over the area of interest consistent with the level of detailed needed for hydrologic flow and radionuclide transport modeling through the UZ and for repository design. The model is limited by the availability of data and relative amount of geologic complexity found in an area. The geologic framework model is inherently limited by scale and content. The grid spacing used in the geologic framework model (200 feet [61 meters]), discussed in Section 6.4.2, limits the size of features that can be resolved by the model but is appropriate for the distribution of data available and its intended use. Uncertainty and limitations are discussed in Section 6.6 and model validation is discussed in Section 7.

T. Vogt

2004-08-26T23:59:59.000Z

107

An analysis of repository waste-handling operations  

SciTech Connect (OSTI)

This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs.

Dennis, A.W.

1990-09-01T23:59:59.000Z

108

Salt repository project closeout status report  

SciTech Connect (OSTI)

This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs.

NONE

1988-06-01T23:59:59.000Z

109

The application of high-resolution 3D seismic data to model the distribution of mechanical and hydrogeological properties of a potential host rock for the deep storage of radioactive waste in France  

E-Print Network [OSTI]

In the context of a deep geological repository of high-level radioactive wastes, the French National Radioactive Waste Management Agency (Andra) has conducted an extensive characterization of the Callovo-Oxfordian argillaceous rock and surrounding formations in the Eastern Paris Basin. As part of this project, an accurate 3D seismic derived geological model is needed. The paper shows the procedure used for building the 3D seismic constrained geological model in depth by combining time-to-depth conversion of seismic horizons, consistent seismic velocity model and elastic impedance in time. It also shows how the 3D model is used for mechanical and hydrogeological studies. The 3D seismic field data example illustrates the potential of the proposed depth conversion procedure for estimating density and velocity distributions, which are consistent with the depth conversion of seismic horizons using the Bayesian Kriging method. The geological model shows good agreement with well log data obtained from a reference we...

Mari, Jean-Luc

2014-01-01T23:59:59.000Z

110

Application of oil exploration techniques toward finding a nuclear waste repository site  

SciTech Connect (OSTI)

Through its National Waste Terminal Storage (NWTS) Program, the U.S. Department of Energy is responsible for providing facilities to permanently dispose of high-level nuclear waste in a manner that will ensure public health and safety and that will be environmentally acceptable. Three separately coordinated projects, which have placed emphasis on deep, underground repositories are described. They are the Basalt Waste Isolation Project at the Hanford Reservation in Wahington, the Nevada Nuclear Waste Storage investigations at the Nevada Test Site, and a project focusing on suitable rock types in the remainder of the conterminous 48 states, managed by the Office of Nuclear Waste Isolation in Columbus, Ohio. The last-mentioned project is presently focused on rock salt and crystalline formations as suitable host rocks for a repository. The geologic evaluation considers stratigraphy, structure, hydrogeology, seismicity, tectonic history, Quaternary features, physiography, energy/mineral resources, and geotechnical factors. Extensive use has been made of drill stem test data, a mainstay of petroleum exploration since the late 1920`s, to obtain hydrologic information. (JMT)

Laughon, R.B.

1982-06-01T23:59:59.000Z

111

2004 Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.org. Geology; October 2004; v. 32; no. 10; p. 925928; doi: 10.1130/G20561.1; 4 figures; Data Repository item 2004149. 925  

E-Print Network [OSTI]

as far east as the Texas panhandle (Fig. 2), and may have influenced the locus of Neogene extension2004 Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.org. Geology; October 2004; v. 32; no. 10; p. 925­928; doi: 10.1130/G20561.1; 4 figures

Pazzaglia, Frank J.

112

2004 Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.org. Geology; January 2004; v. 32; no. 1; p. 58; DOI 10.1130/G19957.1; 2 figures; Data Repository item 2004001. 5  

E-Print Network [OSTI]

2004 Geological Society of America. For permission to copy, contact Copyright Permissions, GSA, or editing@geosociety.org. Geology; January 2004; v. 32; no. 1; p. 5­8; DOI 10.1130/G19957.1; 2 figures; Data a speleothem-based ab- solutely dated record (using uranium-series data) of climate change for the southwestern

Asmerom, Yemane

113

YOUNG GEOLOGY GEOLOGY OF THE  

E-Print Network [OSTI]

YOUNG GEOLOGY UNIVERSITY May, 1962 GEOLOGY OF THE SOUTHERN WASATCH MOUNTAINS AND VICIN~IM,UTAH C O ....................J. Keith Rigby 80 Economic Geology of North-Central Utah ...,............... Kcnneth C.Bdodc 85 Rod Log ........................Lehi F. Hintze, J. Ka# Ri&, & ClydeT. Hardy 95 Geologic Map of Southern

Seamons, Kent E.

114

Deep Vs Profiling Along the Top of Yucca Mountain Using a Vibroseis Source and Surface Waves  

SciTech Connect (OSTI)

Yucca Mountain, Nevada, was approved as the site for development of the geologic repository for high-level radioactive waste and spent nuclear fuel in the United States. The U.S. Department of Energy has been conducting studies to characterize the site and assess its future performance as a geologic repository. As part of these studies, a program of deep seismic profiling, to depths of 200 m, was conducted along the top of Yucca Mountain to evaluate the shear-wave velocity (V{sub s}) structure of the repository block. The resulting V{sub s} data were used as input into the development of ground motions for the preclosure seismic design of the repository and for postclosure performance assessment. The noninvasive spectral-analysis-of-surface-waves (SASW) method was employed in the deep profiling. Field measurements involved the use of a modified Vibroseis as the seismic source. The modifications allowed the Vibroseis to be controlled by a signal analyzer so that slow frequency sweeps could be performed while simultaneous narrow-band filtering was performed on the receiver outputs. This process optimized input energy from the source and signal analysis of the receiver outputs. Six deep V{sub s} profiles and five intermediate-depth (about 100 m) profiles were performed along the top of Yucca Mountain over a distance of about 5 km. In addition, eleven shallower profiles (averaging about 45-m deep) were measured using a bulldozer source. The shallower profiles were used to augment the deeper profiles and to evaluate further the near-surface velocity structure. The V{sub s} profiles exhibit a strong velocity gradient within 5 m of the surface, with the mean V{sub s} value more than doubling. Below this depth, V{sub s} gradually increases from a mean value of about 900 to 1000 m/s at a depth of 150 m. Between the depths of 150 and 210 m, V{sub s} increases more rapidly to about 1350 m/s, but this trend is based on limited data. At depths less than 50 m, anisotropy in V{sub s} was measured for surveys conducted parallel and perpendicular to the mountain crest, with the velocity parallel to the crest about 200 m/s higher. In the 5- to 50-m depth range, the average coefficient of variation (COV) of all data is about 0.25. Below 75 m, where the data set is smaller and includes measurements only parallel to the crest, the average COV decreases to a value of about 0.11.

K. Stokoe; B. Rosenblad; I. Wong; J. Bay; P. Thomas; W. Silva

2004-03-16T23:59:59.000Z

115

Assessment of effectiveness of geologic isolation systems. CIRMIS data system. Volume 3. Generator routines  

SciTech Connect (OSTI)

The Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing and applying the methodology for assessing the far-field, long-term post-closure safety of deep geologic nuclear waste repositories. AEGIS is being performed by Pacific Northwest Laboratory (PNL) under contract with the Office of Nuclear Waste Isolation (ONWI) for the Department of Energy (DOE). One task within AEGIS is the development of methodology for analysis of the consequences (water pathway) from loss of repository containment as defined by various release scenarios. The various input parameters required in the analysis are compiled in data systems. The data are organized and prepared by various input subroutines for utilization by the hydraulic and transport codes. The hydrologic models simulate the groundwater flow systems and provide water flow directions, rates, and velocities as inputs to the transport models. Outputs from the transport models are basically graphs of radionuclide concentration in the groundwater plotted against time. After dilution in the receiving surface-water body (e.g., lake, river, bay), these data are the input source terms for the dose models, if dose assessments are required. The dose models calculate radiation dose to individuals and populations. CIRMIS (Comprehensive Information Retrieval and Model Input Sequence) Data System, a storage and retrieval system for model input and output data, including graphical interpretation and display is described. This is the third of four volumes of the description of the CIRMIS Data System.

Friedrichs, D.R.; Argo, R.S.

1980-01-01T23:59:59.000Z

116

Geologic and hydrologic investigations of a potential nuclear waste disposal site at Yucca Mountain, southern Nevada  

SciTech Connect (OSTI)

Yucca Mountain in southern Nye County, Nevada, has been selected by the United States Department of Energy as one of three potential sites for the nation`s first high-level nuclear waste repository. Its deep water table, closed-basin ground-water flow, potentially favorable host rock, and sparse population have made the Yucca Mountain area a viable candidate during the search for a nuclear waste disposal site. Yucca Mountain, however, lies within the southern Great Basin, a region of known contemporary tectonism and young volcanic activity, and the characterization of tectonism and volcanism remains as a fundamental problem for the Yucca Mountain site. The United States Geological Survey has been conducting extensive studies to evaluate the geologic setting of Yucca Mountain, as well as the timing and rates of tectonic and volcanic activity in the region. A workshop was convened by the Geologic Survey in Denver, Colorado, on August 19, 20, and 21, 1985, to review the scientific progress and direction of these studies. Considerable debate resulted. This collection of papers represents the results of some of the studies presented at the workshop, but by no means covers all of the scientific results and viewpoints presented. Rather, the volume is meant to serve as a progress report on some of the studies within the Geological Survey`s continuing research program toward characterizing the tectonic framework of Yucca Mountain. Individual papers were processed separately for the data base.

Carr, M.D.; Yount, J.C. (eds.)

1988-12-31T23:59:59.000Z

117

Development of Science-Based Permitting Guidance for Geological Sequestration of CO2 in Deep Saline Aquifers Based on Modeling and Risk Assessment  

SciTech Connect (OSTI)

Underground carbon storage may become one of the solutions to address global warming. However, to have an impact, carbon storage must be done at a much larger scale than current CO{sub 2} injection operations for enhanced oil recovery. It must also include injection into saline aquifers. An important characteristic of CO{sub 2} is its strong buoyancy--storage must be guaranteed to be sufficiently permanent to satisfy the very reason that CO{sub 2} is injected. This long-term aspect (hundreds to thousands of years) is not currently captured in legislation, even if the U.S. has a relatively well-developed regulatory framework to handle carbon storage, especially in the operational short term. This report proposes a hierarchical approach to permitting in which the State/Federal Government is responsible for developing regional assessments, ranking potential sites (''General Permit'') and lessening the applicant's burden if the general area of the chosen site has been ranked more favorably. The general permit would involve determining in the regional sense structural (closed structures), stratigraphic (heterogeneity), and petrophysical (flow parameters such as residual saturation) controls on the long-term fate of geologically sequestered CO{sub 2}. The state-sponsored regional studies and the subsequent local study performed by the applicant will address the long-term risk of the particular site. It is felt that a performance-based approach rather than a prescriptive approach is the most appropriate framework in which to address public concerns. However, operational issues for each well (equivalent to the current underground injection control-UIC-program) could follow regulations currently in place. Area ranking will include an understanding of trapping modes. Capillary (due to residual saturation) and structural (due to local geological configuration) trappings are two of the four mechanisms (the other two are solubility and mineral trappings), which are the most relevant to the time scale of interest. The most likely pathways for leakage, if any, are wells and faults. We favor a defense-in-depth approach, in which storage permanence does not rely upon a primary seal only but assumes that any leak can be contained by geologic processes before impacting mineral resources, fresh ground water, or ground surface. We examined the Texas Gulf Coast as an example of an attractive target for carbon storage. Stacked sand-shale layers provide large potential storage volumes and defense-in-depth leakage protection. In the Texas Gulf Coast, the best way to achieve this goal is to establish the primary injection level below the total depth of most wells (>2,400 m-8,000 ft). In addition, most faults, particularly growth faults, present at the primary injection level do not reach the surface. A potential methodology, which includes an integrated approach comprising the whole chain of potential events from leakage from the primary site to atmospheric impacts, is also presented. It could be followed by the State/Federal Government, as well as by the operators.

Jean-Philippe Nicot; Renaud Bouroullec; Hugo Castellanos; Susan Hovorka; Srivatsan Lakshminarasimhan; Jeffrey Paine

2006-06-30T23:59:59.000Z

118

Geology Publications 1 Fieldiana: Geology  

E-Print Network [OSTI]

in Ten Numbers) 73 No. 1. North American Plesiosaurs. By S. W. Williston. 1903. 78 pages, 34 illus. 77 No. Williston. 1903. 38 pages, 7 illus. 1 #12;Geology Publications 2 Fieldiana: Geology Pub. No. 82 No. 4

Westneat, Mark W.

119

Illustration of sampling-based approaches to the calculation of expected dose in performance assessments for the proposed high level radioactive waste repository at Yucca Mountain, Nevada.  

SciTech Connect (OSTI)

A deep geologic repository for high level radioactive waste is under development by the U.S. Department of Energy at Yucca Mountain (YM), Nevada. As mandated in the Energy Policy Act of 1992, the U.S. Environmental Protection Agency (EPA) has promulgated public health and safety standards (i.e., 40 CFR Part 197) for the YM repository, and the U.S. Nuclear Regulatory Commission has promulgated licensing standards (i.e., 10 CFR Parts 2, 19, 20, etc.) consistent with 40 CFR Part 197 that the DOE must establish are met in order for the YM repository to be licensed for operation. Important requirements in 40 CFR Part 197 and 10 CFR Parts 2, 19, 20, etc. relate to the determination of expected (i.e., mean) dose to a reasonably maximally exposed individual (RMEI) and the incorporation of uncertainty into this determination. This presentation describes and illustrates how general and typically nonquantitive statements in 40 CFR Part 197 and 10 CFR Parts 2, 19, 20, etc. can be given a formal mathematical structure that facilitates both the calculation of expected dose to the RMEI and the appropriate separation in this calculation of aleatory uncertainty (i.e., randomness in the properties of future occurrences such as igneous and seismic events) and epistemic uncertainty (i.e., lack of knowledge about quantities that are poorly known but assumed to have constant values in the calculation of expected dose to the RMEI).

Helton, Jon Craig (Arizona State University, Tempe, AZ); Sallaberry, Cedric J. PhD. (.; .)

2007-04-01T23:59:59.000Z

120

Preliminary analyses of scenarios for potential human interference for repositories in three salt formations  

SciTech Connect (OSTI)

Preliminary analyses of scenarios for human interference with the performance of a radioactive waste repository in a deep salt formation are presented. The following scenarios are analyzed: (1) the U-Tube Connection Scenario involving multiple connections between the repository and the overlying aquifer system; (2) the Single Borehole Intrusion Scenario involving penetration of the repository by an exploratory borehole that simultaneously connects the repository with overlying and underlying aquifers; and (3) the Pressure Release Scenario involving inflow of water to saturate any void space in the repository prior to creep closure with subsequent release under near lithostatic pressures following creep closure. The methodology to evaluate repository performance in these scenarios is described and this methodology is applied to reference systems in three candidate formations: bedded salt in the Palo Duro Basin, Texas; bedded salt in the Paradox Basin, Utah; and the Richton Salt Dome, Mississippi, of the Gulf Coast Salt Dome Basin.

Not Available

1985-10-01T23:59:59.000Z

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121

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

122

A drop-in-concept for deep borehole canister emplacement  

E-Print Network [OSTI]

Disposal of high-level nuclear waste in deep boreholes drilled into crystalline bedrock (i.e., "granite") is an interesting repository alternative of long standing. Work at MIT over the past two decades, and more recently ...

Bates, Ethan Allen

2011-01-01T23:59:59.000Z

123

Integrating repositories with fuel cycles: The airport authority model  

SciTech Connect (OSTI)

The organization of the fuel cycle is a legacy of World War II and the cold war. Fuel cycle facilities were developed and deployed without consideration of the waste management implications. This led to the fuel cycle model of a geological repository site with a single owner, a single function (disposal), and no other facilities on site. Recent studies indicate large economic, safety, repository performance, nonproliferation, and institutional incentives to collocate and integrate all back-end facilities. Site functions could include geological disposal of spent nuclear fuel (SNF) with the option for future retrievability, disposal of other wastes, reprocessing with fuel fabrication, radioisotope production, other facilities that generate significant radioactive wastes, SNF inspection (navy and commercial), and related services such as SNF safeguards equipment testing and training. This implies a site with multiple facilities with different owners sharing some facilities and using common facilities - the repository and SNF receiving. This requires a different repository site institutional structure. We propose development of repository site authorities modeled after airport authorities. Airport authorities manage airports with government-owned runways, collocated or shared public and private airline terminals, commercial and federal military facilities, aircraft maintenance bases, and related operations - all enabled and benefiting the high-value runway asset and access to it via taxi ways. With a repository site authority the high value asset is the repository. The SNF and HLW receiving and storage facilities (equivalent to the airport terminal) serve the repository, any future reprocessing plants, and others with needs for access to SNF and other wastes. Non-public special-built roadways and on-site rail lines (equivalent to taxi ways) connect facilities. Airport authorities are typically chartered by state governments and managed by commissions with members appointed by the state governor, county governments, and city governments. This structure (1) enables state and local governments to work together to maximize job and tax benefits to local communities and the state, (2) provides a mechanism to address local concerns such as airport noise, and (3) creates an institutional structure with large incentives to maximize the value of the common asset, the runway. A repository site authority would have a similar structure and be the local interface to any national waste management authority. (authors)

Forsberg, C. [Massachusetts Inst. of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139-4307 (United States)

2012-07-01T23:59:59.000Z

124

Geology Major www.geology.pitt.edu/undergraduate/geology.html  

E-Print Network [OSTI]

Geology Major www.geology.pitt.edu/undergraduate/geology.html Revised: 03/2013 Geology is a scientific discipline that aims to understand every aspect of modern and ancient Earth. A degree in geology the field of geology, environmental and geotechnical jobs exist for people with BS degrees. A master

Jiang, Huiqiang

125

U.S. Department of the Interior U.S. Geological Survey  

E-Print Network [OSTI]

process for the Nation's proposed geologic repository for high-level nuclear waste at Yucca Mountain ountains Yucca Mountain Pahute Mesa Yucca Flat Valley Penoyer Valley Penoyer Valley Nevada Test Site

126

Monte Carlo simulations for generic granite repository studies  

SciTech Connect (OSTI)

In a collaborative study between Los Alamos National Laboratory (LANL) and Sandia National Laboratories (SNL) for the DOE-NE Office of Fuel Cycle Technologies Used Fuel Disposition (UFD) Campaign project, we have conducted preliminary system-level analyses to support the development of a long-term strategy for geologic disposal of high-level radioactive waste. A general modeling framework consisting of a near- and a far-field submodel for a granite GDSE was developed. A representative far-field transport model for a generic granite repository was merged with an integrated systems (GoldSim) near-field model. Integrated Monte Carlo model runs with the combined near- and farfield transport models were performed, and the parameter sensitivities were evaluated for the combined system. In addition, a sub-set of radionuclides that are potentially important to repository performance were identified and evaluated for a series of model runs. The analyses were conducted with different waste inventory scenarios. Analyses were also conducted for different repository radionuelide release scenarios. While the results to date are for a generic granite repository, the work establishes the method to be used in the future to provide guidance on the development of strategy for long-term disposal of high-level radioactive waste in a granite repository.

Chu, Shaoping [Los Alamos National Laboratory; Lee, Joon H [SNL; Wang, Yifeng [SNL

2010-12-08T23:59:59.000Z

127

Hydrogeologic effects of natural disruptive events on nuclear waste repositories  

SciTech Connect (OSTI)

Some possible hydrogeologic effects of disruptive events that may affect repositories for nuclear wastte are described. A very large number of combinations of natural events can be imagined, but only those events which are judged to be most probable are covered. Waste-induced effects are not considered. The disruptive events discussed above are placed into four geologic settings. Although the geology is not specific to given repository sites that have been considered by other agencies, the geology has been generalized from actual field data and is, therefore, considered to be physically reasonable. The geologic settings considered are: (1) interior salt domes of the Gulf Coast, (2) bedded salt of southeastern New Mexico, (3) argillaceous rocks of southern Nevanda, and (4) granitic stocks of the Basin and Range Province. Log-normal distributions of permeabilities of rock units are given for each region. Chapters are devoted to: poresity and permeability of natural materials, regional flow patterns, disruptive events (faulting, dissolution of rock forming minerals, fracturing from various causes, rapid changes of hydraulic regimen); possible hydrologic effects of disruptive events; and hydraulic fracturing.

Davis, S.N.

1980-06-01T23:59:59.000Z

128

Final Supplemental Environmental Impact Statement for a Geologic Repository  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES ANDIndustrialEnergyFinal FY 2009 NEUP RDFinal Site-Widefor the

129

Geological flows  

E-Print Network [OSTI]

In this paper geology and planetology are considered using new conceptual basis of high-speed flow dynamics. Recent photo technics allow to see all details of a flow, 'cause the flow is static during very short time interval. On the other hand, maps and images of many planets are accessible. Identity of geological flows and high-speed gas dynamics is demonstrated. There is another time scale, and no more. All results, as far as the concept, are new and belong to the author. No formulae, pictures only.

Yu. N. Bratkov

2008-11-19T23:59:59.000Z

130

Hydrologic Nuclide Transport Models in Cyder, A Geologic Disposal Software Library - 13328  

SciTech Connect (OSTI)

Component level and system level abstraction of detailed computational geologic repository models have resulted in four rapid computational models of hydrologic radionuclide transport at varying levels of detail. Those models are described, as is their implementation in Cyder, a software library of interchangeable radionuclide transport models appropriate for representing natural and engineered barrier components of generic geology repository concepts. A proof of principle demonstration was also conducted in which these models were used to represent the natural and engineered barrier components of a repository concept in a reducing, homogenous, generic geology. This base case demonstrates integration of the Cyder open source library with the Cyclus computational fuel cycle systems analysis platform to facilitate calculation of repository performance metrics with respect to fuel cycle choices. (authors)

Huff, Kathryn D. [Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL (United States)] [Argonne National Laboratory, 9700 S. Cass Ave, Argonne, IL (United States)

2013-07-01T23:59:59.000Z

131

Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste Repository  

E-Print Network [OSTI]

Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste-Malabry, France Key words: waste repository, geological disposal, thermo- hydraulic modeling Introduction The most developed a sequential model to predict the coupled thermo-hydraulic processes at a cell-scale radioactive

Boyer, Edmond

132

Environmental effects on corrosion in the Tuff repository  

SciTech Connect (OSTI)

Cortest Columbus is investigating the long-term performance of container materials used for high-level waste packages as part of the information needed by the Nuclear Regulatory Commission to assess the Department of Energy`s application to construct a geologic repository for high-level radioactive waste. The scope of work consists of employing short-term techniques, to examine a wide range of possible failure modes. Long-term tests are being used to verify and further examine specific failure modes identified as important by the short-term studies. The original focus of the program was on the salt repository but the emphasis was shifted to the Tuff repository. This report summarizes the results of a literature survey performed under Task 1 of the program. The survey focuses on the influence of environmental variables on the corrosion behavior of candidate container materials for the Tuff repository. Environmental variables considered include: radiation, thermal and microbial effects. 80 refs., 44 figs., 44 tabs.

Beavers, J.A.; Thompson, N.G. [Cortest Columbus, Inc., OH (USA)

1990-02-01T23:59:59.000Z

133

Materials Characterization Center state-of-the-art report on corrosion data pertaining to metallic barriers for nuclear-waste repositories  

SciTech Connect (OSTI)

A compilation of published corrosion data on metals that have been suggested as canisters and overpack materials is presented. The data were categorized according to the solutions used in testing and divided into two parts: high-ionic strength solutions (such as seawater and brine) and low-ionic-strength waters (such as basalt and tuff waters). This distinction was made primarily because of the general difference in aggressiveness of these solutions with respect to general corrosion. A considerable amount of data indicated that titanium alloys have acceptably low uniform corrosion rates in anticipated repository sites; the other possible corrosion failure modes for titanium alloys, such as stress corrosion cracking and delayed failure due to hydrogen, have not been sufficiently studied to make any similar conclusions about lifetime with respect to these particular degradation processes. Other data suggested that iron-base alloys are sufficiently resistant to corrosion in basalt and tuff waters, although the effects of radiation and radiation combined with elevated temperature have not been reported in enough detail to conclusively qualify iron-base alloys for any particular barrier thickness in regard to uniform corrosion rate. The effect of overpack size on corrosion rate has been given little attention. A review of long-term underground data indicated that temperature and accessibility to oxygen were too different for deep geologic repositories to make the underground corrosion data directly applicable. However, the characteristics of corrosion attack, statistical treatment of data, and kinetics of corrosion showed that corrosion proceeds in a systematic and predictable way.

Merz, M.D.

1982-10-01T23:59:59.000Z

134

Waste Isolation Safety Assessment Program. Task 4. Third Contractor Information Meeting. [Adsorption-desorption on geological media  

SciTech Connect (OSTI)

The study subject of this meeting was the adsorption and desorption of radionuclides on geologic media under repository conditions. This volume contans eight papers. Separate abstracts were prepared for all eight papers. (DLC)

Not Available

1980-06-01T23:59:59.000Z

135

Why West Cumbria is unsuitable for a deep  

E-Print Network [OSTI]

, with current water production Wells Typical geology in northern Allerdale ? LEGAL CHALLENGE #12;(Oil and gasWhy West Cumbria is unsuitable for a deep geological nuclear waste facility: Allerdale International aspects Guidelines What other countries do Geology of Allerdale Political/scientific manipulation

136

HYDROMECHANICAL RESPONSE TO A MINE BY TEST EXPERIMENT IN DEEP CLAYSTONE  

E-Print Network [OSTI]

radioactifs, France ABSTRACT In order to demonstrate the feasibility of radioactive waste repository in deep radioactive waste management agency) in eastern France, in a Callovo-Oxfordian claystone. 15 boreholes were the feasibility of a radioactive waste repository in the claystone formation, the French national radioactive

Boyer, Edmond

137

Implementing Geological Disposal of Radioactive Waste Technology Platform From the Strategic Research Agenda to its Deployment - 12015  

SciTech Connect (OSTI)

Several European waste management organizations (WMOs) have initiated a technology platform for accelerating the implementation of deep geological disposal of radioactive waste in Europe. The most advanced waste management programmes in Europe (i.e. Finland, Sweden, and France) have already started or are prepared to start the licensing process of deep geological disposal facilities within the next decade. A technology platform called Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) was launched in November 2009. A shared vision report for the platform was published stating that: 'Our vision is that by 2025, the first geological disposal facilities for spent fuel, high-level waste, and other long-lived radioactive waste will be operating safely in Europe'. In 2011, the IGD-TP had eleven WMO members and about 70 participants from academia, research, and the industry committed to its vision. The IGD-TP has started to become a tool for reducing overlapping work, to produce savings in total costs of research and implementation and to make better use of existing competence and research infrastructures. The main contributor to this is the deployment of the IGD-TP's newly published Strategic Research Agenda (SRA). The work undertaken for the SRA defined the pending research, development and demonstration (RD and D) issues and needs. The SRA document describing the identified issues that could be worked on collaboratively was published in July 2011. It is available on the project's public web site (www.igdtp.eu). The SRA was organized around 7 Key Topics covering the Safety Case, Waste forms and their behaviour, Technical feasibility and long-term performance of repository components, Development strategy of the repository, Safety of construction and operations, Monitoring, and Governance and stakeholder involvement. Individual Topics were prioritized within the Key Topics. Cross-cutting activities like Education and Training or Knowledge Management as well as activities remaining specific for the WMOs were as well identified in the document. For example, each WMO has to develop their own waste acceptance rules, and plan for the economics and the funding of their waste management programmes. The challenge at hand for the IGD-TP is to deploy the SRA. This is carried out by agreeing on a Deployment Plan (DP) that guides organizing the concrete joint activities between the WMOs and the other participants of the IGD-TP. The first DP points out the coordinated RD and D projects and other activities that need to be launched to produce these results over the next four to five years (by the end of 2016). The DP also describes general principles for how the joint work can be organised and funded. (authors)

Ouzounian, P. [ANDRA, Chatenay-Malabry (France); Palmu, Marjatta [Posiva Oy, Eurajoki (Finland); Eng, Torsten [SKB, Stockholm (Sweden)

2012-07-01T23:59:59.000Z

138

An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes  

E-Print Network [OSTI]

Deep boreholes, 3 to 5 km into igneous rock, such as granite, are evaluated for next- generation repository use in the disposal of spent nuclear fuel and other high level waste. The primary focus is on the stability and ...

Anderson, Victoria Katherine, 1980-

2004-01-01T23:59:59.000Z

139

Statistical approaches to leak detection for geological sequestration  

E-Print Network [OSTI]

Geological sequestration has been proposed as a way to remove CO? from the atmosphere by injecting it into deep saline aquifers. Detecting leaks to the atmosphere will be important for ensuring safety and effectiveness of ...

Haidari, Arman S

2011-01-01T23:59:59.000Z

140

Geologic Framework Model Analysis Model Report  

SciTech Connect (OSTI)

The purpose of this report is to document the Geologic Framework Model (GFM), Version 3.1 (GFM3.1) with regard to data input, modeling methods, assumptions, uncertainties, limitations, and validation of the model results, qualification status of the model, and the differences between Version 3.1 and previous versions. The GFM represents a three-dimensional interpretation of the stratigraphy and structural features of the location of the potential Yucca Mountain radioactive waste repository. The GFM encompasses an area of 65 square miles (170 square kilometers) and a volume of 185 cubic miles (771 cubic kilometers). The boundaries of the GFM were chosen to encompass the most widely distributed set of exploratory boreholes (the Water Table or WT series) and to provide a geologic framework over the area of interest for hydrologic flow and radionuclide transport modeling through the unsaturated zone (UZ). The depth of the model is constrained by the inferred depth of the Tertiary-Paleozoic unconformity. The GFM was constructed from geologic map and borehole data. Additional information from measured stratigraphy sections, gravity profiles, and seismic profiles was also considered. This interim change notice (ICN) was prepared in accordance with the Technical Work Plan for the Integrated Site Model Process Model Report Revision 01 (CRWMS M&O 2000). The constraints, caveats, and limitations associated with this model are discussed in the appropriate text sections that follow. The GFM is one component of the Integrated Site Model (ISM) (Figure l), which has been developed to provide a consistent volumetric portrayal of the rock layers, rock properties, and mineralogy of the Yucca Mountain site. The ISM consists of three components: (1) Geologic Framework Model (GFM); (2) Rock Properties Model (RPM); and (3) Mineralogic Model (MM). The ISM merges the detailed project stratigraphy into model stratigraphic units that are most useful for the primary downstream models and the repository design. These downstream models include the hydrologic flow models and the radionuclide transport models. All the models and the repository design, in turn, will be incorporated into the Total System Performance Assessment (TSPA) of the potential radioactive waste repository block and vicinity to determine the suitability of Yucca Mountain as a host for the repository. The interrelationship of the three components of the ISM and their interface with downstream uses are illustrated in Figure 2.

R. Clayton

2000-12-19T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Summary report of first and foreign high-level waste repository concepts; Technical report, working draft 001  

SciTech Connect (OSTI)

Reference repository concepts designs adopted by domestic and foreign waste disposal programs are reviewed. Designs fall into three basic categories: deep borehole from the surface; disposal in boreholes drilled from underground excavations; and disposal in horizontal tunnels or drifts. The repository concepts developed in Sweden, Switzerland, Finland, Canada, France, Japan, United Kingdom, Belgium, Italy, Holland, Denmark, West Germany and the United States are described. 140 refs., 315 figs., 19 tabs.

Hanke, P.M.

1987-11-04T23:59:59.000Z

142

A Handbook for Geology Students Why study Geology?.............................................................................................3  

E-Print Network [OSTI]

1 A Handbook for Geology Students #12;2 Contents Why study Geology ..................................................................................7 Why Appalachian Geology?................................................................................10 Geology Faculty and Staff

Thaxton, Christopher S.

143

Co2 geological sequestration  

SciTech Connect (OSTI)

Human activities are increasingly altering the Earth's climate. A particular concern is that atmospheric concentrations of carbon dioxide (CO{sub 2}) may be rising fast because of increased industrialization. CO{sub 2} is a so-called ''greenhouse gas'' that traps infrared radiation and may contribute to global warming. Scientists project that greenhouse gases such as CO{sub 2} will make the arctic warmer, which would melt glaciers and raise sea levels. Evidence suggests that climate change may already have begun to affect ecosystems and wildlife around the world. Some animal species are moving from one habitat to another to adapt to warmer temperatures. Future warming is likely to exceed the ability of many species to migrate or adjust. Human production of CO{sub 2} from fossil fuels (such as at coal-fired power plants) is not likely to slow down soon. It is urgent to find somewhere besides the atmosphere to put these increased levels of CO{sub 2}. Sequestration in the ocean and in soils and forests are possibilities, but another option, sequestration in geological formations, may also be an important solution. Such formations could include depleted oil and gas reservoirs, unmineable coal seams, and deep saline aquifers. In many cases, injection of CO2 into a geological formation can enhance the recovery of hydrocarbons, providing value-added byproducts that can offset the cost of CO{sub 2} capture and sequestration. Before CO{sub 2} gas can be sequestered from power plants and other point sources, it must be captured. CO{sub 2} is also routinely separated and captured as a by-product from industrial processes such as synthetic ammonia production, H{sub 2} production, and limestone calcination. Then CO{sub 2} must be compressed into liquid form and transported to the geological sequestration site. Many power plants and other large emitters of CO{sub 2} are located near geological formations that are amenable to CO{sub 2} sequestration.

Xu, Tianfu

2004-11-18T23:59:59.000Z

144

System description of the Repository-Only System for the FY 1990 systems integration program studies. [CONTAINS GLOSSARY  

SciTech Connect (OSTI)

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs.

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01T23:59:59.000Z

145

Deep Web Web Deep Web Web  

E-Print Network [OSTI]

Deep Web 100872 Deep Web Web Deep Web Web Web Deep Web Deep Web TP391 A Uncertain Schema Matching in Deep Web Integration Service JIANG Fang-Jiao MENG Xiao-Feng JIA Lin-Lin (School of Information, Renmin University of China, Beijing, 100872) Abstract: With increasing of Deep Web, providing

146

Conceptual model for regional radionuclide transport from a salt dome repository: a technical memorandum  

SciTech Connect (OSTI)

Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.

Kier, R.S.; Showalter, P.A.; Dettinger, M.D.

1980-05-30T23:59:59.000Z

147

Sub-Seabed Repository for Nuclear Waste - a Strategic Alternative - 13102  

SciTech Connect (OSTI)

It was recognized at the outset of nuclear power generation in the 1950's that the waste products would require isolation away from humans for periods in excess of 10,000 years. After years studying alternatives, the DOE recommended pursuing the development of a SNF/HLW disposal facility within Yucca Mountain in the desert of Nevada. That recommendation became law with passage of the NWPAA, effectively stopping development of other approaches to the waste problem. In the face of political resistance from the state of Nevada, the 2010 decision to withdraw the license application for the geologic repository at Yucca Mountain has delayed further the most mature option for safe, long-term disposal of SNF and HLW. It is time to revisit an alternative option, sub-seabed disposal within the US Exclusive Economic Zone (EEZ), which would permanently sequester waste out of the biosphere, and out of the reach of saboteurs or terrorists. A proposal is made for a full scale pilot project to demonstrate burying radioactive waste in stable, deep ocean sediments. While much of the scientific work on pelagic clays has been done to develop a sub-seabed waste sequestration capability, this proposal introduces technology from non-traditional sources such as riser-less ocean drilling and the Navy's Sound Surveillance System. The political decisions affecting the issue will come down to site selection and a thorough understanding of comparative risks. The sub-seabed sequestration of nuclear waste has the potential to provide a robust solution to a critical problem for this clean and reliable energy source. (authors)

McAllister, Keith R. [Department of the Navy, 15 Turkey Foot Court, Darnestown, MD 20878 (United States)] [Department of the Navy, 15 Turkey Foot Court, Darnestown, MD 20878 (United States)

2013-07-01T23:59:59.000Z

148

GEOLOGY (GEOL) Robinson Foundation  

E-Print Network [OSTI]

177Geology GEOLOGY (GEOL) Robinson Foundation PROFESSOR HARBOR ASSOCIATE PROFESSORS KNAPP, CONNORS ASSISTANT PROFESSORS GREER, RAHL MAJORS BACHELOR OF SCIENCE A major in geology leading to a Bachelor of Science degree consists of 50 credits as follows: 1. Geology 160, 185, 211, 311, 330, 350

Dresden, Gregory

149

Regional Geologic Map  

SciTech Connect (OSTI)

Shaded relief base with Hot Pot project area, generalized geology, selected mines, and major topographic features

Lane, Michael

2013-06-28T23:59:59.000Z

150

Regional Geologic Map  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

Shaded relief base with Hot Pot project area, generalized geology, selected mines, and major topographic features

Lane, Michael

151

The Application of Performance Assessment to Make Regulatory and Operational Changes in an Operating Nuclear Waste Repository  

SciTech Connect (OSTI)

This paper describes how performance assessment (PA) is used to support changes to the regulatory basis of the Waste Isolation Pilot Plant (WIPP). The WIPP, located near Carlsbad, New Mexico is operated by the U.S. Department of Energy (DOE) as the nation's only deep geologic repository for the disposal of transuranic nuclear waste. In 1998, the Environmental Protection Agency (EPA) certified that the WIPP met the performance requirements of 40 CFR Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes. A PA analysis of long term (10,000 year) repository performance successfully demonstrated that the probability and consequences of potential long-term releases of radionuclides to the accessible environment would be well below the established limits. These results were key in obtaining WIPP's initial certification, allowing the first shipment and disposal of nuclear waste in March of 1999. As disposal operations have taken place over the last eight years, changes have been identified in the regulatory and operational realms of the facility that would enhance waste disposal efficiency. Such changes, however, cannot be made without prior consent of the EPA. Therefore, changes planned by the DOE must be thoroughly described and supported by varying degrees of the same type of analyses that were conducted to demonstrate the WIPP's containment capabilities as presented in the initial compliance application submitted to EPA in 1996. Such analyses are used to identify the impacts or benefits of implementing the planned change. The DOE has successfully used performance assessment analyses for the approval of changes such as: 1) the disposal of super-compacted waste forms, and; 2) the adoption of new parameters and modeling assumptions In some cases the planned changes are simpler in nature than those listed above, and therefore only require targeted or simplified PA analyses to demonstrate the effect on performance. Targeted analyses have been used to successfully gain approval of the following: 1) a reduction in the amount of magnesium oxide (MgO) chemical buffer backfill that must be emplaced in the repository 2) a change in the repository mining/disposal horizon In addition to these approved changes, the DOE has used PA analyses to support the following planned change requests that await EPA's approval: 1) panel closure redesign 2) further reduction in the MgO-to-waste ratio Finally, this paper will discuss some of the changes that the DOE is currently preparing and plans to submit to the EPA for approval in the near future. This paper will describe how a set of analytical tools initially used to open the WIPP continues to have a role in making the repository more efficient and adaptable as variations in waste streams, operational demands, and other dynamic forces change the operating environment over time. (authors)

Patterson, R. [Department of Energy, Carlsbad Field Office, Carlsbad, NM (United States); Kirkes, R. [John Hart and Associates, P.A., Albuquerque, NM (United States)

2008-07-01T23:59:59.000Z

152

Thermomechanical response of WIPP repositories  

SciTech Connect (OSTI)

Coarsely zoned STEALTH 2D calculations were used to investigate two candidate WIPP repositories. The grid was designed for one hundred thousand years of response with modest computing costs. As a result, the early time mechanical response was compromised by non-real oscillations that could not be damped completely before a few thousand years. In spite of these oscillations, it was possible to see that the dominant effects of stress and strain peaked between one and two thousand years, at the time of maximum heat in the site. This time corresponded to the condition that the surface heat loss rate balanced the heat generation rate. Though the creep strains were quite small, a large volume of salt was involved and the effects were significant. The peak surface uplift of 75HLW was increased by about 25% due to creep. However, the deviatoric stress relaxation due to creep produced large changes in the stress fields. The Rustler layer survived reasonable failure criterion for the 75HLW case with creep, and failed both in tension and shear, according to these same criterion, when the calculation was repeated without creep. The deviatoric stress fields, with and without salt creep, concentrated near the repository as expected and also in the Rustler layer due to its relatively high Young's modulus compared to the neighboring layers. Since the time of interest is so much smaller than the 100,000 years this calculation was designed to examine, it is possible to model the WIPP stratigraphy in much more detail and still be able to calculate the response for the time of interest. A finer zoned calculation of the response of the WIPP stratigraphy to a repository similar to the 75 K watt/acre repository is modeled in this report. In this calculation the Rustler formation is modeled as a five layered formation using material properties derived from data taken at the Nome site.

Maxwell, D.E.; Wahi, K.K.; Dial, B.

1980-05-01T23:59:59.000Z

153

Nye County, Nevada 1992 nuclear waste repository program: Program overview. Final report  

SciTech Connect (OSTI)

The purpose of this document is to provide an overview of the Nye County FY92 Nuclear Waste Repository Program (Program). Funds to pay for Program costs will come from the Federal Nuclear Waste Fund, which was established under the Nuclear Waste Policy Act of 1982 (NWPA). In early 1983, the Yucca Mountain was identified as a potentially suitable site for the nation`s first geologic repository for spent reactor fuel and high-level radioactive waste. Later that year, the Nye County Board of County Commissioners (Board) established the capability to monitor the Federal effort to implement the NWPA and evaluate the potential impacts of repository-related activities on Nye County. Over the last eight years, the County`s program has grown in complexity and cost in order to address DOE`s evolving site characterization studies, and prepare for the potential for facility construction and operation. Changes were necessary as well, in response to Congress`s redirection of the repository program specified in the amendments, to the NWPA approved in 1987. In early FY 1991, the County formally established a project office to plan and implement its program of work. The Repository Project Office`s (RPO) mission and functions are provided in Section 2.0. The RPO organization structure is described in Section 3.0.

NONE

1998-07-01T23:59:59.000Z

154

Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum  

SciTech Connect (OSTI)

This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

1980-05-23T23:59:59.000Z

155

NATURAL GAS RESOURCES IN DEEP SEDIMENTARY BASINS  

SciTech Connect (OSTI)

From a geological perspective, deep natural gas resources are generally defined as resources occurring in reservoirs at or below 15,000 feet, whereas ultra-deep gas occurs below 25,000 feet. From an operational point of view, ''deep'' is often thought of in a relative sense based on the geologic and engineering knowledge of gas (and oil) resources in a particular area. Deep gas can be found in either conventionally-trapped or unconventional basin-center accumulations that are essentially large single fields having spatial dimensions often exceeding those of conventional fields. Exploration for deep conventional and unconventional basin-center natural gas resources deserves special attention because these resources are widespread and occur in diverse geologic environments. In 1995, the U.S. Geological Survey estimated that 939 TCF of technically recoverable natural gas remained to be discovered or was part of reserve appreciation from known fields in the onshore areas and State waters of the United. Of this USGS resource, nearly 114 trillion cubic feet (Tcf) of technically-recoverable gas remains to be discovered from deep sedimentary basins. Worldwide estimates of deep gas are also high. The U.S. Geological Survey World Petroleum Assessment 2000 Project recently estimated a world mean undiscovered conventional gas resource outside the U.S. of 844 Tcf below 4.5 km (about 15,000 feet). Less is known about the origins of deep gas than about the origins of gas at shallower depths because fewer wells have been drilled into the deeper portions of many basins. Some of the many factors contributing to the origin of deep gas include the thermal stability of methane, the role of water and non-hydrocarbon gases in natural gas generation, porosity loss with increasing thermal maturity, the kinetics of deep gas generation, thermal cracking of oil to gas, and source rock potential based on thermal maturity and kerogen type. Recent experimental simulations using laboratory pyrolysis methods have provided much information on the origins of deep gas. Technologic problems are one of the greatest challenges to deep drilling. Problems associated with overcoming hostile drilling environments (e.g. high temperatures and pressures, and acid gases such as CO{sub 2} and H{sub 2}S) for successful well completion, present the greatest obstacles to drilling, evaluating, and developing deep gas fields. Even though the overall success ratio for deep wells is about 50 percent, a lack of geological and geophysical information such as reservoir quality, trap development, and gas composition continues to be a major barrier to deep gas exploration. Results of recent finding-cost studies by depth interval for the onshore U.S. indicate that, on average, deep wells cost nearly 10 times more to drill than shallow wells, but well costs and gas recoveries vary widely among different gas plays in different basins. Based on an analysis of natural gas assessments, many topical areas hold significant promise for future exploration and development. One such area involves re-evaluating and assessing hypothetical unconventional basin-center gas plays. Poorly-understood basin-center gas plays could contain significant deep undiscovered technically-recoverable gas resources.

Thaddeus S. Dyman; Troy Cook; Robert A. Crovelli; Allison A. Henry; Timothy C. Hester; Ronald C. Johnson; Michael D. Lewan; Vito F. Nuccio; James W. Schmoker; Dennis B. Riggin; Christopher J. Schenk

2002-02-05T23:59:59.000Z

156

Focused Crawling of the Deep Web Using Service Class Descriptions  

SciTech Connect (OSTI)

Dynamic Web data sources--sometimes known collectively as the Deep Web--increase the utility of the Web by providing intuitive access to data repositories anywhere that Web access is available. Deep Web services provide access to real-time information, like entertainment event listings, or present a Web interface to large databases or other data repositories. Recent studies suggest that the size and growth rate of the dynamic Web greatly exceed that of the static Web, yet dynamic content is often ignored by existing search engine indexers owing to the technical challenges that arise when attempting to search the Deep Web. To address these challenges, we present DynaBot, a service-centric crawler for discovering and clustering Deep Web sources offering dynamic content. DynaBot has three unique characteristics. First, DynaBot utilizes a service class model of the Web implemented through the construction of service class descriptions (SCDs). Second, DynaBot employs a modular, self-tuning system architecture for focused crawling of the DeepWeb using service class descriptions. Third, DynaBot incorporates methods and algorithms for efficient probing of the Deep Web and for discovering and clustering Deep Web sources and services through SCD-based service matching analysis. Our experimental results demonstrate the effectiveness of the service class discovery, probing, and matching algorithms and suggest techniques for efficiently managing service discovery in the face of the immense scale of the Deep Web.

Rocco, D; Liu, L; Critchlow, T

2004-06-21T23:59:59.000Z

157

Building of multilevel stakeholder consensus in radioactive waste repository siting  

SciTech Connect (OSTI)

This report considers the problem of multilevel consensus building for siting and construction of shared multinational/regional repositories for radioactive waste (RW) deep disposal. In the siting of a multinational repository there appears an essential innovative component of stakeholder consensus building, namely: to reach consent - political, social, economic, ecological - among international partners, in addition to solving the whole set of intra-national consensus building items. An entire partnering country is considered as a higher-level stakeholder - the national stakeholder, represented by the national government, being faced to simultaneous seeking an upward (international) and a downward (intra-national) consensus in a psychologically stressed environment, possibly being characterized by diverse political, economic and social interests. The following theses as a possible interdisciplinary approach towards building of shared understanding and stakeholder consensus on the international scale of RW disposal are forwarded and developed: a) building of international stakeholder consensus would be promoted by activating and diversifying on the international scale multilateral interactions between intra- and international stakeholders, including web-based networks of the RW disposal site investigations and decision-making, as well as networks for international cooperation among government authorities in nuclear safety, b) gradual progress in intergovernmental consensus and reaching multilateral agreements on shared deep repositories will be the result of democratic dialogue, via observing the whole set of various interests and common resolving of emerged controversies by using advanced synergetic approaches of conflict resolution, c) cross-cultural thinking and world perception, mental flexibility, creativity and knowledge are considered as basic prerogatives for gaining a higher level of mutual understanding and consensus for seeking further consensus, for advancing the preparedness to act together, and ultimately - for achieving desired shared goals. It is proposed that self-organized social learning will make it possible to promote adequate perception of risk and prevent, by diminishing uncertainties and unknown factors, social amplification of an imagined risk, as well as to increase the trust level and facilitate more adequate equity perception. The proposed approach to the multilevel stakeholder consensus building on international scale is extrapolated to the present-day activities of siting of such near-surface RW disposal facilities which supposedly could have non-negligible trans-boundary impact. A multilevel stakeholder interaction process is considered for the case of resolving of emerged problems in site selection for the planned near-surface RW repository in vicinity of the Lithuanian-Latvian border foreseen for disposal of short lived low- and intermediate level waste arising from the decommissioning of the Ignalina Nuclear Power Plant. (authors)

Dreimanis, A. [Radiation Safety Centre, Riga LV (Latvia)

2007-07-01T23:59:59.000Z

158

The Geological Research in France - The Dossier 2005 Argile  

SciTech Connect (OSTI)

At the end of fifteen years of research defined by the French act of December 30, 1991 on radwaste management, ANDRA gave a report, 'Dossier Argile 2005', which concluded with the feasibility of a reversible disposal in the argillaceous Callovo-Oxfordian formation studied by means of an underground research laboratory at the Meuse/Haute-Marne site. Starting from source data like the characteristics of the geological medium and the waste inventory, the process followed by ANDRA to achieve this conclusion is of a sequential type, and iterative between concept design, scientific knowledge, in particular that of the phenomenological evolution of the repository and its geological environment from operating period to long term, and safety assessment. The 'Dossier Argile 2005' covers a broad radwaste inventory, ILLW, HLW and Spent Fuel, so that it makes it possible to cover the whole of the technological, scientific and safety topics. This article will give an overview of the geological disposal studies in France and draw the main conclusion of the Dossier 2005 Argile. It will be focused on the near field (engineering components and near field host rock), while considering, if necessary, its integration within the whole system. After a short description of the concepts (including waste inventory and the characteristics of the Meuse/Haute the Marne site) and the functions of the components of repository and geological medium, one will describe, successively, the broad outline of the phenomenological evolution of repository and the geological medium in near field, in particular, by releasing the time scales of processes and uncertainties of knowledge. On this basis, one will indicate the safety scenarios that were considered and the broad outline of performance and dose calculations. Lessons learn from the Dossier 2005 Argile will be discussed and perspectives and priorities for future will be indicated. (authors)

Plas, Frederic; Wendling, Jacques [DS/IT, Andra, Parc de la Croix Blanche, 1-7 rue Jean Monnet, Chatenay-Malabry, 92298 (France)

2007-07-01T23:59:59.000Z

159

Immersion studies on candidate container alloys for the Tuff Repository  

SciTech Connect (OSTI)

Cortest Columbus Technologies (CC Technologies) is investigating the long-term performance of container materials used for high-level radioactive waste packages. This information is being developed for the Nuclear Regulatory Commission to aid in their assessment of the Department of Energy`s application to construct a geologic repository for disposal of high-level radioactive waste. This report summarizes the results of exposure studies performed on two copper-base and two Fe-Cr-Ni alloys in simulated Tuff Repository conditions. Testing was performed at 90{degrees}C in three environments; simulated J-13 well water, and two environments that simulated the chemical effects resulting from boiling and irradiation of the groundwater. Creviced specimens and U-bends were exposed to liquid, to vapor above the condensed phase, and to alternate immersion. A rod specimen was used to monitor corrosion at the vapor-liquid interface. The specimens were evaluated by electrochemical, gravimetric, and metallographic techniques following approximately 2000 hours of exposure. Results of the exposure tests indicated that all four alloys exhibited acceptable general corrosion rates in simulated J-13 well water. These rates decreased with time. Incipient pitting was observed under deposits on Alloy 825 and pitting was observed on both Alloy CDA 102 and Alloy CDA 715 in the simulated J-13 well water. No SCC was observed in U-bend specimens of any of the alloys in simulated J-13 well water. 33 refs., 48 figs., 23 tabs.

Beavers, J.A.; Durr, C.L. [Cortest Columbus Technologies, OH (USA)

1991-05-01T23:59:59.000Z

160

Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)  

SciTech Connect (OSTI)

This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.

Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.

1986-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

EXTENDING GEOSPATIAL REPOSITORIES WITH GEOSEMANTIC PROXIMITY FUNCTIONALITIES  

E-Print Network [OSTI]

EXTENDING GEOSPATIAL REPOSITORIES WITH GEOSEMANTIC PROXIMITY FUNCTIONALITIES TO FACILITATE THE INTEROPERABILITY OF GEOSPATIAL DATA Jean Brodeur a, b , Yvan Bédard a a Centre for Research in Geomatics, Laval.Bedard@scg.ulaval.ca Commission IV, WG IV/1 KEY WORDS: Geospatial data interoperability, Geospatial repository, Geosemantic

162

An Assessment of Image Quality in Geology Works from the HathiTrust Digital Library  

E-Print Network [OSTI]

This study assesses the quality of both images and text in a sample from the 2,180 works on geology from the HathiTrust Digital Library (multi-institutional digital repository)--an outgrowth of the Michigan Digitization Project and partnership...

McEathron, Scott R.

2011-10-27T23:59:59.000Z

163

Geologic Maps and Structures Name ______________________________ Geology 100 Harbor section  

E-Print Network [OSTI]

Geologic Maps and Structures Name ______________________________ Geology 100 ­ Harbor section The objectives of this lab are for you to learn the basic geologic structures in 3-D and to develop some facility in interpreting the nature of geologic structures from geologic maps and geologic cross sections. A big part

Harbor, David

164

BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES  

E-Print Network [OSTI]

#12;BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 33, Part 1 CONTENTS Tertiary Geologic History Geology of the Deadman Canyon 7112-Minute Quadrangle, Carbon County, Utah, Utah. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .James Douglas Smith 135 Geology

Seamons, Kent E.

165

Coupling geothermal energy capture with carbon dioxide sequestration in naturally permeable, porous geologic formations  – a novel approach for expanding geothermal energy utilization.  

E-Print Network [OSTI]

??This thesis research presents a new method to harness geothermal energy by combining it with geologic carbon dioxide (CO2) sequestration. CO2 is injected into deep,… (more)

Randolph, Jimmy Bryan

2011-01-01T23:59:59.000Z

166

Temperature-package power correlations for open-mode geologic disposal concepts.  

SciTech Connect (OSTI)

Logistical simulation of spent nuclear fuel (SNF) management in the U.S. combines storage, transportation and disposal elements to evaluate schedule, cost and other resources needed for all major operations leading to final geologic disposal. Geologic repository reference options are associated with limits on waste package thermal power output at emplacement, in order to meet limits on peak temperature for certain key engineered and natural barriers. These package power limits are used in logistical simulation software such as CALVIN, as threshold requirements that must be met by means of decay storage or SNF blending in waste packages, before emplacement in a repository. Geologic repository reference options include enclosed modes developed for crystalline rock, clay or shale, and salt. In addition, a further need has been addressed for open modes in which SNF can be emplaced in a repository, then ventilated for decades or longer to remove heat, prior to permanent repository closure. For each open mode disposal concept there are specified durations for surface decay storage (prior to emplacement), repository ventilation, and repository closure operations. This study simulates those steps for several timing cases, and for SNF with three fuel-burnup characteristics, to develop package power limits at which waste packages can be emplaced without exceeding specified temperature limits many years later after permanent closure. The results are presented in the form of correlations that span a range of package power and peak postclosure temperature, for each open-mode disposal concept, and for each timing case. Given a particular temperature limit value, the corresponding package power limit for each case can be selected for use in CALVIN and similar tools.

Hardin, Ernest L.

2013-02-01T23:59:59.000Z

167

Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)  

SciTech Connect (OSTI)

The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, calcium ions, and galvanic coupling to less noble metals are further considered. It is concluded that, as far as materials degradation is concerned, the materials and design adopted in the U.S. Yucca Mountain Project will provide sufficient safety margins within the 10,000-years regulatory period.

F. Hua; P. Pasupathi; N. Brown; K. Mon

2005-09-19T23:59:59.000Z

168

Geological problems in radioactive waste isolation  

SciTech Connect (OSTI)

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Witherspoon, P.A. (ed.)

1991-01-01T23:59:59.000Z

169

Fundamental properties of monolithic bentonite buffer material formed by cold isostatic pressing for high-level radioactive waste repository  

SciTech Connect (OSTI)

The methods of fabrication, handling, and emplacement of engineered barriers used in a deep geological repository for high level radioactive waste should be planned as simply as possible from the engineering and economic viewpoints. Therefore, a new concept of a monolithic buffer material around a waste package have been proposed instead of the conventional concept with the use of small blocks, which would decrease the cost for buffer material. The monolithic buffer material is composed of two parts of highly compacted bentonite, a cup type body and a cover. As the forming method of the monolithic buffer material, compaction by the cold isostatic pressing process (CIP) has been employed. In this study, monolithic bentonite bodies with the diameter of about 333 mm and the height of about 455 mm (corresponding to the approx. 1/5 scale for the Japanese reference concept) were made by the CIP of bentonite powder. The dry densities: {rho}d of the bodies as a whole were measured and the small samples were cut from several locations to investigate the density distribution. The swelling pressure and hydraulic conductivity as function of the monolithic body density for CIP-formed specimens were also measured. High density ({rho}d: 1.4--2.0 Mg/m{sup 3}) and homogeneous monolithic bodies were formed by the CIP. The measured results of the swelling pressure (3--15 MPa) and hydraulic conductivity (0.5--1.4 x 10{sup {minus}13} m/s) of the specimens were almost the same as those for the uniaxial compacted bentonite in the literature. It is shown that the vacuum hoist system is an applicable handling method for emplacement of the monolithic bentonite.

Kawakami, S.; Yamanaka, Y.; Kato, K.; Asano, H.; Ueda, H.

1999-07-01T23:59:59.000Z

170

Assessment of the geothermal resources of Indiana based on existing geologic data  

SciTech Connect (OSTI)

The general geology of Indiana is presented including the following: physiography, stratigraphy, and structural features. The following indicators of geothermal energy are discussed: heat flow and thermal gradient, geothermal occurrences, seismic activity, geochemistry, and deep sedimentary basins. (MHR)

Vaught, T.L.

1980-12-01T23:59:59.000Z

171

Preliminary Geologic Characterization of West Coast States for Geologic Sequestration  

SciTech Connect (OSTI)

Characterization of geological sinks for sequestration of CO{sub 2} in California, Nevada, Oregon, and Washington was carried out as part of Phase I of the West Coast Regional Carbon Sequestration Partnership (WESTCARB) project. Results show that there are geologic storage opportunities in the region within each of the following major technology areas: saline formations, oil and gas reservoirs, and coal beds. The work focused on sedimentary basins as the initial most-promising targets for geologic sequestration. Geographical Information System (GIS) layers showing sedimentary basins and oil, gas, and coal fields in those basins were developed. The GIS layers were attributed with information on the subsurface, including sediment thickness, presence and depth of porous and permeable sandstones, and, where available, reservoir properties. California offers outstanding sequestration opportunities because of its large capacity and the potential of value-added benefits from enhanced oil recovery (EOR) and enhanced gas recovery (EGR). The estimate for storage capacity of saline formations in the ten largest basins in California ranges from about 150 to about 500 Gt of CO{sub 2}, depending on assumptions about the fraction of the formations used and the fraction of the pore volume filled with separate-phase CO{sub 2}. Potential CO{sub 2}-EOR storage was estimated to be 3.4 Gt, based on a screening of reservoirs using depth, an API gravity cutoff, and cumulative oil produced. The cumulative production from gas reservoirs (screened by depth) suggests a CO{sub 2} storage capacity of 1.7 Gt. In Oregon and Washington, sedimentary basins along the coast also offer sequestration opportunities. Of particular interest is the Puget Trough Basin, which contains up to 1,130 m (3,700 ft) of unconsolidated sediments overlying up to 3,050 m (10,000 ft) of Tertiary sedimentary rocks. The Puget Trough Basin also contains deep coal formations, which are sequestration targets and may have potential for enhanced coal bed methane recovery (ECBM).

Larry Myer

2005-09-29T23:59:59.000Z

172

Department of Geology and Geological Engineering University of Mississippi Announces  

E-Print Network [OSTI]

Department of Geology and Geological Engineering University of Mississippi Announces Krista Pursuing a degree within the Geology & Geological Engineering department Record of financial need the University of Mississippi with a Bachelor of Science degree in geological engineering in 1982. After earning

Elsherbeni, Atef Z.

173

Geologic Maps and Structures Name ______________________________ Geology 100 Harbor section  

E-Print Network [OSTI]

Geologic Maps and Structures Name ______________________________ Geology 100 ­ Harbor section Read Ch. 7 before you begin. The objectives of this lab are for you to learn the basic geologic structures in 3-D and to develop some facility in interpreting the nature of geologic structures from geologic

Harbor, David

174

Environmental Geology Major www.geology.pitt.edu/uprogs.html  

E-Print Network [OSTI]

Environmental Geology Major www.geology.pitt.edu/uprogs.html Revised: 04/2004 Environmental geology in environmental geology provides the diverse skills required to work in many different employment settings issues. Within the field of geology, environmental and geotechnical jobs exist for people with BS degrees

Jiang, Huiqiang

175

DSpace: An Open Source Dynamic Digital Repository  

E-Print Network [OSTI]

For the past two years the Massachusetts Institute of Technology (MIT) Libraries and Hewlett-Packard Labs have been collaborating on the development of an open source system called DSpaceâ?¢ that functions as a repository ...

Smith, MacKenzie

176

YUCCA MOUNTAIN PROJECT RECOMMENDATION BY THE SECRETARY OF ENERGY REGARDING THE SUITABILITY OF THE YUCCA MOUNTAIN SITE FOR A REPOSITORY UNDER THE NUCLEAR WASTE POLICY ACT OF 1982  

SciTech Connect (OSTI)

For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that !he Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or ''the Act''), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository. Fifteen years ago, Congress directed the Secretary of Energy to investigate and recommend to the President whether such a repository could be located safely at Yucca Mountain, Nevada. Since then, our country has spent billions of dollars and millions of hours of research endeavoring to answer this question. I have carefully reviewed the product of this study. In my judgment, it constitutes sound science and shows that a safe repository can be sited there. I also believe that compelling national interests counsel in favor of proceeding with this project. Accordingly, consistent with my responsibilities under the NWPA, today I am recommending that Yucca Mountain be developed as the site for an underground repository for spent fuel and other radioactive wastes. The first consideration in my decision was whether the Yucca Mountain site will safeguard the health and safety of the people, in Nevada and across the country, and will be effective in containing at minimum risk the material it is designed to hold. Substantial evidence shows that it will. Yucca Mountain is far and away the most thoroughly researched site of its kind in the world. It is a geologically stable site, in a closed groundwater basin, isolated on thousands of acres of Federal land, and farther from any metropolitan area than the great majority of less secure, temporary nuclear waste storage sites that exist in the country today. This point bears emphasis. We are not confronting a hypothetical problem. We have a staggering amount of radioactive waste in this country--nearly 100,000,000 gallons of high-level nuclear waste and more than 40,000 metric tons of spent nuclear fuel with more created every day. Our choice is not between, on the one hand, a disposal site with costs and risks held to a minimum, and, on the other, a magic disposal system with no costs or risks at all. Instead, the real choice is between a single secure site, deep under the ground at Yucca Mountain, or making do with what we have now or some variant of it--131 aging surface sites, scattered across 39 states. Every one of those sites was built on the assumption that it would be temporary. As time goes by. every one is closer to the limit of its safe life span. And every one is at least a potential security risk--safe for today, but a question mark in decades to come.

NA

2002-03-26T23:59:59.000Z

177

MRS system study for the repository: Yucca Mountain Site Characterization Project; Volume 2  

SciTech Connect (OSTI)

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ``MRS``) on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. This document contains A-D.

Sinagra, T.A. [Bechtel National, Inc., San Francisco, CA (USA); Harig, R. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA)

1990-12-01T23:59:59.000Z

178

EMSL - subsurface geological field  

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

subsurface-geological-field en Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. http:www.emsl.pnl.govemslwebpublicationsmagnesium-behavior-and-s...

179

subsurface geological field | EMSL  

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

field subsurface geological field Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a...

180

The subsurface fluid mechanics of geologic carbon dioxide storage  

E-Print Network [OSTI]

In carbon capture and storage (CCS), CO? is captured at power plants and then injected into deep geologic reservoirs for long-term storage. While CCS may be critical for the continued use of fossil fuels in a carbon-constrained ...

Szulczewski, Michael Lawrence

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Deep Research Submarine  

E-Print Network [OSTI]

The Deep Sea Research Submarine (Figure 1) is a modified VIRGINIA Class Submarine that incorporates a permanently installed Deep Sea Operations Compartment (Figure 2). Table 1 summarizes the characteristics of the Deep ...

Woertz, Jeff

2002-02-01T23:59:59.000Z

182

Coupling fuel cycles with repositories: how repository institutional choices may impact fuel cycle design  

SciTech Connect (OSTI)

The historical repository siting strategy in the United States has been a top-down approach driven by federal government decision making but it has been a failure. This policy has led to dispatching fuel cycle facilities in different states. The U.S. government is now considering an alternative repository siting strategy based on voluntary agreements with state governments. If that occurs, state governments become key decision makers. They have different priorities. Those priorities may change the characteristics of the repository and the fuel cycle. State government priorities, when considering hosting a repository, are safety, financial incentives and jobs. It follows that states will demand that a repository be the center of the back end of the fuel cycle as a condition of hosting it. For example, states will push for collocation of transportation services, safeguards training, and navy/private SNF (Spent Nuclear Fuel) inspection at the repository site. Such activities would more than double local employment relative to what was planned for the Yucca Mountain-type repository. States may demand (1) the right to take future title of the SNF so if recycle became economic the reprocessing plant would be built at the repository site and (2) the right of a certain fraction of the repository capacity for foreign SNF. That would open the future option of leasing of fuel to foreign utilities with disposal of the SNF in the repository but with the state-government condition that the front-end fuel-cycle enrichment and fuel fabrication facilities be located in that state.

Forsberg, C. [Massachusetts Institute of Technology, 77 Massachusetts Ave., Room 24-207A Cambridge, MA 02139 (United States); Miller, W.F. [Texas A.M. University System, MS 3133 College Station, TX 77843-3133 (United States)

2013-07-01T23:59:59.000Z

183

A literature review of coupled thermal-hydrologic-mechanical-chemical processes pertinent to the proposed high-level nuclear waste repository at Yucca Mountain  

SciTech Connect (OSTI)

A literature review has been conducted to determine the state of knowledge available in the modeling of coupled thermal (T), hydrologic (H), mechanical (M), and chemical (C) processes relevant to the design and/or performance of the proposed high-level waste (HLW) repository at Yucca Mountain, Nevada. The review focuses on identifying coupling mechanisms between individual processes and assessing their importance (i.e., if the coupling is either important, potentially important, or negligible). The significance of considering THMC-coupled processes lies in whether or not the processes impact the design and/or performance objectives of the repository. A review, such as reported here, is useful in identifying which coupled effects will be important, hence which coupled effects will need to be investigated by the US Nuclear Regulatory Commission in order to assess the assumptions, data, analyses, and conclusions in the design and performance assessment of a geologic reposit``. Although this work stems from regulatory interest in the design of the geologic repository, it should be emphasized that the repository design implicitly considers all of the repository performance objectives, including those associated with the time after permanent closure. The scope of this review is considered beyond previous assessments in that it attempts with the current state-of-knowledge) to determine which couplings are important, and identify which computer codes are currently available to model coupled processes.

Manteufel, R.D.; Ahola, M.P.; Turner, D.R.; Chowdhury, A.H. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses

1993-07-01T23:59:59.000Z

184

CO2 Geologic Storage (Kentucky)  

Broader source: Energy.gov [DOE]

Division staff, in partnership with the Kentucky Geological Survey (KGS), continued to support projects to investigate and demonstrate the technical feasibility of geologic storage of carbon...

185

THERMAL CONDUCTIVITY OF NON-REPOSITORY LITHOSTRATIGRAPHIC LAYERS  

SciTech Connect (OSTI)

This model report addresses activities described in ''Technical Work Plan for: Near-Field Environment and Transport Thermal Properties and Analysis Reports Integration'' (BSC 2004 [DIRS 171708]). The model develops values for thermal conductivity, and its uncertainty, for the nonrepository layers of Yucca Mountain; in addition, the model provides estimates for matrix porosity and dry bulk density for the nonrepository layers. The studied lithostratigraphic units, as identified in the ''Geologic Framework Model'' (GFM 2000) (BSC 2004 [DIRS 170029]), are the Timber Mountain Group, the Tiva Canyon Tuff, the Yucca Mountain Tuff, the Pah Canyon Tuff, the Topopah Spring Tuff (excluding the repository layers), the Calico Hills Formation, the Prow Pass Tuff, the Bullfrog Tuff, and the Tram Tuff. The deepest model units of the GFM (Tund and Paleozoic) are excluded from this study because no data suitable for model input are available. The parameter estimates developed in this report are used as input to various models and calculations that simulate heat transport through the rock mass. Specifically, analysis model reports that use product output from this report are: (1) Drift-scale coupled processes (DST and TH seepage) models; (2) Drift degradation analysis; (3) Multiscale thermohydrologic model; and (4) Ventilation model and analysis report. In keeping with the methodology of the thermal conductivity model for the repository layers in ''Thermal Conductivity of the Potential Repository Horizon'' (BSC 2004 [DIRS 169854]), the Hsu et al. (1995 [DIRS 158073]) three-dimensional (3-D) cubic model (referred to herein as ''the Hsu model'') was used to represent the matrix thermal conductivity as a function of the four parameters (matrix porosity, thermal conductivity of the saturating fluid, thermal conductivity of the solid, and geometric connectivity of the solid). The Hsu model requires input data from each test specimen to meet three specific conditions: (1) Known value for matrix porosity; (2) Known values for wet and dry thermal conductivity; and (3) The location of the measured specimen in relation to the model stratigraphic unit. The only matrix thermal conductivity values developed are limited to fully saturated and dry conditions. The model does not include the effects of convection and thermal radiation in voids. The model does not include temperature dependence of thermal conductivity, porosity, or bulk density.

R. JONES

2004-10-22T23:59:59.000Z

186

Geologic mapping of the air intake shaft at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The air intake shaft (AS) was geologically mapped from the surface to the Waste Isolation Pilot Plant (WIPP) facility horizon. The entire shaft section including the Mescalero Caliche, Gatuna Formation, Santa Rosa Formation, Dewey Lake Redbeds, Rustler Formation, and Salado Formation was geologically described. The air intake shaft (AS) at the Waste Isolation Pilot Plant (WIPP) site was constructed to provide a pathway for fresh air into the underground repository and maintain the desired pressure balances for proper underground ventilation. It was up-reamed to minimize construction-related damage to the wall rock. The upper portion of the shaft was lined with slip-formed concrete, while the lower part of the shaft, from approximately 903 ft below top of concrete at the surface, was unlined. As part of WIPP site characterization activities, the AS was geologically mapped. The shaft construction method, up-reaming, created a nearly ideal surface for geologic description. Small-scale textures usually best seen on slabbed core were easily distinguished on the shaft wall, while larger scale textures not generally revealed in core were well displayed. During the mapping, newly recognized textures were interpreted in order to refine depositional and post-depositional models of the units mapped. The objectives of the geologic mapping were to: (1) provide confirmation and documentation of strata overlying the WIPP facility horizon; (2) provide detailed information of the geologic conditions in strata critical to repository sealing and operations; (3) provide technical basis for field adjustments and modification of key and aquifer seal design, based upon the observed geology; (4) provide geological data for the selection of instrument borehole locations; (5) and characterize the geology at geomechanical instrument locations to assist in data interpretation. 40 refs., 27 figs., 1 tab.

Holt, R.M.; Powers, D.W. (IT Corporation (USA))

1990-12-01T23:59:59.000Z

187

REMOTE SENSING GEOLOGICAL SURVEY  

E-Print Network [OSTI]

-ASTER that operate in visible, near infrared and short wave infrared wavelengths of electromagnetic spectrum and Reflection Radiometer) Imagery Collection in CPRM Examples of sensors used in the CPRM geologic projects #12

188

Geologic flow characterization using tracer techniques  

SciTech Connect (OSTI)

A new tracer flow-test system has been developed for in situ characterization of geologic formations. This report describes two sets of test equipment: one portable and one for testing in deep formations. Equations are derived for in situ detector calibration, raw data reduction, and flow logging. Data analysis techniques are presented for computing porosity and permeability in unconfined isotropic media, and porosity, permeability and fracture characteristics in media with confined or unconfined two-dimensional flow. The effects of tracer pulse spreading due to divergence, dispersion, and porous formations are also included.

Klett, R. D.; Tyner, C. E.; Hertel, Jr., E. S.

1981-04-01T23:59:59.000Z

189

Jobtong Deep Web Web""Surface WebDeep Web  

E-Print Network [OSTI]

Jobtong Deep Web Web Web Web""Surface WebDeep Web Surface WebDeep Web Web[1] 20007BrightPlanet.comDeep Web[2] Web43,000-96,000Web7,500TB(Surface Web500) UIUC5Deep Web[3]2004Deep Web 307,000366,000-535,000"" Deep Web""Google Yahoo32%Deep Web WAMDMWebDeep WebJobtong Deep Web (Jobtong) Jobtong(, http

190

Uncertainty and sensitivity analysis in the 2008 performance assessment for the proposed repository for high-level radioactive waste at Yucca Mountain, Nevada.  

SciTech Connect (OSTI)

Extensive work has been carried out by the U.S. Department of Energy (DOE) in the development of a proposed geologic repository at Yucca Mountain (YM), Nevada, for the disposal of high-level radioactive waste. As part of this development, an extensive performance assessment (PA) for the YM repository was completed in 2008 [1] and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository [2]. This presentation provides an overview of the conceptual and computational structure of the indicated PA (hereafter referred to as the 2008 YM PA) and the roles that uncertainty analysis and sensitivity analysis play in this structure.

Helton, Jon Craig; Sallaberry, Cedric M.; Hansen, Clifford W.

2010-05-01T23:59:59.000Z

191

The geomechanics of CO{sub 2} storage in deep sedimentary formations  

SciTech Connect (OSTI)

This paper provides a review of the geomechanics and modeling of geomechanics associated with geologic carbon storage (GCS), focusing on storage in deep sedimentary formations, in particular saline aquifers. The paper first introduces the concept of storage in deep sedimentary formations, the geomechanical processes and issues related with such an operation, and the relevant geomechanical modeling tools. This is followed by a more detailed review of geomechanical aspects, including reservoir stress-strain and microseismicity, well integrity, caprock sealing performance, and the potential for fault reactivation and notable (felt) seismic events. Geomechanical observations at current GCS field deployments, mainly at the In Salah CO2 storage project in Algeria, are also integrated into the review. The In Salah project, with its injection into a relatively thin, low-permeability sandstone is an excellent analogue to the saline aquifers that might be used for large scale GCS in parts of Northwest Europe, the U.S. Midwest, and China. Some of the lessons learned at In Salah related to geomechanics are discussed, including how monitoring of geomechanical responses is used for detecting subsurface geomechanical changes and tracking fluid movements, and how such monitoring and geomechanical analyses have led to preventative changes in the injection parameters. Recently, the importance of geomechanics has become more widely recognized among GCS stakeholders, especially with respect to the potential for triggering notable (felt) seismic events and how such events could impact the long-term integrity of a CO{sub 2} repository (as well as how it could impact the public perception of GCS). As described in the paper, to date, no notable seismic event has been reported from any of the current CO{sub 2} storage projects, although some unfelt microseismic activities have been detected by geophones. However, potential future commercial GCS operations from large power plants will require injection at a much larger scale. For such largescale injections, a staged, learn-as-you-go approach is recommended, involving a gradual increase of injection rates combined with continuous monitoring of geomechanical changes, as well as siting beneath a multiple layered overburden for multiple flow barrier protection, should an unexpected deep fault reactivation occur.

Rutqvist, J.

2011-11-01T23:59:59.000Z

192

The consequences of failure should be considered in siting geologic carbon sequestration projects  

SciTech Connect (OSTI)

Geologic carbon sequestration is the injection of anthropogenic CO{sub 2} into deep geologic formations where the CO{sub 2} is intended to remain indefinitely. If successfully implemented, geologic carbon sequestration will have little or no impact on terrestrial ecosystems aside from the mitigation of climate change. However, failure of a geologic carbon sequestration site, such as large-scale leakage of CO{sub 2} into a potable groundwater aquifer, could cause impacts that would require costly remediation measures. Governments are attempting to develop regulations for permitting geologic carbon sequestration sites to ensure their safety and effectiveness. At present, these regulations focus largely on decreasing the probability of failure. In this paper we propose that regulations for the siting of early geologic carbon sequestration projects should emphasize limiting the consequences of failure because consequences are easier to quantify than failure probability.

Price, P.N.; Oldenburg, C.M.

2009-02-23T23:59:59.000Z

193

Chapter 14 Geology and Soils  

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

activity, could affect the project. Related information can be found in Chapter 15, Water and Appendix J, Geologic Hazard Assessment. 14.1 Affected Environment 14.1.1 Geology...

194

GEOLOGY, November 2008 871 INTRODUCTION  

E-Print Network [OSTI]

GEOLOGY, November 2008 871 INTRODUCTION A number of geodetic and morphotectonic techniques. 2). Geology, November 2008; v. 36; no. 11; p. 871­874; doi: 10.1130/G25073A.1; 3 figures; Data

Avouac, Jean-Philippe

195

Fukushima Daiichi Information Repository FY13 Status  

SciTech Connect (OSTI)

The accident at the Fukushima Daiichi nuclear power station in Japan is one of the most serious in commercial nuclear power plant operating history. Much will be learned that may be applicable to the U.S. reactor fleet, nuclear fuel cycle facilities, and supporting systems, and the international reactor fleet. For example, lessons from Fukushima Daiichi may be applied to emergency response planning, reactor operator training, accident scenario modeling, human factors engineering, radiation protection, and accident mitigation; as well as influence U.S. policies towards the nuclear fuel cycle including power generation, and spent fuel storage, reprocessing, and disposal. This document describes the database used to establish a centralized information repository to store and manage the Fukushima data that has been gathered. The data is stored in a secured (password protected and encrypted) repository that is searchable and available to researchers at diverse locations.

Curtis Smith; Cherie Phelan; Dave Schwieder

2013-09-01T23:59:59.000Z

196

The German quality system for waste repositories  

SciTech Connect (OSTI)

The Bundesamt fuer Strahlenschutz (BfS)--Federal Office for Radiation protection--has to guarantee that the requirements resulting from different regulations concerning planning, design, construction, operation and decommissioning of a waste repository are fulfilled. In addition, the results of the safety assessments lead to nuclear-specific requirements on the design of the plant as well as to requirements on the radioactive waste packages intended to be disposed of. Therefore, the implementation of a quality assurance (QA) and quality control (QC) system is an essential task in order to ensure that the designed quality is achieved so that the necessary precaution against damage is taken. In this paper, a detailed description of QA and QC to be applied to the planned Konrad repository as well as the basic principles and the present status of the waste package QC are indicated and discussed.

Beckmerhagen, I.; Berg, H.P.; Brennecke, P. [Bundesamt fuer Strahlenschutz, Saltzgitter (Germany)

1993-12-31T23:59:59.000Z

197

Death Valley Lower Carbonate Aquifer Monitoring Program Wells Down gradient of the Proposed Yucca Mountain Nuclear Waste Repository  

SciTech Connect (OSTI)

Inyo County has participated in oversight activities associated with the Yucca Mountain Nuclear Waste Repository since 1987. The overall goal of these studies are the evaluation of far-field issues related to potential transport, by ground water, or radionuclides into Inyo County, including Death Valley, and the evaluation of a connection between the Lower Carbonate Aquifer (LCA) and the biosphere. Our oversight and completed Cooperative Agreement research, and a number of other investigators research indicate that there is groundwater flow between the alluvial and carbonate aquifers both at Yucca Mountain and in Inyo County. In addition to the potential of radionuclide transport through the LCA, Czarnecki (1997), with the US Geological Survey, research indicate potential radionuclide transport through the shallower Tertiary-age aquifer materials with ultimate discharge into the Franklin Lake Playa in Inyo County. The specific purpose of this Cooperative Agreement drilling program was to acquire geological, subsurface geology, and hydrologic data to: (1) establish the existence of inter-basin flow between the Amargosa Basin and Death Valley Basin; (2) characterize groundwater flow paths in the LCA through Southern Funeral Mountain Range, and (3) Evaluation the hydraulic connection between the Yucca Mountain repository and the major springs in Death Valley through the LCA.

Inyo County

2006-07-26T23:59:59.000Z

198

Deep Web video  

ScienceCinema (OSTI)

To make the web work better for science, OSTI has developed state-of-the-art technologies and services including a deep web search capability. The deep web includes content in searchable databases available to web users but not accessible by popular search engines, such as Google. This video provides an introduction to the deep web search engine.

None Available

2012-03-28T23:59:59.000Z

199

Deep Web video  

SciTech Connect (OSTI)

To make the web work better for science, OSTI has developed state-of-the-art technologies and services including a deep web search capability. The deep web includes content in searchable databases available to web users but not accessible by popular search engines, such as Google. This video provides an introduction to the deep web search engine.

None Available

2009-06-01T23:59:59.000Z

200

Deep-Burn Modular Helium Reactor Fuel Development Plan  

SciTech Connect (OSTI)

This document contains the workscope, schedule and cost for the technology development tasks needed to satisfy the fuel and fission product transport Design Data Needs (DDNs) for the Gas Turbine-Modular Helium Reactor (GT-MHR), operating in its role of transmuting transuranic (TRU) nuclides in spent fuel discharged from commercial light-water reactors (LWRs). In its application for transmutation, the GT-MHR is referred to as the Deep-Burn MHR (DB-MHR). This Fuel Development Plan (FDP) describes part of the overall program being undertaken by the U.S. Department of Energy (DOE), utilities, and industry to evaluate the use of the GT-MHR to transmute transuranic nuclides from spent nuclear fuel. The Fuel Development Plan (FDP) includes the work on fuel necessary to support the design and licensing of the DB-MHR. The FDP is organized into ten sections. Section 1 provides a summary of the most important features of the plan, including cost and schedule information. Section 2 describes the DB-MHR concept, the features of its fuel and the plan to develop coated particle fuel for transmutation. Section 3 describes the knowledge base for fabrication of coated particles, the experience with irradiation performance of coated particle fuels, the database for fission product transport in HTGR cores, and describes test data and calculations for the performance of coated particle fuel while in a repository. Section 4 presents the fuel performance requirements in terms of as-manufactured quality and performance of the fuel coatings under irradiation and accident conditions. These requirements are provisional because the design of the DB-MHR is in an early stage. However, the requirements are presented in this preliminary form to guide the initial work on the fuel development. Section 4 also presents limits on the irradiation conditions to which the coated particle fuel can be subjected for the core design. These limits are based on past irradiation experience. Section 5 describes the Design Data Needs to: (1) fabricate the coated particle fuel, (2) predict its performance in the reactor core, (3) predict the radionuclide release rates from the reactor core, and (4) predict the performance of spent fuel in a geological repository. The heart of this fuel development plan is Section 6, which describes the development activities proposed to satisfy the DDNs presented in Section 5. The development scope is divided into Fuel Process Development, Fuel Materials Development, Fission Product Transport, and Spent Fuel Disposal. Section 7 describes the facilities to be used. Generally, this program will utilize existing facilities. While some facilities will need to be modified, there is no requirement for major new facilities. Section 8 states the Quality Assurance requirements that will be applied to the development activities. Section 9 presents detailed costs organized by WBS and spread over time. Section 10 presents a list of the types of deliverables that will be prepared in each of the WBS elements. Four Appendices contain supplementary information on: (a) design data needs, (b) the interface with the separations plant, (c) the detailed development schedule, and (d) the detailed cost estimate.

McEachern, D

2002-12-02T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

2009-07-01T23:59:59.000Z

202

GEOLOGY, September 2010 823 INTRODUCTION  

E-Print Network [OSTI]

GEOLOGY, September 2010 823 INTRODUCTION Deformations around transpressive plate boundaries numerical models constrained by global positioning system (GPS) observations and Geology, September 2010; v. 38; no. 9; p. 823­826; doi: 10.1130/G30963.1; 3 figures; 1 table. © 2010 Geological Society

Demouchy, Sylvie

203

DEPARTMENT OF GEOLOGY & GEOPHYSICS UNDERGRADUATE  

E-Print Network [OSTI]

DEPARTMENT OF GEOLOGY & GEOPHYSICS UNDERGRADUATE SURVIVAL MANUAL 2013-2014 SCHOOL OF OCEAN & EARTH SCIENCE & TECHNOLOGY UNIVERSITY OF HAWAI`I AT MNOA Updated July 2013 #12;CONTENTS INTRODUCTION 1 Geology and Geophysics 1 Job Opportunities 1 Prepare Educationally 1 Challenges and Rewards 1 THE DEPARTMENT OF GEOLOGY

204

The Lapworth Museum of Geology  

E-Print Network [OSTI]

The Lapworth Museum of Geology www.lapworth.bham.ac.uk www.bham.ac.uk Events The Lapworth Lectures take place on evenings during University term time. These lectures are on a wide range of geological geological topics, usually based around collections in the museum. These provide an opportunity to see

Birmingham, University of

205

CO2 leakage up from a geological storage site to shallow fresh groundwater: CO2-water-rock interaction assessment and  

E-Print Network [OSTI]

CO2 leakage up from a geological storage site to shallow fresh groundwater: CO2-water repository requires the investigation of the potential CO2 leakage back into fresh groundwater, particularly sensitive monitoring techniques in order to detect potential CO2 leaks and their magnitude as well

Paris-Sud XI, Université de

206

September 2012 BASIN RESEARCH AND ENERGY GEOLOGY  

E-Print Network [OSTI]

September 2012 BASIN RESEARCH AND ENERGY GEOLOGY STATE UNIVERSITY OF NEW YORK at BINGHAMTON research programs in geochemistry, sedimentary geology, or Earth surface processes with the potential the position, visit the Geological Sciences and Environmental Studies website (www.geology

Suzuki, Masatsugu

207

Environmental Impacts of Transportation to the Potential Repository at Yucca Mountain  

SciTech Connect (OSTI)

The Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada analyzes a Proposed Action to construct, operate, monitor, and eventually close a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. As part of the Proposed Action, the EIS analyzes the potential impacts of transporting commercial and DOE spent nuclear fuel and high-level radioactive waste to Yucca Mountain from 77 sites across the United States. The analysis includes information on the comparative impacts of transporting these materials by truck and rail and discusses the impacts of building a rail line or using heavy-haul trucks to move rail casks from a mainline railroad in Nevada to the site. This paper provides an overview of the analyses and the potential impacts of these transportation activities. The potential transportation impacts were looked at from two perspectives: transportation of spent nuclear fuel and high-level radioactive waste by legal-weight truck or by rail on a national scale and impacts specific to Nevada from the transportation of these materials from the State borders to the Yucca Mountain site. In order to address the range of impacts that could result from the most likely modes, legal-weight truck and rail, the EIS employed two analytical scenarios--mostly legal-weight truck and mostly rail. Estimated national transportation impacts were based on 24 years of transportation activities. Approximately 8 fatalities could occur from all causes in the nationwide general population from incident-free transportation activities of the mostly legal-weight truck scenario and about 4 from the mostly rail scenario. The analysis examined the radiological consequences under the maximum foreseeable accident scenario and also overall accident risk. The overall accident risk over the 24 year period would be about 0.0002 latent cancer fatality for the mostly legal-weight truck scenario and about 0.0005 latent cancer fatality for the mostly rail scenario. The maximum reasonably foreseeable accident scenario resulted in 0.55 latent cancer fatality for the legal-weight truck case and 5 latent cancer fatalities in the case of mostly rail. The EIS also analyzed the impacts associated with the transportation of spent nuclear fuel and high-level radioactive waste in the State of Nevada. This included: constructing a branch rail line and using it to ship waste to the repository; upgrading highways in Nevada for use by heavy-haul trucks; constructing and operating an intermodal transfer station; and transporting personnel and materials to support construction and operation of the repository.

R.L. Sweeney; R. Best; P. Bolton; P. Adams

2002-01-03T23:59:59.000Z

208

Environmental Responses to Carbon Mitigation through Geological Storage  

SciTech Connect (OSTI)

In summary, this DOE EPSCoR project is contributing to the study of carbon mitigation through geological storage. Both deep and shallow subsurface research needs are being addressed through research directed at improved understanding of environmental responses associated with large scale injection of CO{sub 2} into geologic formations. The research plan has two interrelated research objectives. ? Objective 1: Determine the influence of CO{sub 2}-related injection of fluids on pore structure, material properties, and microbial activity in rock cores from potential geological carbon sequestration sites. ? Objective 2: Determine the Effects of CO{sub 2} leakage on shallow subsurface ecosystems (microbial and plant) using field experiments from an outdoor field testing facility.

Cunningham, Alfred; Bromenshenk, Jerry

2013-08-30T23:59:59.000Z

209

Strategic Basis for License Application Planning for a Potential Yucca Mountain Repository  

SciTech Connect (OSTI)

If Yucca Mountain, Nevada is designated as the site for development of a geologic repository for disposal of spent nuclear fuel and high-level radioactive waste, the Department of Energy (DOE) must obtain Nuclear Regulatory Commission (NRC) approval first for repository construction, then for an operating license, and, eventually, for repository closure and decommissioning. The licensing criteria defined in Code of Federal Regulations, Title 10, Part 63 (10 CFR Part 63) establish the basis for these NRC decisions. Submittal of a license application (LA) to the NRC for authorization to construct a repository at the Yucca Mountain site is, at this point, only a potential future action by the DOE. The policy process defined in the Nuclear Waste Policy Act (NWPA), as amended, for recommendation and designation of Yucca Mountain as a repository site makes it difficult to predict whether or when the site might be designated. The DOE may only submit a LA to the NRC if the site designation takes effect. In spite of this uncertainty, the DOE must take prudent and appropriate action now, and over the next several years, to prepare for development and timely submittal of a LA. This is particularly true given the need for the DOE to develop, load, and certify the operation of its electronic information system to provide access to its relevant records as part of the licensing support network (LSN) in compliance with NRC requirements six months prior to LA submittal. The DOE must also develop a LA, which is a substantially different document from those developed to support a Site Recommendation (SR) decision. The LA must satisfy NRC licensing criteria and content requirements, and address the acceptance criteria defined by the NRC in its forthcoming Yucca Mountain Review Plan (YMRP). The content of the LA must be adequate to facilitate NRC acceptance and docketing for review, and the LA and its supporting documents must provide the documented basis for the NR C findings required for a construction authorization. The LA must also support a licensing proceeding before an Atomic Safety and Licensing Board panel prior to NRC action on any decision to authorize construction. The DOE has established a strategic basis for planning that is intended to provide the framework for development of an integrated plan for activities leading to preparation and submittal of a LA.

Newberry, C. M.; Brocoum, S. J.; Gamble, R. P.; Murray, R. C.; Cline, M.

2002-02-26T23:59:59.000Z

210

Evaluating new waste form impacts on repository capacity from a total system perspective  

SciTech Connect (OSTI)

This paper summarizes the steps that need to be taken to develop a long-term performance assessment of a repository and discusses the potential impacts on the existing performance assessment model that could result from a national decision to dispose of wastes from an advanced fuel cycle, such as that envisioned under the Global Nuclear Energy Partnership (GNEP). The objective is to establish a common understanding of what activities would potentially need to be conducted, and why, to support the disposal of high level wastes from an advanced nuclear fuel cycle. The long-term performance of the proposed repository at Yucca Mountain is currently evaluated using a methodology called Total System Performance Assessment (TSPA). The TSPA methodology can be applied to evaluate the safety of the disposal of nuclear wastes arising from GNEP technologies. The entire TSPA would need to be updated in accordance with U.S. Nuclear Regulatory Commission (NRC) requirements for a license to accommodate GNEP wastes. The revised TSPA would have to reflect the entire repository system as configured to dispose of these wastes. Major changes in the TSPA expected from introduction of GNEP wastes would be in two areas. First, the features, events and processes (FEPs) that might affect performance of the geologic system would have to be re-evaluated considering the GNEP wastes and any corresponding changes to the repository design. The modeling hierarchy used in the TSPA would then be modified to reflect any revised FEPs and scenarios. Secondly, the input and boundary conditions of some models used in the TSPA would have to be revised based on characteristics of the GNEP nuclear wastes and any associated change to the repository design. Some new models would likely have to be developed, for example due to new waste form types. These model revisions would likely require additional data such as characteristics of new waste forms. Post-closure performance assessment should be an integral part of the GNEP program with models developing in an iterative and integrated manner. Testing, analyses, and modeling of nuclear wastes supported by GNEP should strive to meet the requirements for data and processes established by NRC regulations and the U.S. Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). This rigor will assure that a revision to the post-closure safety analysis is technically defensible in a regulatory environment. Qualifying data to describe changes introduced by GNEP wastes would have to undergo the same rigor and compliance with procedures as the data collection and modeling that supports the original license application. (authors)

Kim, D.K. [Office of Radioactive Waste Management, U.S. Dept. of Energy, S.W., Washington DC (United States); Nutt, W.M. [Golder Associates Inc., Las Vegas NV (United States); Dravo, A.N.; Seitz, M.G. [Booz Allen Hamilton, Washington DC (United States)

2007-07-01T23:59:59.000Z

211

WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY  

SciTech Connect (OSTI)

One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO{sub 4}{sup -} but are not expected to be durable. On the other hand, durable materials, such as hydrotalcite, do not have sufficient affinity to be useful getters. Despite these problems, the great increase in the repository performance and corresponding decrease in uncertainty promised by a useful getter has generated significant interest in these materials. This report is the result a workshop sponsored by the Office of Civilian Radioactive Waste Management and Office of Science and Technology and International of the DOE to assess the state of research in this field.

K.C. Holt

2006-03-13T23:59:59.000Z

212

Containment of uranium in the proposed Egyptian geologic repository for radioactive waste using hydroxyapatite.  

SciTech Connect (OSTI)

Currently, the Egyptian Atomic Energy Authority is designing a shallow-land disposal facility for low-level radioactive waste. To insure containment and prevent migration of radionuclides from the site, the use of a reactive backfill material is being considered. One material under consideration is hydroxyapatite, Ca{sub 10}(PO{sub 4}){sub 6}(OH){sub 2}, which has a high affinity for the sorption of many radionuclides. Hydroxyapatite has many properties that make it an ideal material for use as a backfill including low water solubility (K{sub sp}>10{sup -40}), high stability under reducing and oxidizing conditions over a wide temperature range, availability, and low cost. However, there is often considerable variation in the properties of apatites depending on source and method of preparation. In this work, we characterized and compared a synthetic hydroxyapatite with hydroxyapatites prepared from cattle bone calcined at 500 C, 700 C, 900 C and 1100 C. The analysis indicated the synthetic hydroxyapatite was similar in morphology to 500 C prepared cattle hydroxyapatite. With increasing calcination temperature the crystallinity and crystal size of the hydroxyapatites increased and the BET surface area and carbonate concentration decreased. Batch sorption experiments were performed to determine the effectiveness of each material to sorb uranium. Sorption of U was strong regardless of apatite type indicating all apatite materials evaluated. Sixty day desorption experiments indicated desorption of uranium for each hydroxyapatite was negligible.

Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Headley, Thomas Jeffrey; Sanchez, Charles Anthony (University of Arizona, Yuma, AZ); Zhao, Hongting; Salas, Fred Manuel; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt); Holt, Kathleen Caroline

2004-04-01T23:59:59.000Z

213

Area recommendation report for the crystalline repository project: An evaluation. [Crystalline Repository Project  

SciTech Connect (OSTI)

An evaluation is given of DOE's recommendation of the Elk River complex in North Carolina for siting the second repository. Twelve recommendations are made including a strong suggestion that the Cherokee Tribe appeal both through political and legal avenues for inclusion as an affected area primarily due to projected impacts upon economy and public health as a consequence of the potential for reduced tourism.

Beck, J E; Lowe, H; Yurkovich, S P

1986-03-28T23:59:59.000Z

214

Room at the Mountain: Estimated Maximum Amounts of Commercial Spent Nuclear Fuel Capable of Disposal in a Yucca Mountain Repository  

SciTech Connect (OSTI)

The purpose of this paper is to present an initial analysis of the maximum amount of commercial spent nuclear fuel (CSNF) that could be emplaced into a geological repository at Yucca Mountain. This analysis identifies and uses programmatic, material, and geological constraints and factors that affect this estimation of maximum amount of CSNF for disposal. The conclusion of this initial analysis is that the current legislative limit on Yucca Mountain disposal capacity, 63,000 MTHM of CSNF, is a small fraction of the available physical capacity of the Yucca Mountain system assuming the current high-temperature operating mode (HTOM) design. EPRI is confident that at least four times the legislative limit for CSNF ({approx}260,000 MTHM) can be emplaced in the Yucca Mountain system. It is possible that with additional site characterization, upwards of nine times the legislative limit ({approx}570,000 MTHM) could be emplaced. (authors)

Kessler, John H. [Electric Power Research Institute - EPRI, 3420 Hillview Avenue, Palo Alto, California 94304 (United States); Kemeny, John [University of Arizona, Tucson AZ 85721 (United States); King, Fraser [Integrity Corrosion Consulting, Ltd., 6732 Silverview Drive NW, Calgary, Alberta (Canada); Ross, Alan M. [Alan M. Ross and Associates, 1061 Gray Fox Circle Pleasanton, CA 94566 (Canada); Ross, Benjamen [Disposal Safety, Inc., Bethesda, MD 20814 (United States)

2006-07-01T23:59:59.000Z

215

Geology and geohydrology of the east Texas Basin. Report on the progress of nuclear waste isolation feasibility studies (1979)  

SciTech Connect (OSTI)

The program to investigate the suitability of salt domes in the east Texas Basin for long-term nuclear waste repositories addresses the stability of specific domes for potential repositories and evaluates generically the geologic and hydrogeologic stability of all the domes in the region. Analysis during the second year was highlighted by a historical characterization of East Texas Basin infilling, the development of a model to explain the growth history of the domes, the continued studies of the Quaternary in East Texas, and a better understanding of the near-dome and regional hydrology of the basin. Each advancement represents a part of the larger integrated program addressing the critical problems of geologic and hydrologic stabilities of salt domes in the East Texas Basin.

Kreitler, C.W.; Agagu, O.K.; Basciano, J.M.

1980-01-01T23:59:59.000Z

216

National Geoscience Data Repository System, Phase II. Final report, January 30, 1995--January 28, 1997  

SciTech Connect (OSTI)

The American Geological Institute (AGI) has completed Phase II of a project to establish a National Geoscience Data Repository System (NGDRS). The project`s primary objectives are to preserve geoscience data in jeopardy of being destroyed and to make that data available to those who have a need to use it in future investigations. These data are available for donation to the public as a result of the downsizing that has occurred in the major petroleum and mining companies in the United States for the past decade. In recent years, these companies have consolidated domestic operations, sold many of their domestic properties and relinquished many of their leases. The scientific data associated with those properties are no longer considered to be useful assets and are consequently in danger of being lost forever. The national repository project will make many of these data available to the geoscience community for the first time. To address this opportunity, AGI sought support from the Department of Energy (DOE) in 1994 to initiate the NGDRS Phase I feasibility study to determine the types and quantity of data that companies would be willing to donate. The petroleum and mining companies surveyed indicated that they were willing to donate approximately five million well logs, one hundred million miles of seismic reflection data, millions of linear feet of core and cuttings, and a variety of other types of scientific data. Based on the positive results of the Phase I study, AGI undertook Phase II of the program in 1995. Funded jointly by DOE and industry, Phase II encompasses the establishment of standards for indexing and cataloging of geoscience data and determination of the costs of transferring data from the private sector to public-sector data repositories. Pilot projects evaluated the feasibility of the project for transfer of different data types and creation of a Web-based metadata supercatalog and browser.

NONE

1998-04-01T23:59:59.000Z

217

RESOLUTION STRATEGY FOR GEOMECHANICALLY-RELATED REPOSITORY DESIGN FOR THERMAL-MECHANICAL EFFECTS (RDTME)  

SciTech Connect (OSTI)

In September of 2000, the U.S. Nuclear Regulatory Commission (NRC) issued an Issue Resolution Status Report (NRC 2000). The Key Technical Issue (KTI) agreements on Repository Design and Thermal-Mechanical Effects (RDTME) were jointly developed at the Technical Exchange and Management Meeting held on February 6-8, 2001 in Las Vegas, Nevada. In that report, a number of geomechanically-related issues were raised regarding the determination of rock properties, the estimation of the impacts of geologic variability, the use of numerical models, and the examination of drift degradation and design approach to the ground support system for the emplacement drifts. Ultimately, the primary end products of the KTI agreement resolution processes are an assessment of the preclosure stability of emplacement drifts and the associated ground support requirements. There is also an assessment of the postclosure degradation of the excavations when subjected to thermal and seismic-related stresses as well as in situ loading over time.

M. Board

2003-04-01T23:59:59.000Z

218

NSNFP Activities in Support of Repository Licensing for Disposal of DOE SNF  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management is in the process of preparing the Yucca Mountain license application for submission to the Nuclear Regulatory Commission as the nation’s first geologic repository for spent nuclear fuel (SNF) and high-level waste. Because the DOE SNF will be part of the license application, there are various components of the license application that will require information relative to the DOE SNF. The National Spent Nuclear Fuel Program (NSNFP) is the organization that directs the research, development, and testing of treatment, shipment, and disposal technologies for all DOE SNF. This report documents the work activities conducted by the NSNFP and discusses the relationship between these NSNFP technical activities and the license application. A number of the NSNFP activities were performed to provide risk insights and understanding of DOE SNF disposal as well as to prepare for anticipated questions from the regulatory agency.

Henry H. Loo; Brett W.. Carlsen; Sheryl L. Morton; Larry L. Taylor; Gregg W. Wachs

2004-09-01T23:59:59.000Z

219

Stability of ceramic waste forms in potential repository environments: a review  

SciTech Connect (OSTI)

Most scenarios for geologic disposal of high-level nuclear waste include the eventual intrusion of groundwater into the repository. Reactions in the system and eventual release of the radionuclides, if any, will be controlled by the chemistry of the groundwater, the surrounding rock, the waste form, and any engineered barrier materials that are present, as well as by the temperature and pressure of the system. This report is a compilation and evaluation of the work completed to date on interactions within the waste-form/host-rock/groundwater system at various points in its lifetime. General results from leaching experiments are presented as a basis for comparison. The factors involved in studying the complete system are discussed so that future research may avoid some of the oversights of past research. Although relatively little hard data on prototype waste-form/repository-system interactions exist at this time, the available data and their implications are discussed. Sorption studies and models for predicting radionuclide migration are also presented, again with a study of the factors involved.

Johnston, R. J.; Palmer, R. A.

1982-03-31T23:59:59.000Z

220

Espinosa Glaze Polychrome Bowl New Mexico Cultural Assets Digital Repository  

E-Print Network [OSTI]

Espinosa Glaze Polychrome Bowl NM CADRe New Mexico Cultural Assets Digital Repository and e for Advanced Research Computing; thomas@phys.unm.edu) Led by the University of New Mexico Maxwell Museum of Anthropology (MMA), the New Mexico Cultural Assets Digital Repository and efacility is being established

Maccabe, Barney

Note: This page contains sample records for the topic "deep geologic repository" 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

A Framework for Describing Web Repositories Frank McCown  

E-Print Network [OSTI]

, dark and grey web repos- itories; and states of recoverability (vulnerable, replicated, endangeredA Framework for Describing Web Repositories Frank McCown Department of Computer Science Harding to "lazily preserve" websites and re- construct them when they are lost. We use the term "web repositories

Nelson, Michael L.

222

The Economic, repository and proliferation implications of advanced nuclear fuel cycle  

SciTech Connect (OSTI)

The goal of this project was to compare the effects of recycling actinides using fast burner reactors, with recycle that would be done using inert matrix fuel burned in conventional light water reactors. In the fast reactor option, actinides from both spent light water and fast reactor fuel would be recycled. In the inert matrix fuel option, actinides from spent light water fuel would be recycled, but the spent inert matrix fuel would not be reprocessed. The comparison was done over a limited 100-year time horizon. The economic, repository and proliferation implications of these options all hinge on the composition of isotopic byproducts of power production. We took the perspective that back-end economics would be affected by the cost of spent fuel reprocessing (whether conventional uranium dioxide fuel, or fast reactor fuel), fuel manufacture, and ultimate disposal of high level waste in a Yucca Mountain like geological repository. Central to understanding these costs was determining the overall amount of reprocessing needed to implement a fast burner, or inert matrix fuel, recycle program. The total quantity of high level waste requiring geological disposal (along with its thermal output), and the cost of reprocessing were also analyzed. A major advantage of the inert matrix fuel option is that it could in principle be implemented using the existing fleet of commercial power reactors. A central finding of this project was that recycling actinides using an inert matrix fuel could achieve reductions in overall actinide production that are nearly very close to those that could be achieved by recycling the actinides using a fast burner reactor.

Mark Deinert; K.B. Cady

2011-09-04T23:59:59.000Z

223

Petroleum geology of Tunisia  

SciTech Connect (OSTI)

Recent discoveries and important oil shows have proven the existence of hydrocarbons in newly identified depocenters and reservoirs. In general, except for some areas around the producing fields, Tunisia is largely underdrilled. The national company ETAP has decided to release data and to publish a synthesis on the petroleum geology of Tunisia. The geology of Tunisia provides a fine example of the contrast between Alpine folding, which typifies northern Tunisia and the African craton area of the Saharan part. Eastern Tunisia corresponds to an unstable platform forming plains or low hills and extending eastwards to the shallow Pelagian Sea. There are a wide variety of basins: central and northern Tunisia represents a front basin the Saharan Ghadames basin or the Chott trough are sag basins; the Gulf of Gabes was formed as a distension margin the Gulf of Hammamet is a composite basin and several transversal grabens cut across the country, including offshore, and are rift-type basins. All these features are known to be oil prolific throughout the world. Two large fields and many modest-size pools are known in Tunisia. Oil and gas fields in the surrounding countries, namely the Saharan fields of Algeria and Libya the large Bouri field offshore Tripolitania and discoveries in the Italian part of the Straits of Sicily, suggest a corresponding potential in Tunisia. Exposed paleogeographic and structural maps, balanced sections, and examples of fields and traps will support an optimistic evaluation of the future oil exploration in Tunisia.

Burollet, P.F. (CIFEG, Paris (France)); Ferjami, A.B.; Mejri, F. (ETAP, Tunis (Tunisia))

1990-05-01T23:59:59.000Z

224

Regional Geology: GIS Database for Alternative Host Rocks and...  

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

Performance of a Salt Repository for Disposal of Heat-Generating Nuclear Waste Oil Shale Research in the United States Repository Reference Disposal Concepts and Thermal...

225

Montana State University 1 Geology Option  

E-Print Network [OSTI]

Montana State University 1 Geology Option The Geology Option is a degree program designed and private sectors in fields such as petroleum geology, mining geology, seismology (including earthquake and volcanic risk assessment), hydrology (surface and ground water) natural-hazard geology, environmental clean

Maxwell, Bruce D.

226

WSU B.S. Geology Curriculum (structural)  

E-Print Network [OSTI]

WSU B.S. Geology Curriculum Geology GEL 3300 (structural) GEL 3400 (sed/strat) Geology Elective 1 Geology Elective 2 Yr 1 Yr 2 Yr 3 Yr 4 PHY 2130/31 MAT 2010 PHY 2140/41 CHEM 1220/30 MAT 1800 Cognates GEL 5593 (writing intensive) GEL 3160 (petrology) GEL 3650 (field camp) Geology Elective 3 GEL 2130

Berdichevsky, Victor

227

Progress report on the results of testing advanced conceptual design metal barrier materials under relevant environmental conditions for a tuff repository  

SciTech Connect (OSTI)

This report discusses the performance of candidate metallic materials envisioned for fabricating waste package containers for long-term disposal at a possible geological repository at Yucca Mountain, Nevada. Candidate materials include austenitic iron-base to nickel-base alloy (AISI 304L, AISI 316L, and Alloy 825), high-purity copper (CDA 102), and copper-base alloys (CDA 613 and CDA 715). Possible degradation modes affecting these container materials are identified in the context of anticipated environmental conditions at the repository site. Low-temperature oxidation is the dominant degradation mode over most of the time period of concern (minimum of 300 yr to a maximum of 1000 yr after repository closure), but various forms of aqueous corrosion will occur when water infiltrates into the near-package environment. The results of three years of experimental work in different repository-relevant environments are presented. Much of the work was performed in water taken from Well J-13, located near the repository, and some of the experiments included gamma irradiation of the water or vapor environment. The influence of metallurgical effects on the corrosion and oxidation resistance of the material is reviewed; these effects result from container fabrication, welding, and long-term aging at moderately elevated temperatures in the repository. The report indicates the need for mechanisms to understand the physical/chemical reactions that determine the nature and rate of the different degradation modes, and the subsequent need for models based on these mechanisms for projecting the long-term performance of the container from comparatively short-term laboratory data. 91 refs., 17 figs., 16 tabs.

McCright, R.D.; Halsey, W.G.; Van Konynenburg, R.A.

1987-12-01T23:59:59.000Z

228

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01T23:59:59.000Z

229

National survey of crystalline rocks and recommendations of regions to be explored for high-level radioactive waste repository sites  

SciTech Connect (OSTI)

A reconnaissance of the geological literature on large regions of exposed crystalline rocks in the United States provides the basis for evaluating if any of those regions warrant further exploration toward identifying potential sites for development of a high-level radioactive waste repository. The reconnaissance does not serve as a detailed evaluation of regions or of any smaller subunits within the regions. Site performance criteria were selected and applied insofar as a national data base exists, and guidelines were adopted that relate the data to those criteria. The criteria include consideration of size, vertical movements, faulting, earthquakes, seismically induced ground motion, Quaternary volcanic rocks, mineral deposits, high-temperature convective ground-water systems, hydraulic gradients, and erosion. Brief summaries of each major region of exposed crystalline rock, and national maps of relevant data provided the means for applying the guidelines and for recommending regions for further study. It is concluded that there is a reasonable likelihood that geologically suitable repository sites exist in each of the major regions of crystalline rocks. The recommendation is made that further studies first be conducted of the Lake Superior, Northern Appalachian and Adirondack, and the Southern Appalachian Regions. It is believed that those regions could be explored more effectively and suitable sites probably could be found, characterized, verified, and licensed more readily there than in the other regions.

Smedes, H.W.

1983-04-01T23:59:59.000Z

230

Copyright 2007, SEPM (Society for Sedimentary Geology) 0883-1351/07/0022-0577/$3.00 PALAIOS, 2007, v. 22, p. 577582  

E-Print Network [OSTI]

IMPLICATIONS OF URANIUM ROLL FRONTS PENNILYN HIGGINS* University of Wyoming Department of GeologyCopyright 2007, SEPM (Society for Sedimentary Geology) 0883-1351/07/0022-0577/$3.00 PALAIOS, 2007 deep structural basins containing both abundant vertebrate fossils and uranium-ore deposits in the form

Higgins, Pennilyn

231

GRADUATE PROGRAM IN GEOLOGICAL ENGINEERING  

E-Print Network [OSTI]

5342 Geological Engineering: Soils and Weak Rocks 3 2 EOSC 535 Transport Processes in Porous Media 3 2 Site Investigation and Management 3 2 CIVL 574 Experimental Soil Mechanics 3 2 CIVL 579 Geosynthetics 2 Geological Engineering Soils and Weak Rocks 3 2 CIVL 408 Geo-Environmental Engineering 3 2 CIVL 410

232

Coring in deep hardrock formations  

SciTech Connect (OSTI)

The United States Department of Energy is involved in a variety of scientific and engineering feasibility studies requiring extensive drilling in hard crystalline rock. In many cases well depths extend from 6000 to 20,000 feet in high-temperature, granitic formations. Examples of such projects are the Hot Dry Rock well system at Fenton Hill, New Mexico and the planned exploratory magma well near Mammoth Lakes, California. In addition to these programs, there is also continuing interest in supporting programs to reduce drilling costs associated with the production of geothermal energy from underground sources such as the Geysers area near San Francisco, California. The overall progression in these efforts is to drill deeper holes in higher temperature, harder formations. In conjunction with this trend is a desire to improve the capability to recover geological information. Spot coring and continuous coring are important elements in this effort. It is the purpose of this report to examine the current methods used to obtain core from deep wells and to suggest projects which will improve existing capabilities. 28 refs., 8 figs., 2 tabs.

Drumheller, D.S.

1988-08-01T23:59:59.000Z

233

Z .Chemical Geology 152 1998 227256 The thermal and cementation histories of a sandstone petroleum  

E-Print Network [OSTI]

Z .Chemical Geology 152 1998 227­256 The thermal and cementation histories of a sandstone petroleum-feldspars recovered at various depths from a deep well drilled through a carbonate-cemented sandstone petroleum of a sandstone petroleum xreservoir, Elk Hills, California. Part 2: In situ oxygen and carbon isotopic results

234

Repository Subsurface Preliminary Fire Hazard Analysis  

SciTech Connect (OSTI)

This fire hazard analysis identifies preliminary design and operations features, fire, and explosion hazards, and provides a reasonable basis to establish the design requirements of fire protection systems during development and emplacement phases of the subsurface repository. This document follows the Technical Work Plan (TWP) (CRWMS M&O 2001c) which was prepared in accordance with AP-2.21Q, ''Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities''; Attachment 4 of AP-ESH-008, ''Hazards Analysis System''; and AP-3.11Q, ''Technical Reports''. The objective of this report is to establish the requirements that provide for facility nuclear safety and a proper level of personnel safety and property protection from the effects of fire and the adverse effects of fire-extinguishing agents.

Richard C. Logan

2001-07-30T23:59:59.000Z

235

Repository surface design site layout analysis  

SciTech Connect (OSTI)

The purpose of this analysis is to establish the arrangement of the Yucca Mountain Repository surface facilities and features near the North Portal. The analysis updates and expands the North Portal area site layout concept presented in the ACD, including changes to reflect the resizing of the Waste Handling Building (WHB), Waste Treatment Building (WTB), Carrier Preparation Building (CPB), and site parking areas; the addition of the Carrier Washdown Buildings (CWBs); the elimination of the Cask Maintenance Facility (CMF); and the development of a concept for site grading and flood control. The analysis also establishes the layout of the surface features (e.g., roads and utilities) that connect all the repository surface areas (North Portal Operations Area, South Portal Development Operations Area, Emplacement Shaft Surface Operations Area, and Development Shaft Surface Operations Area) and locates an area for a potential lag storage facility. Details of South Portal and shaft layouts will be covered in separate design analyses. The objective of this analysis is to provide a suitable level of design for the Viability Assessment (VA). The analysis was revised to incorporate additional material developed since the issuance of Revision 01. This material includes safeguards and security input, utility system input (size and location of fire water tanks and pump houses, potable water and sanitary sewage rates, size of wastewater evaporation pond, size and location of the utility building, size of the bulk fuel storage tank, and size and location of other exterior process equipment), main electrical substation information, redundancy of water supply and storage for the fire support system, and additional information on the storm water retention pond.

Montalvo, H.R.

1998-02-27T23:59:59.000Z

236

GEOLOGY AND FRACTURE SYSTEM AT STRIPA  

E-Print Network [OSTI]

of underground test site •• 1.5 Regional bedrock geology.Stripa mine, sub-till geology in the immediate mine area.Fig. 2.1 Stripa mine, sub-till geology in the immediate mine

Olkiewicz, O.

2010-01-01T23:59:59.000Z

237

Panel 2, Geologic Storage of Hydrogen  

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

Geologic Storage - Types Types of Underground Storage Aquifers Aquifers are similar in geology to depleted reservoirs, but have not been proven to trap gas and must be developed....

238

Assessment of effectiveness of geologic isolation systems: a short description of the AEGIS approach  

SciTech Connect (OSTI)

To meet licensing criteria and protection standards for HLW disposal, research programs are in progress to determine acceptable waste forms, canisters, backfill materials for the repository, and geological formations. Methods must be developed to evaluate the effectiveness of the total system. To meet this need, methods are being developed to assess the long-term effectiveness of isolating nuclear wastes in geologic formations. This work was started in 1976 in the Waste Isolation Safety Assessment Program (WISAP) and continues in the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program. The evaluation of this long-term effectiveness involves a number of distinct steps. AEGIS currently has the methods for performing these evaluation steps. These methods are continuously being improved to meet the inreasing level of sophistication which will be required. AEGIS develops a conceptual description of the geologic systems and uses computer models to simulate the existing ground-water pathways. AEGIS also uses a team of consulting experts, with the assistance of a computer model of the geologic processes, to develop and evaluate plausible release scenarios. Then other AEGIS computer models are used to simulate the transport of radionuclides to the surface and the resultant radiation doses to individuals and populations. (DLC)

Silviera, D.J.; Harwell, M.A.; Napier, B.A.; Zellmer, J.T.; Benson, G.L.

1980-09-01T23:59:59.000Z

239

Remote sensing data exploiration for geologic characterization of difficult targets : Laboratory Directed Research and Development project 38703 final report.  

SciTech Connect (OSTI)

Characterizing the geology, geotechnical aspects, and rock properties of deep underground facility sites can enhance targeting strategies for both nuclear and conventional weapons. This report describes the results of a study to investigate the utility of remote spectral sensing for augmenting the geological and geotechnical information provided by traditional methods. The project primarily considered novel exploitation methods for space-based sensors, which allow clandestine collection of data from denied sites. The investigation focused on developing and applying novel data analysis methods to estimate geologic and geotechnical characteristics in the vicinity of deep underground facilities. Two such methods, one for measuring thermal rock properties and one for classifying rock types, were explored in detail. Several other data exploitation techniques, developed under other projects, were also examined for their potential utility in geologic characterization.

Costin, Laurence S.; Walker, Charles A.; Lappin, Allen R.; Hayat, Majeed M. (University of New Mexico, Albuquerque, NM); Ford, Bridget K.; Paskaleva, Biliana (University of New Mexico, Albuquerque, NM); Moya, Mary M.; Mercier, Jeffrey Alan (University of Arizona, Tucson, AZ); Stormont, John C. (University of New Mexico, Albuquerque, NM); Smith, Jody Lynn

2003-09-01T23:59:59.000Z

240

Adding OAI-ORE Support to Repository Platforms  

E-Print Network [OSTI]

to DSpace considerably simplifies the task of maintaining TDL?s federated ETD colection. However, the aplications of this project extend beyond its initial use case. The ability to easily harvest content from one repository to another provides...

Maslov, Alexey; Mikeal, Adam; Phillips, Scott; Leggett, John; McFarland, Mark

2009-05-17T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

The DSpace Institutional Digital Repository System: Current Functionality  

E-Print Network [OSTI]

In this paper we describe DSpaceâ?¢, an open source system that acts as a repository for digital research and educational material produced by an organization or institution. DSpace was developed during two years’ collaboration ...

Tansley, Robert

2003-01-01T23:59:59.000Z

242

Automated Validation of Trusted Digital Repository Assessment Criteria  

E-Print Network [OSTI]

The RLG/NARA trusted digital repository (TDR) certification checklist defines a set of assessment criteria for preservation environments. The criteria can be mapped into data management policies that define how a digital ...

Smith, MacKenzie

243

A Repository for Beyond-the-Standard-Model Tools  

SciTech Connect (OSTI)

To aid phenomenological studies of Beyond-the-Standard-Model (BSM) physics scenarios, a web repository for BSM calculational tools has been created. We here present brief overviews of the relevant codes, ordered by topic as well as by alphabet.

Skands, P.; /Fermilab; Richardson, P.; Allanach, B.C.; Baer, H.; Belanger, G.; El Kacimi, M.; Ellwanger, U.; Freitas, A.; Ghodbane, N.; Goujdami, D.; Hahn, T.; Heinemeyer,; Kneur, J.-L.; Landsberg, G.; Lee, J.S.; Muhlleitner, M.; Ohl, T.; Perez, E.; Peskin, M.; Pilaftsis, A.; Plehn, T.

2005-05-01T23:59:59.000Z

244

Mined Geologic Disposal System Requirements Document. Revision 1  

SciTech Connect (OSTI)

This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS.

Not Available

1994-03-01T23:59:59.000Z

245

Preliminary geology of eastern Umtanum Ridge, South-Central Washington  

SciTech Connect (OSTI)

The basalt stratigraphy and geologic structures of eastern Umtanum Ridge have been mapped and studied in detail to help assess the feasibility of nuclear waste terminal storage on the Hanford Site in southeastern Washington State. Eastern Umtanum Ridge is an asymmetric east-west-trending anticline of Columbia River basalt that plunges 5 degrees eastward into the Pasco Basin. Geologic mapping and determination of natural remanent magnetic polarity and chemical composition reveal that flows of the Pomona and Umatilla Members (Saddle Mountains Basalt), Priest Rapids and Frenchman Springs Members (Wanapum Basalt), and Grande Ronde Basalt were erupted as fairly uniform sheets. The Wahluke and Huntzinger flows (Saddle Mountains Basalt) fill a paleovalley cut into Wanapum Basalt. No evidence was found to indicate Quaternary-age movement on any structures in the map area. The basalt strata on the south limb of the Umtanum anticline display relatively little tectonic deformation since Miocene-Pliocene time. Thus, the buried south flank of Umtanum Ridge may provide an excellent location for a nuclear waste repository beneath the Hanford Site.

Goff, F.E.

1981-01-01T23:59:59.000Z

246

Reprinted February 2003 4-H Geology  

E-Print Network [OSTI]

4-H 340 Reprinted February 2003 4-H Geology Member Guide OREGON STATE UNIVERSITY EXTENSION SERVICE #12;Contents 4-H Geology Project 3 Project Recommendations 3 Books on Geology 4 Trip Planning 4 Contests 7 Identification of Rocks and Minerals 7 Physical Properties of Minerals 8 Generalized Geologic

Tullos, Desiree

247

Geology of the Shenandoah National Park Region  

E-Print Network [OSTI]

1 Geology of the Shenandoah National Park Region 39th Annual Virginia Geological Field Conference October 2nd - 3rd, 2009 Scott Southworth U. S. Geological Survey L. Scott Eaton James Madison University Meghan H. Lamoreaux College of William & Mary William C. Burton U. S. Geological Survey Christopher M

Eaton, L. Scott

248

242 Department of Geology Undergraduate Catalogue 201415  

E-Print Network [OSTI]

242 Department of Geology Undergraduate Catalogue 2014­15 Department of Geology Chairperson: Abdel. Assistant Instructor: P Hajj-Chehadeh, Abdel-Halim The Department of Geology offers programs leading to the degree of Bachelor of Science in Geology, and Master of Science degrees in certain areas of the vast

249

Assessment Report, Department of Geology August, 2012  

E-Print Network [OSTI]

Assessment Report, Department of Geology August, 2012 1. Learning Goals ALL students in geology, classification schemes, geologic history and processes, and the structure of the Earth. 3. demonstrate an understanding of the variability, complexity, and interdependency of processes within geologic systems. 4. use

Bogaerts, Steven

250

149Department of Geology Graduate Catalogue 201415  

E-Print Network [OSTI]

149Department of Geology Graduate Catalogue 2014­15 Department of Geology Chairperson: Abdel. Assistant Instructor: P Hajj-Chehadeh, Abdel-Halim MS in Geology Candidates pursuing the Master of Science program in geology must complete seven graduate courses (21 cr.) and a thesis (9 cr.). Students may select

251

Characteristics of potential repository wastes. Volume 2  

SciTech Connect (OSTI)

The LWR spent fuels discussed in Volume 1 of this report comprise about 99% of all domestic non-reprocessed spent fuel. In this report we discuss other types of spent fuels which, although small in relative quantity, consist of a number of diverse types, sizes, and compositions. Many of these fuels are candidates for repository disposal. Some non-LWR spent fuels are currently reprocessed or are scheduled for reprocessing in DOE facilities at the Savannah River Site, Hanford Site, and the Idaho National Engineering Laboratory. It appears likely that the reprocessing of fuels that have been reprocessed in the past will continue and that the resulting high-level wastes will become part of defense HLW. However, it is not entirely clear in some cases whether a given fuel will be reprocessed, especially in cases where pretreatment may be needed before reprocessing, or where the enrichment is not high enough to make reprocessing attractive. Some fuels may be canistered, while others may require special means of disposal. The major categories covered in this chapter include HTGR spent fuel from the Fort St. Vrain and Peach Bottom-1 reactors, research and test reactor fuels, and miscellaneous fuels, and wastes generated from the decommissioning of facilities.

Not Available

1992-07-01T23:59:59.000Z

252

LIFE Materials: Fuel Cycle and Repository Volume 11  

SciTech Connect (OSTI)

The fusion-fission LIFE engine concept provides a path to a sustainable energy future based on safe, carbon-free nuclear power with minimal nuclear waste. The LIFE design ultimately offers many advantages over current and proposed nuclear energy technologies, and could well lead to a true worldwide nuclear energy renaissance. When compared with existing and other proposed future nuclear reactor designs, the LIFE engine exceeds alternatives in the most important measures of proliferation resistance and waste minimization. The engine needs no refueling during its lifetime. It requires no removal of fuel or fissile material generated in the LIFE engine. It leaves no weapons-attractive material at the end of life. Although there is certainly a need for additional work, all indications are that the 'back end' of the fuel cycle does not to raise any 'showstopper' issues for LIFE. Indeed, the LIFE concept has numerous benefits: (1) Per unit of electricity generated, LIFE engines would generate 20-30 times less waste (in terms of mass of heavy metal) requiring disposal in a HLW repository than does the current once-through fuel cycle. (2) Although there may be advanced fuel cycles that can compete with LIFE's low mass flow of heavy metal, all such systems require reprocessing, with attendant proliferation concerns; LIFE engines can do this without enrichment or reprocessing. Moreover, none of the advanced fuel cycles can match the low transuranic content of LIFE waste. (3) The specific thermal power of LIFE waste is initially higher than that of spent LWR fuel. Nevertheless, this higher thermal load can be managed using appropriate engineering features during an interim storage period, and could be accommodated in a Yucca-Mountain-like repository by appropriate 'staging' of the emplacement of waste packages during the operational period of the repository. The planned ventilation rates for Yucca Mountain would be sufficient for LIFE waste to meet the thermal constraints of the repository design. (4) A simple, but arguably conservative, estimate for the dose from a repository containing 63,000 MT of spent LIFE fuel would have similar performance to the currently planned Yucca Mountain Repository. This indicates that a properly designed 'LIFE Repository' would almost certainly meet the proposed Nuclear Regulatory Commission standards for dose to individuals, even though the waste in such a repository would have produced 20-30 times more generated electricity than the reference case for Yucca Mountain. The societal risk/benefit ratio for a LIFE repository would therefore be significantly better than for currently planned repositories for LWR fuel.

Shaw, H; Blink, J A

2008-12-12T23:59:59.000Z

253

BACHELOR OF SCIENCE IN ENVIRONMENTAL GEOLOGY DEPARTMENT OF GEOLOGY AND PLANETARY SCIENCE  

E-Print Network [OSTI]

BACHELOR OF SCIENCE IN ENVIRONMENTAL GEOLOGY DEPARTMENT OF GEOLOGY AND PLANETARY SCIENCE WWW.GEOLOGY" for a complete range of advising information plus the latest Environmental Geology requirements. CORE COURSES (check each as completed): (30 credits) ____Choose one of the following introductory geology classes

Jiang, Huiqiang

254

A case study on the influence of THM coupling on the near field safety of a spent fuel repository in sparsely fractured granite  

SciTech Connect (OSTI)

In order to demonstrate the feasibility of geological disposal of spent CANDU fuel in Canada, a safety assessment was performed for a hypothetical repository in the Canadian Shield. The assessment shows that such repository would meet international criteria for dose rate; however, uncertainties in the assumed evolution of the repository were identified. Such uncertainties could be resolved by the consideration of coupled Thermal-Hydro-Mechanical-Chemical (THMC) processes. In Task A of the DECOVALEX-THMC project, THM models were developed within the framework of the theory of poroelasticity. Such model development was performed in an iterative manner, using experimental data from laboratory and field tests. The models were used to perform near-field simulations of the evolution of the repository in order to address the above uncertainties. This paper presents the definition and rationale of task A and the results of the simulations. From a repository safety point of view, the simulations predict that the maximum temperature would be well below the design target of 100 C, however the load on the container can marginally exceed the design value of 15 MPa. However, the most important finding from the simulations is that a rock damage zone could form around the emplacement borehole. Such damage zone can extend a few metres from the walls of the emplacement holes, with permeability values that are orders of magnitude higher than the initial values. The damage zone has the potential to increase the radionuclide transport flux from the geosphere; the effect of such an increase should be taken into account in the safety assessment and mitigated if necessary by the provision of sealing systems.

Nguyen, T.S.; Borgesson, L.; Chijimatsu, M.; Hernelind, J.; Jing, L.; Kobayashi, A.; Rutqvist, J.

2009-03-01T23:59:59.000Z

255

International Symposium on Site Characterization for CO2Geological Storage  

SciTech Connect (OSTI)

Several technological options have been proposed to stabilize atmospheric concentrations of CO{sub 2}. One proposed remedy is to separate and capture CO{sub 2} from fossil-fuel power plants and other stationary industrial sources and to inject the CO{sub 2} into deep subsurface formations for long-term storage and sequestration. Characterization of geologic formations for sequestration of large quantities of CO{sub 2} needs to be carefully considered to ensure that sites are suitable for long-term storage and that there will be no adverse impacts to human health or the environment. The Intergovernmental Panel on Climate Change (IPCC) Special Report on Carbon Dioxide Capture and Storage (Final Draft, October 2005) states that ''Site characterization, selection and performance prediction are crucial for successful geological storage. Before selecting a site, the geological setting must be characterized to determine if the overlying cap rock will provide an effective seal, if there is a sufficiently voluminous and permeable storage formation, and whether any abandoned or active wells will compromise the integrity of the seal. Moreover, the availability of good site characterization data is critical for the reliability of models''. This International Symposium on Site Characterization for CO{sub 2} Geological Storage (CO2SC) addresses the particular issue of site characterization and site selection related to the geologic storage of carbon dioxide. Presentations and discussions cover the various aspects associated with characterization and selection of potential CO{sub 2} storage sites, with emphasis on advances in process understanding, development of measurement methods, identification of key site features and parameters, site characterization strategies, and case studies.

Tsang, Chin-Fu

2006-02-23T23:59:59.000Z

256

Carbon-14 releases from an unsaturated repository: A senseless but expensive dilemma  

SciTech Connect (OSTI)

The purpose of the US Environmental Protection Agency (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR Part 191 or standards) is to protect public health and safety. The 1985 rule was developed on the basis of the assumption that the repository would be located in a geologic formation that lies below the water table. It is appropriate to examine gaseous releases and transport of pollutants in order to determine site adequacy. When the provisions of the 1985 standard are applied to Yucca Mountain, specifically the limits for carbon-14, we can release in 10,000 years no more than 7,000 curies of carbon-14 in the form of carbon dioxide. Meanwhile, the US Department of Energy (DOE) and others indicate that the repository may release about 8,000 curies of carbon-14 dioxide, an amount that exceeds the standard by 10 to 20 percent. The original basis of the 1985 standards was that, in a site below the water table, the limit for carbon-14 was technically achievable. It was not a standard based on a release level that would prevent a danger to public health. If we examine the danger to public health of the release of 8,000 curies of carbon-14 dioxide during and 8,000-year period, this release would not a pose a significant threat to the average individual. Industry and natural sources release many times this amount of carbon-14 dioxide each year. The question therefore becomes: is it appropriate to spend an additional $3.2 billion on waste packages when the expenditure does not measurably improve the public health?

Pflum, C.G.

1993-10-01T23:59:59.000Z

257

Characteristics of potential repository wastes. Volume 1  

SciTech Connect (OSTI)

This document, and its associated appendices and microcomputer (PC) data bases, constitutes the reference OCRWM data base of physical and radiological characteristics data of radioactive wastes. This Characteristics Data Base (CDB) system includes data on spent nuclear fuel and high-level waste (HLW), which clearly require geologic disposal, and other wastes which may require long-term isolation, such as sealed radioisotope sources. The data base system was developed for OCRWM by the CDB Project at Oak Ridge National Laboratory. Various principal or official sources of these data provided primary information to the CDB Project which then used the ORIGEN2 computer code to calculate radiological properties. The data have been qualified by an OCRWM-sponsored peer review as suitable for quality-affecting work meeting the requirements of OCRWM`s Quality Assurance Program. The wastes characterized in this report include: light-water reactor (LWR) spent fuel and immobilized HLW.

Not Available

1992-07-01T23:59:59.000Z

258

Proceedings of the scientific visit on crystalline rock repository development.  

SciTech Connect (OSTI)

A scientific visit on Crystalline Rock Repository Development was held in the Czech Republic on September 24-27, 2012. The visit was hosted by the Czech Radioactive Waste Repository Authority (RAWRA), co-hosted by Sandia National Laboratories (SNL), and supported by the International Atomic Energy Agency (IAEA). The purpose of the visit was to promote technical information exchange between participants from countries engaged in the investigation and exploration of crystalline rock for the eventual construction of nuclear waste repositories. The visit was designed especially for participants of countries that have recently commenced (or recommenced) national repository programmes in crystalline host rock formations. Discussion topics included repository programme development, site screening and selection, site characterization, disposal concepts in crystalline host rock, regulatory frameworks, and safety assessment methodology. Interest was surveyed in establishing a %E2%80%9Cclub,%E2%80%9D the mission of which would be to identify and address the various technical challenges that confront the disposal of radioactive waste in crystalline rock environments. The idea of a second scientific visit to be held one year later in another host country received popular support. The visit concluded with a trip to the countryside south of Prague where participants were treated to a tour of the laboratory and underground facilities of the Josef Regional Underground Research Centre.

Mariner, Paul E.; Hardin, Ernest L.; Miksova, Jitka [RAWRA, Czech Republic

2013-02-01T23:59:59.000Z

259

Transportation analysis for the concept of regional repositories  

SciTech Connect (OSTI)

Over the past several years, planning associated with the National Waste Terminal Storage (NWTS) program assumed the use of one or two large, centrally located repository facilities. Recently, an alternative approach has been proposed which consists of the use of multiple, smaller regional repositories. In this report, several regional concepts were studied and the transportation requirements for the shipment of spent fuel to the regional repositories were estimated. In general, the transportation requirements decrease as the number of repositories increase. However, as far as transportation is concerned, the point of diminishing returns is reached at approximately one repository in each of three to four regions. Additional savings beyond this point are small. A series of sensitivity studies is also included to demonstrate the impact on the total transportation requirements of varying cask capacity, rail speed, or truck speed. Since most of the projected fuel shipments are to be made by rail, varying the capacity of the rail cask or varying average rail transport speed will have a major effect on overall transportation requirements.

Joy, D.S.; Hudson, B.J.

1980-06-01T23:59:59.000Z

260

Federal Control of Geological Carbon Sequestration  

SciTech Connect (OSTI)

The United States has economically recoverable coal reserves of about 261 billion tons, which is in excess of a 250-­?year supply based on 2009 consumption rates. However, in the near future the use of coal may be legally restricted because of concerns over the effects of its combustion on atmospheric carbon dioxide concentrations. In response, the U.S. Department of Energy is making significant efforts to help develop and implement a commercial scale program of geologic carbon sequestration that involves capturing and storing carbon dioxide emitted from coal-­?burning electric power plants in deep underground formations. This article explores the technical and legal problems that must be resolved in order to have a viable carbon sequestration program. It covers the responsibilities of the United States Environmental Protection Agency and the Departments of Energy, Transportation and Interior. It discusses the use of the Safe Drinking Water Act, the Clean Air Act, the National Environmental Policy Act, the Endangered Species Act, and other applicable federal laws. Finally, it discusses the provisions related to carbon sequestration that have been included in the major bills dealing with climate change that Congress has been considering in 2009 and 2010. The article concludes that the many legal issues that exist can be resolved, but whether carbon sequestration becomes a commercial reality will depend on reducing its costs or by imposing legal requirements on fossil-­?fired power plants that result in the costs of carbon emissions increasing to the point that carbon sequestration becomes a feasible option.

Reitze, Arnold

2011-04-11T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

The Geologic and Hydrogeologic Setting of the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a mined repository constructed by the US Department of Energy for the permanent disposal of transuranic wastes generated since 1970 by activities related to national defense. The WIPP is located 42 km east of Carlsbad, New Mexico, in bedded salt (primarily halite) of the Late Permian (approximately 255 million years old) Salado Formation 655 m below the land surface. Characterization of the site began in the mid-1970s. Construction of the underground disposal facilities began in the early 1980s, and the facility received final certification from the US Environmental Protection Agency in May 1998. Disposal operations are planned to begin following receipt of a final permit from the State of New Mexico and resolution of legal issues. Like other proposed geologic repositories for radioactive waste, the WIPP relies on a combination of engineered and natural barriers to isolate the waste from the biosphere. Engineered barriers at the WIPP, including the seals that will be emplaced in the access shafts when the facility is decommissioned, are discussed in the context of facility design elsewhere in this volume. Physical properties of the natural barriers that contribute to the isolation of radionuclides are discussed here in the context of the physiographic, geologic, and hydrogeologic setting of the site.

Swift, P.N.; Corbet, T.F.

1999-03-04T23:59:59.000Z

262

pre or co-requisite Geology Course Prerequisite Chart  

E-Print Network [OSTI]

pre or co-requisite Geology Course Prerequisite Chart 1101, 1102, 1103,1104, 1105 2250 3160 2500 hours geology junior standing; six hours geology depends on course senior standing, permission hours geology six hours geology Evolution of the Earth Geophysics Physical Geology , Historical Geology

Thaxton, Christopher S.

263

The Suitable Geological Formations for Spent Fuel Disposal in Romania  

SciTech Connect (OSTI)

Using the experience in the field of advanced countries and formerly Romanian program data, ANDRAD, the agency responsible for the disposal of radioactive wastes, started the program for spent fuel disposal in deep geological formations with a documentary analysis at the national scale. The potential geological formations properly characterized elsewhere in the world: salt, clay, volcanic tuff, granite and crystalline rocks,. are all present in Romania. Using general or specific selection criteria, we presently consider the following two areas for candidate geological formations: 1. Clay formations in two areas in the western part of Romania: (1) The Pannonian basin Socodor - Zarand, where the clay formation is 3000 m thick, with many bentonitic strata and undisturbed structure, and (2) The Eocene Red Clay on the Somes River, extending 1200 m below the surface. They both need a large investigation program in order to establish and select the required homogeneous, dry and undisturbed zones at a suitable depth. 2. Old platform green schist formations, low metamorphosed, quartz and feldspar rich rocks, in the Central Dobrogea structural unit, not far from Cernavoda NPP (30 km average distance), 3000 m thick and including many homogeneous, fine granular, undisturbed, up to 300 m thick layers. (authors)

Marunteanu, C. [Bucharest Univ. (Romania); Ionita, G. [ANDRAD, Bucharest (Romania); Durdun, I. [S.C. GEOTEC S.A., Bucharest (Romania)

2007-07-01T23:59:59.000Z

264

Implementation of the Brazilian National Repository - RBMN Project - 13008  

SciTech Connect (OSTI)

Ionizing radiation in Brazil is used in electricity generation, medicine, industry, agriculture and for research and development purposes. All these activities can generate radioactive waste. At this point, in Brazil, the use of nuclear energy and radioisotopes justifies the construction of a national repository for radioactive wastes of low and intermediate-level. According to Federal Law No. 10308, Brazilian National Commission for Nuclear Energy (CNEN) is responsible for designing and constructing the intermediate and final storages for radioactive wastes. Additionally, a restriction on the construction of Angra 3 is that the repository is under construction until its operation start, attaining some requirements of the Brazilian Environmental Regulator (IBAMA). Besides this NPP, in the National Energy Program is previewed the installation of four more plants, by 2030. In November 2008, CNEN launched the Project RBMN (Repository for Low and Intermediate-Level Radioactive Wastes), which aims at the implantation of a National Repository for disposal of low and intermediate-level of radiation wastes. This Project has some aspects that are unique in the Brazilian context, especially referring to the time between its construction and the end of its institutional period. This time is about 360 years, when the area will be released for unrestricted uses. It means that the Repository must be safe and secure for more than three hundred years, which is longer than half of the whole of Brazilian history. This aspect is very new for the Brazilian people, bringing a new dimension to public acceptance. Another point is this will be the first repository in South America, bringing a real challenge for the continent. The current status of the Project is summarized. (authors)

Cassia Oliveira de Tello, Cledola [CDTN - Center for Development of Nuclear Technology, Av. Presidente Antonio Carlos, 6.627 - Campus UFMG - Pampulha, CEP 31270-901 - Belo Horizonte - MG (Brazil)

2013-07-01T23:59:59.000Z

265

DSpace : An Institutional Repository from the MIT Libraries and Hewlett Packard Laboratories  

E-Print Network [OSTI]

The DSpaceâ?¢ project of the MIT Libraries and the Hewlett Packard Laboratories has built an institutional repository system for digital research material. This paper will describe the rationale for institutional repositories, ...

Smith, MacKenzie

2002-01-01T23:59:59.000Z

266

Why Geology Matters: Decoding the Past, Anticipating the Future  

E-Print Network [OSTI]

Review: Why Geology Matters: Decoding the Past, AnticipatingUSA Macdougall, Doug. Why Geology Matters: Decoding theE-book available. Why Geology Matters pursues two goals: to

Anderson, Byron P.

2011-01-01T23:59:59.000Z

267

www.geology.pdx.edu Undergraduate Degrees Offered  

E-Print Network [OSTI]

electron microscope, atomic absorption spectrometer, ICP-mass spectrometer, ground penetrating radarGEOLOGY www.geology.pdx.edu Undergraduate Degrees Offered: Bachelor of Arts in Geology Bachelor

268

Risk assessment framework for geologic carbon sequestration sites  

E-Print Network [OSTI]

Framework for geologic carbon sequestration risk assessment,for geologic carbon sequestration risk assessment, Energyfor Geologic Carbon Sequestration, Int. J. of Greenhouse Gas

Oldenburg, C.

2010-01-01T23:59:59.000Z

269

Certification Framework Based on Effective Trapping for Geologic Carbon Sequestration  

E-Print Network [OSTI]

workshop on geologic carbon sequestration, 2002. Benson,verification of geologic carbon sequestration, Geophys. Res.CO 2 from geologic carbon sequestration sites, Vadose Zone

Oldenburg, Curtis M.

2009-01-01T23:59:59.000Z

270

Technical Geologic Overview of Long Valley Caldera for the Casa...  

Open Energy Info (EERE)

of geothermal production. This report addresses geologic considerations in preparing an EISEIR including:Geology, soils and mineralsGeologic hazardsSeismic hazardsFaulting...

271

The Proposed Yucca Mountain Repository From A Corrosion Perspective  

SciTech Connect (OSTI)

Corrosion is a primary determinant of waste package performance at the proposed Yucca Mountain Repository and will control the delay time for radionuclide transport from the waste package. Corrosion is the most probable and most likely degradation process that will determine when packages will be penetrated and the shape size and distribution of those penetrations. The general issues in corrosion science, materials science and electrochemistry are well defined, and the knowledge base is substantial for understanding corrosion processes. In this paper, the Yucca Mountain Repository is viewed from a corrosion perspective.

J.H. Payer

2005-03-10T23:59:59.000Z

272

The AutoMed Schema Integration Repository Michael Boyd, Peter M c . Brien and Nerissa Tong  

E-Print Network [OSTI]

The AutoMed Schema Integration Repository Michael Boyd, Peter M c . Brien and Nerissa Tong {mboyd,pjm

McBrien, Peter

273

Repository Reference Disposal Concepts and Thermal Load Management...  

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

Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clayshale, salt, crystalline,...

274

Geology in coal resource utilization  

SciTech Connect (OSTI)

The 37 papers in this book were compiled with an overriding theme in mind: to provide the coal industry with a comprehensive source of information on how geology and geologic concepts can be applied to the many facets of coal resource location, extraction, and utilization. The chapters have been arranged to address the major coal geology subfields of Exploration and Reserve Definition, Reserve Estimation, Coalbed Methane, Underground Coal Gasification, Mining, Coal Quality Concerns, and Environmental Impacts, with papers distributed on the basis of their primary emphasis. To help guide one through the collection, the author has included prefaces at the beginning of each chapter. They are intended as a brief lead-in to the subject of the chapter and an acknowledgement of the papers' connections to the subject and contributions to the chapter. In addition, a brief cross-reference section has been included in each preface to help one find papers of interest in other chapters. The subfields of coal geology are intimately intertwined, and investigations in one area may impact problems in another area. Some subfields tend to blur at their edges, such as with reserve definition and reserve estimation. Papers have been processed separately for inclusion on the data base.

Peters, D.C. (ed.)

1991-01-01T23:59:59.000Z

275

GEOLOGY, February 2008 151 INTRODUCTION  

E-Print Network [OSTI]

College, 600 1st Street West, Mount Vernon, Iowa 52314, USA Yemane Asmerom Victor Y. Polyak Department of Miami, 4600 Rickenbacker Causeway, Miami, Florida 33149, USA Peter Cole Department of Geology, Cornell College, 600 1st Street West, Mount Vernon, Iowa 52314, USA Ann F. Budd Department of Geoscience

Asmerom, Yemane

276

Geological Characterization of California's Offshore  

E-Print Network [OSTI]

for the various data generated by the West Coast Regional Carbon Sequestration Partnership. The project's goals are to: · Perform a preliminary geologic characterization of the carbon dioxide sequestration of carbon sequestration potential. · For select formations previously studied in the Southern Sacramento

277

Geology, Environmental Science, Geography, Environmental Management  

E-Print Network [OSTI]

2011 Geology, Environmental Science, Geography, Environmental Management Postgraduate Handbook #12 Environmental Management 14 Environmental Science 18 Geography 22 Geographic Information Science 26 Geology, Environmental Science, Geography, Environmental Management Postgraduate Handbook Editors David Hayward, Ilse

Goodman, James R.

278

Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Standards in Geomatics  

E-Print Network [OSTI]

Modelling Geospatial Application Databases using UML-based Repositories Aligned with International Abstract: This paper presents the result of recent work on the use of geospatial repositories to store and database concepts, a geospatial repository can be defined as a collection of (meta) data structured

279

Hanford Borehole Geologic Information System (HBGIS)  

SciTech Connect (OSTI)

This is a user's guide for viewing and downloading borehold geologic data through a web-based interface.

Last, George V.; Mackley, Rob D.; Saripalli, Ratna R.

2005-09-26T23:59:59.000Z

280

A publication of the Department of Geology  

E-Print Network [OSTI]

#12;A publication of the Department of Geology Brigharn Young University Provo, Utah 84602 Editors W. Kenneth Hamblin Cynthia M. Gardner Brigham Young University Geology Studies is published semiannually by the department. Geology Studies consists of graduate-student and staff research

Seamons, Kent E.

Note: This page contains sample records for the topic "deep geologic repository" 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

, UNIVERSITY Brigham Young University Geology Studies  

E-Print Network [OSTI]

, UNIVERSITY #12;Brigham Young University Geology Studies Volume 1 5 - 1968 Part 2 Studies for Students No. 1 Guide to the Geology of the Wasatch Mountain Front, Between Provo Canyon and Y Mountain, Northeast of Provo, Utah by J. Keith Rigby and Lehi F. Hintze #12;A publication of the Department of Geology

Seamons, Kent E.

282

GeoloGy (Geol) Robinson Foundation  

E-Print Network [OSTI]

182 GeoloGy (Geol) Robinson Foundation PROFESSOR HARBoR ASSOCIATE PROFESSORS KNAPP, CONNORS ASSISTANT PROFESSORS GREER, RAHL MAJORS BACHELOR OF SCIENCE Amajor in geology leading to a Bachelor of Science degree consists of 50 credits as follows: 1. Geology160,185,211,311,330,350,andacom- prehensive

Dresden, Gregory

283

Geological carbon sequestration: critical legal issues  

E-Print Network [OSTI]

Geological carbon sequestration: critical legal issues Ray Purdy and Richard Macrory January 2004 Tyndall Centre for Climate Change Research Working Paper 45 #12;1 Geological carbon sequestration an integrated assessment of geological carbon sequestration (Project ID code T2.21). #12;2 1 Introduction

Watson, Andrew

284

ABOUT THE JOURNAL One of the oldest journals in geology, The Journal of Geology has  

E-Print Network [OSTI]

ABOUT THE JOURNAL One of the oldest journals in geology, The Journal of Geology has promoted the systematic philosophical and fundamental study of geology since 1893. The Journal publishes original research across a broad range of subfields in geology, including geophysics, geochemistry, sedimentology

Mateo, Jill M.

285

Courses: Geology (GEOL) Page 325Sonoma State University 2014-2015 Catalog Geology (GEOL)  

E-Print Network [OSTI]

Courses: Geology (GEOL) Page 325Sonoma State University 2014-2015 Catalog Geology (GEOL) geoL 102 our dynAMiC eArtH: introduCtion to geoLogy (3) Lecture, 2 hours; laboratory, 3 hours. A study. Empha- sis on local geology, including earthquakes and other environmental aspects. Labo- ratory study

Ravikumar, B.

286

Geology and Geohazards in Taiwan Geologic Field Course and Study Abroad Experience  

E-Print Network [OSTI]

Geology and Geohazards in Taiwan Geologic Field Course and Study Abroad Experience Winter Break 2015 Interested in field geology? Interested in environmental hazards and climate? Want to visit #12;Geology and Geohazards in Taiwan This is a 3-week course for students interested in mixing field

Alpay, S. Pamir

287

Mathematical Geology, Vol. 34, No. 1, January 2002 ( C 2002) On Modelling Discrete Geological Structures  

E-Print Network [OSTI]

Mathematical Geology, Vol. 34, No. 1, January 2002 ( C 2002) On Modelling Discrete Geological there is a large amount of missing observations, which often is the case in geological applications. We make,predictions,MarkovchainMonteCarlo,simulatedannealing,incomplete observations. INTRODUCTION In many geological applications, there is an interest in predicting properties

Baran, Sándor

288

Roadmap: Geology Environmental Geology -Bachelor of Science [AS-BS-GEOL-EGEO  

E-Print Network [OSTI]

Roadmap: Geology ­ Environmental Geology - Bachelor of Science [AS-BS-GEOL-EGEO] College of Arts This roadmap is a recommended semester-by-semester plan of study for this major. However, courses on page 2 General Elective 8 #12;Roadmap: Geology ­ Environmental Geology - Bachelor of Science [AS

Sheridan, Scott

289

R. Jonk $ Department of Geology and Petro-leum Geology, University of Aberdeen, AB24  

E-Print Network [OSTI]

Kingdom) and a geological con- sultant for various oil companies. His research focused primarilyAUTHORS R. Jonk $ Department of Geology and Petro- leum Geology, University of Aberdeen, AB24 3UE, Texas 77060; rene.jonk@exxonmobil.com Rene Jonk received his M.Sc. degree in structural geology from

Mazzini, Adriano

290

Total System Performance Assessment, 1993: An evaluation of the potential Yucca Mountain repository  

SciTech Connect (OSTI)

Total System Performance Assessments are an important component in the evaluation of the suitability of Yucca Mountain, Nevada as a potential site for a mined geologic repository for the permanent disposal of high-level radioactive wastes in the United States. The Total System Performance Assessments are conducted iteratively during site characterization to identify issues which should be addressed by the characterization and design activities as well as providing input to regulatory/licensing and programmatic decisions. During fiscal years 1991 and 1992, the first iteration of Total System Performance Assessment (hereafter referred to as TSPA 1991) was completed by Sandia National Laboratories and Pacific Northwest Laboratory. Beginning in fiscal year 1993, the Civilian Radioactive Waste Management System Management and Operating Contractor was assigned the responsibility to plan, coordinate, and contribute to the second iteration of Total System Performance Assessment (hereafter referred to as TSPA 1993). This document presents the objectives, approach, assumptions, input, results, conclusions, and recommendations associated with the Management and Operating Contractor contribution to TSPA 1993. The new information incorporated in TSPA 1993 includes (1) revised estimates of radionuclide solubilities (and their thermal and geochemical dependency), (2) thermal and geochemical dependency of spent fuel waste alteration and glass dissolution rates, (3) new distribution coefficient (k{sub d}) estimates, (4) revised estimates of gas-phase velocities and travel times, and (5) revised hydrologic modeling of the saturated zone which provides updated estimates of the advective flux through the saturated zone.

Andrews, R.W.; Dale, T.F.; McNeish, J.A.

1994-03-01T23:59:59.000Z

291

Physical Geology Laboratory Manual Charles Merguerian and J Bret Bennington  

E-Print Network [OSTI]

Physical Geology Laboratory Manual Charles Merguerian and J Bret Bennington Geology Department Hofstra University © 2006 #12;i PHYSICAL GEOLOGY LABORATORY MANUAL Ninth Edition Professors Charles Merguerian and J Bret Bennington Geology Department Hofstra University #12;ii ACKNOWLEDGEMENTS We thank

Merguerian, Charles

292

Impact of Pyrophoric Events on Long-Term Repository Performance  

SciTech Connect (OSTI)

This paper provides an overview of a feature, event, and process (FEP) screening argument developed for the issue of pyrophoricity as it pertains to the post-closure interment of Department of Energy (DOE) spent nuclear fuel (DSNF) at the Yucca Mountain Repository.

Richard Gregg

2005-09-01T23:59:59.000Z

293

Grey/Gray Matter: The Role of Institutional Repositories  

E-Print Network [OSTI]

and the Academy 3:2 (2003), pp. 327-336. 7. Crow, Raym. "The Case for Institutional Repositories: A SPARC Position Paper." ARL Bimonthly Report 223 (August 2002). 8. google.com 9. DSpace@MIT http://dspace.mit.edu 12. IDEALS http...

Mercer, Holly

2011-04-15T23:59:59.000Z

294

Effect of repository underground ventilation on emplacement drift temperature control  

SciTech Connect (OSTI)

The repository advanced conceptual design (ACD) is being conducted by the Civilian Radioactive Waste Management System, Management & Operating Contractor. Underground ventilation analyses during ACD have resulted in preliminary ventilation concepts and design methodologies. This paper discusses one of the recent evaluations -- effects of ventilation on emplacement drift temperature management.

Yang, H.; Sun, Y.; McKenzie, D.G.; Bhattacharyya, K.K. [Morrison Knudson Corporation, Las Vegas, NV (United States)

1996-02-01T23:59:59.000Z

295

SHERPA Document SHERPA Document -Institutional Repositories: Staff and Skills Requirements  

E-Print Network [OSTI]

SHERPA Document SHERPA Document - Institutional Repositories: Staff and Skills Requirements Mary This document began in response to requests received by the core SHERPA team for examples of job descriptions and UKCORR members. This document will be revised annually (July/August) to reflect changing needs

Southampton, University of

296

Early Restoration Plan Repositories STATE LIBRARY ADDRESS CITY ZIP  

E-Print Network [OSTI]

Calcasieu Parish Public Library Central Branch 301 W. Claude St. Lake Charles 70605 #12;STATE LIBRARYEarly Restoration Plan Repositories STATE LIBRARY ADDRESS CITY ZIP AL Dauphin Island Sea Laboratory. Walton 32548 FL Panama City Beach Public Library 125000 Hutchison Blvd Panama City Beach 32407 FL

297

Step-Wise Repository Licensing-Implementing the Scientific and Legislative Vision for the Next Phase of the Yucca Mountain Project  

SciTech Connect (OSTI)

International scientific consensus backing geologic disposal as the preferred method of long term management of used nuclear fuel and defense high level radioactive waste has existed since the 1950s. Furthermore, many believe that geologic disposal programs should be implemented in a staged or 'step-wise' approach. These principles have also been at the root of US waste management policy for which a regulatory framework for site selection, and the licensing of a site once selected, is set forth in a series of legislation. The US program has now matured to the point where these regulatory components are now in place. Sufficient data has also been gathered and evaluated to support a site recommendation decision. This decision--on whether or not to proceed with a repository site at Yucca Mountain, Nevada - is about to be put before the US President and Congress. If made in the affirmative, the decision would initiate the next phase in the US disposal process as originally envisioned by Congress--a three-step repository licensing process (Construction, Operation, & Closure). This paper explores the many facets of the licensing process that may lie ahead. Approaches that could be deployed to effectively implement this process are discussed and opportunities to optimize the process, by capitalizing on its evolutionary nature to assure that the best available science is always applied to the protection of public health and safety, are identified. Focus is also placed on a key prerequisite to the accomplishment of this goal--the definition of the level to which post closure repository performance must be addressed at each stage of the licensing process.

McCullum, R.; Kessler, J. H.; Eyre, M. L.

2002-02-27T23:59:59.000Z

298

Spacer for deep wells  

SciTech Connect (OSTI)

A spacer for use in a deep well that is to have a submersible pump situated downhole and with a string of tubing attached to the pump for delivering the pumped fluid. The pump is electrically driven, and power is supplied via an armored cable which parallels the string of tubing. Spacers are clamped to the cable and have the tubing running through an eccentrically located passage in each spacer. The outside dimensions of a spacer fit freely inside any casing in the well.

Klein, G. D.

1984-10-23T23:59:59.000Z

299

Nevada potential repository preliminary transportation strategy Study 2. Volume 1  

SciTech Connect (OSTI)

The objectives of this study were to build on the findings of the Nevada Potential Repository Preliminary Transportation Strategy Study 1 (CRWMS M&O 1995b), and to provide additional information for input to the repository environmental impact statement (EIS) process. In addition, this study supported the future selection of a preferred rail corridor and/or heavy haul route based on defensible data, methods, and analyses. Study research did not consider proposed legislation. Planning was conducted according to the Civilian Radioactive Waste Management Program Plan (DOE 1994a). The specific objectives of Study 2 were to: eliminate or reduce data gaps, inconsistencies, and uncertainties, and strengthen the analysis performed in Study 1; develop a preliminary list of rail route evaluation criteria that could be used to solicit input from stakeholders during scoping meetings. The evaluation criteria will be revised based on comments received during scoping; restrict and refine the width of the four rail corridors identified in Study 1 to five miles or less, based on land use constraints and engineering criteria identified and established in Study 2; evaluate national-level effects of routing spent nuclear fuel and high-level waste to the four identified branch lines, including the effects of routing through or avoiding Las Vegas; continue to gather published land use information and environmental data to support the repository EIS; continue to evaluate heavy haul truck transport over three existing routes as an alternative to rail and provide sufficient information to support the repository EIS process; and evaluate secondary uses for rail (passenger use, repository construction, shared use).

NONE

1996-02-01T23:59:59.000Z

300

MSc STUDY PROGRAMME IN THE FACULTY OF GEOLOGY AND GEOENVIRONMENT, UNIVERSITY OF ATHENS 201314 Geology and Geoenvironment  

E-Print Network [OSTI]

MSc STUDY PROGRAMME IN THE FACULTY OF GEOLOGY AND GEOENVIRONMENT, UNIVERSITY OF ATHENS 201314 1 Geology and Geoenvironment MSc Programme STUDENT HANDBOOK Applied Environmental Geology, Stratigraphy Paleontology, Geography and Environment, Dynamic Geology and Tectonics/ Hydrogeology, Geophysics

Kouroupetroglou, Georgios

Note: This page contains sample records for the topic "deep geologic repository" 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

Geological/geophysical study progresses  

SciTech Connect (OSTI)

Robertson Research (U.S.) Inc. of Houston is working on the second of a planned three-phase regional geological and geochemical study of Paleozoic rocks in the Williston Basin. The studies cover the entire Williston Basin in North Dakota, South Dakota, Montana, Saskatchewan and Manitoba. Each report is based largely on original petrographic, well log, and geochemical data that were developed by Robertson.

Savage, D.

1983-10-01T23:59:59.000Z

302

GEOLOGY, April 2010 311 INTRODUCTION  

E-Print Network [OSTI]

. The assumption that this AMSA records a single global event led to the widely accepted global catastrophic) wholesale lithospheric recycling (Turcotte, 1993; Herrick, 1994; Turcotte et al., 1999). In either case or lithospheric recycling. The proposed thickness of deep burial has evolved, ranging from >3 km to >1 km, but 1

Hansen, Vicki

303

World Wide WebWWWDeep Web Web Deep Web  

E-Print Network [OSTI]

Deep Web Web World Wide WebWWWDeep Web Web Deep Web Deep Web Deep Web Deep Web Deep Web 1 World Wide Web [1] Web 200,000TB Web Web Web Internet Web Web Web "" Surface Web Deep Web Surface Web 21.3% Surface Web Deep Web [2] Deep Web Web Crawler Deep Web 1 Web

304

Research On Fiber Optic Sensing Systems And Their Application As Final Repository Monitoring Tools  

SciTech Connect (OSTI)

For several years, fiber-optic sensing devices had been used for straightforward on/off monitoring functions such as presence and position detection. Recently, they gained interest as they offer a novel, exciting technology for a multitude of sensing applications. In the deep geological environment most physical properties, and thus most parameters important to safety, can be measured with fiber-optic technology. Typical examples are displacements, strains, radiation dose and dose rate, presence of some gases, temperature, pressure, etc. Their robustness, immunity to electromagnetic interference, as well as their large bandwidths and data rates ensure high reliability and superior performance. Moreover, the networking capabilities of meanwhile available fiber-optic sensors allow for efficient management of large sensor systems. Distributed sensing with multiple sensing locations on a single fiber reduces significantly the number of cables and connecting points. Reliable, cost effective, and maintenance-free solutions can thus be implemented.

Jobmann, M.; Biurrun, E.

2003-02-24T23:59:59.000Z

305

A deep earthquake goes supershear  

SciTech Connect (OSTI)

Seismic analysis of an aftershock off Russia’s Kamchatka Peninsula offers evidence that deep earthquakes are more complicated than geoscientists realized.

Wilson, R. Mark

2014-09-01T23:59:59.000Z

306

B.S. GEOLOGY (Geology Subplan) CHECKLIST of required courses for major Geology Core Courses: 9-10 courses, 33-34 credits  

E-Print Network [OSTI]

B.S. GEOLOGY (Geology Subplan) CHECKLIST of required courses for major Geology Core Courses: 9 - Experiencing Geology Lab and either GEOSCI 103 - Intro to Oceanography or GEOSCI 105 - Dynamic Earth 4 (1) (4 semester GEOSCI 201 ­ History of the Earth 4 1st or 2nd year, spring semester GEOSCI 231 ­ Geological Field

Massachusetts at Amherst, University of

307

Spent nuclear fuel as a waste form for geologic disposal: Assessment and recommendations on data and modeling needs  

SciTech Connect (OSTI)

This study assesses the status of knowledge pertinent to evaluating the behavior of spent nuclear fuel as a waste form in geologic disposal systems and provides background information that can be used by the DOE to address the information needs that pertain to compliance with applicable standards and regulations. To achieve this objective, applicable federal regulations were reviewed, expected disposal environments were described, the status of spent-fuel modeling was summarized, and information regarding the characteristics and behavior of spent fuel was compiled. This compiled information was then evaluated from a performance modeling perspective to identify further information needs. A number of recommendations were made concerning information still needed to enhance understanding of spent-fuel behavior as a waste form in geologic repositories. 335 refs., 22 figs., 44 tabs.

Van Luik, A.E.; Apted, M.J.; Bailey, W.J.; Haberman, J.H.; Shade, J.S.; Guenther, R.E.; Serne, R.J.; Gilbert, E.R.; Peters, R.; Williford, R.E.

1987-09-01T23:59:59.000Z

308

Method of deep drilling  

DOE Patents [OSTI]

Deep drilling is facilitated by the following steps practiced separately or in any combination: (1) Periodically and sequentially fracturing zones adjacent the bottom of the bore hole with a thixotropic fastsetting fluid that is accepted into the fracture to overstress the zone, such fracturing and injection being periodic as a function of the progression of the drill. (2) Casing the bore hole with ductile, pre-annealed casing sections, each of which is run down through the previously set casing and swaged in situ to a diameter large enough to allow the next section to run down through it. (3) Drilling the bore hole using a drill string of a low density alloy and a high density drilling mud so that the drill string is partially floated.

Colgate, Stirling A. (4616 Ridgeway, Los Alamos, NM 87544)

1984-01-01T23:59:59.000Z

309

Brine and Gas Flow Patterns Between Excavated Areas and Disturbed Rock Zone in the 1996 Performance Assessment for the Waste Isolation Pilot Plant for a Single Drilling Intrusion that Penetrates Repository and Castile Brine Reservoir  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP), which is located in southeastern New Mexico, is being developed for the geologic disposal of transuranic (TRU) waste by the U.S. Department of Energy (DOE). Waste disposal will take place in panels excavated in a bedded salt formation approximately 2000 ft (610 m) below the land surface. The BRAGFLO computer program which solves a system of nonlinear partial differential equations for two-phase flow, was used to investigate brine and gas flow patterns in the vicinity of the repository for the 1996 WIPP performance assessment (PA). The present study examines the implications of modeling assumptions used in conjunction with BRAGFLO in the 1996 WIPP PA that affect brine and gas flow patterns involving two waste regions in the repository (i.e., a single waste panel and the remaining nine waste panels), a disturbed rock zone (DRZ) that lies just above and below these two regions, and a borehole that penetrates the single waste panel and a brine pocket below this panel. The two waste regions are separated by a panel closure. The following insights were obtained from this study. First, the impediment to flow between the two waste regions provided by the panel closure model is reduced due to the permeable and areally extensive nature of the DRZ adopted in the 1996 WIPP PA, which results in the DRZ becoming an effective pathway for gas and brine movement around the panel closures and thus between the two waste regions. Brine and gas flow between the two waste regions via the DRZ causes pressures between the two to equilibrate rapidly, with the result that processes in the intruded waste panel are not isolated from the rest of the repository. Second, the connection between intruded and unintruded waste panels provided by the DRZ increases the time required for repository pressures to equilibrate with the overlying and/or underlying units subsequent to a drilling intrusion. Third, the large and areally extensive DRZ void volumes is a significant source of brine to the repository, which is consumed in the corrosion of iron and thus contributes to increased repository pressures. Fourth, the DRZ itself lowers repository pressures by providing storage for gas and access to additional gas storage in areas of the repository. Fifth, given the pathway that the DRZ provides for gas and brine to flow around the panel closures, isolation of the waste panels by the panel closures was not essential to compliance with the U.S. Environment Protection Agency's regulations in the 1996 WIPP PA.

ECONOMY,KATHLEEN M.; HELTON,JON CRAIG; VAUGHN,PALMER

1999-10-01T23:59:59.000Z

310

3D Geologic Modeling of the Southern San Joaquin Basin for the Westcarb Kimberlina Demonstration Project- A Status Report  

SciTech Connect (OSTI)

The objective of the Westcarb Kimberlina pilot project is to safely inject 250,000 t CO{sub 2}/yr for four years into the deep subsurface at the Clean Energy Systems (CES) Kimberlina power plant in southern San Joaquin Valley, California. In support of this effort, we have constructed a regional 3D geologic model of the southern San Joaquin basin. The model is centered on the Kimberlina power plant and spans the UTM range E 260000-343829 m and N 3887700-4000309 m; the depth of the model ranges from the topographic surface to >9000 m below sea level. The mapped geologic units are Quaternary basin fill, Tertiary marine and continental deposits, and pre-Tertiary basement rocks. Detailed geologic data, including surface maps, borehole data, and geophysical surveys, were used to define the geologic framework. Fifteen time-stratigraphic formations were mapped, as well as >140 faults. The free surface is based on a 10 m lateral resolution DEM. We use Earthvision (Dynamic Graphics, Inc.) to integrate the geologic and geophysical information into a 3D model of x,y,z,p nodes, where p is a unique integer index value representing the geologic unit. This grid represents a realistic model of the subsurface geology and provides input into subsequent flow simulations.

Wagoner, J

2009-04-24T23:59:59.000Z

311

3D Geologic Modeling of the Southern San Joaquin Basin for the Westcarb Kimberlina Demonstration Project- A Status Report  

SciTech Connect (OSTI)

The objective of the Westcarb Kimberlina pilot project is to safely inject 250,000 t CO{sub 2}/yr for four years into the deep subsurface at the Clean Energy Systems (CES) Kimberlina power plant in southern San Joaquin Valley, California. In support of this effort, we have constructed a regional 3D geologic model of the southern San Joaquin basin. The model is centered on the Kimberlina power plant and spans the UTM range E 260000-343829 m and N 3887700-4000309 m; the depth of the model ranges from the topographic surface to >9000 m below sea level. The mapped geologic units are Quaternary basin fill, Tertiary marine and continental deposits, and pre-Tertiary basement rocks. Detailed geologic data, including surface maps, borehole data, and geophysical surveys, were used to define the geologic framework. Fifteen time-stratigraphic formations were mapped, as well as >140 faults. The free surface is based on a 10 m lateral resolution DEM. We use Earthvision (Dynamic Graphics, Inc.) to integrate the geologic and geophysical information into a 3D model of x,y,z,p nodes, where p is a unique integer index value representing the geologic unit. This grid represents a realistic model of the subsurface geology and provides input into subsequent flow simulations.

Wagoner, J

2009-02-23T23:59:59.000Z

312

Repository-relevant testing applied to the Yucca Mountain Project  

SciTech Connect (OSTI)

A repository environment poses a challenge to developing a testing program because of the diverse nature of conditions that may exist at a given time during the life of the repository. A starting point is to identify whether any potential waste-water contact modes are particularly deleterious to the waste form performance, and whether any interactions between materials present in the waste package environment need to be accounted for during modeling the waste form reaction. The Unsaturated Test method in one approach that has been developed by the Yucca Mountain Project (YMP) to investigate the above issues, and a description of results that have been obtained during the testing of glass and unirradiated UO{sub 2} are the subject of this report. 10 refs., 7 figs., 4 tabs.

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

1989-04-01T23:59:59.000Z

313

Lithophysal Rock Mass Mechanical Properties of the Repository Host Horizon  

SciTech Connect (OSTI)

The purpose of this calculation is to develop estimates of key mechanical properties for the lithophysal rock masses of the Topopah Spring Tuff (Tpt) within the repository host horizon, including their uncertainties and spatial variability. The mechanical properties to be characterized include an elastic parameter, Young's modulus, and a strength parameter, uniaxial compressive strength. Since lithophysal porosity is used as a surrogate property to develop the distributions of the mechanical properties, an estimate of the distribution of lithophysal porosity is also developed. The resulting characterizations of rock parameters are important for supporting the subsurface design, developing the preclosure safety analysis, and assessing the postclosure performance of the repository (e.g., drift degradation and modeling of rockfall impacts on engineered barrier system components).

D. Rigby

2004-11-10T23:59:59.000Z

314

Expected brine movement at potential nuclear waste repository salt sites  

SciTech Connect (OSTI)

The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

McCauley, V.S.; Raines, G.E.

1987-08-01T23:59:59.000Z

315

Repository relevant testing applied to the Yucca Mountain Project  

SciTech Connect (OSTI)

The tuff beds of Yucca Mountain, Nevada, are currently being investigated as a site for the disposal of high-level nuclear waste in an underground repository. If this site is found suitable, the repository would be located in the unsaturated zone above the water table, and a description of the site and the methodology of assessing the performance of the repository are described in the Site Characterization Plan (SCP). While many factors are accounted for during performance assessment, an important input parameter is the degradation behavior of the waste forms, which may be either spent fuel or reprocessed waste contained in a borosilicate glass matrix. To develop the necessary waste form degradation input, the waste package environment needs to be identified. This environment will change as the waste decays and also is a function of the repository design which has not yet been finalized. At the present time, an exact description of the waste package environment is not available. The SCP does provide an initial description of conditions that can be used to guide waste form evaluation. However, considerable uncertainty exists concerning the conditions under which waste form degradation and radionuclide release may occur after the waste package containment barriers are finally breached. The release conditions that are considered to be plausible include (1) a {open_quotes}bathtub{close_quotes} condition in which the waste becomes fully or partially submerged in water that enters the breached container and accumulates to fill the container up to the level of the breach opening, (2) a {open_quotes}wet drip{close_quotes} or {open_quotes}trickle through{close_quotes} condition in which the waste form is exposed to dripping water that enters through the top and exits the bottom of a container with multiple holes, and (3) a {open_quotes}dry{close_quotes} condition in which the waste form is exposed to a humid air environment.

Bates, J.K.; Woodland, A.B.; Wronkiewicz, D.J.; Cunnane, J.C.

1990-10-01T23:59:59.000Z

316

Arizona Geological Society Digest 22  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICEACME | NationalTbilisi |Arizona Geological

317

Use of integrated geologic and geophysical information for characterizing the structure of fracture systems at the US/BK Site, Grimsel Laboratory, Switzerland  

SciTech Connect (OSTI)

Fracture systems form the primary fluid flow paths in a number of rock types, including some of those being considered for high level nuclear waste repositories. In some cases, flow along fractures must be modeled explicitly as part of a site characterization effort. Fractures commonly are concentrated in fracture zones, and even where fractures are seemingly ubiquitous, the hydrology of a site can be dominated by a few discrete fracture zones. We have implemented a site characterization methodology that combines information gained from geophysical and geologic investigations. The general philosophy is to identify and locate the major fracture zones, and then to characterize their systematics. Characterizing the systematics means establishing the essential and recurring patterns in which fractures are organized within the zones. We make a concerted effort to use information on the systematics of the fracture systems to link the site-specific geologic, borehole and geophysical information. This report illustrates how geologic and geophysical information on geologic heterogeneities can be integrated to guide the development of hydrologic models. The report focuses on fractures, a particularly common type of geologic heterogeneity. However, many aspects of the methodology we present can be applied to other geologic heterogeneities as well. 57 refs., 40 figs., 1 tab.

Martel, S.J.; Peterson, J.E. Jr. (Lawrence Berkeley Lab., CA (USA))

1990-05-01T23:59:59.000Z

318

Information needs for characterization of high-level waste repository sites in six geologic media. Volume 2. Appendices  

SciTech Connect (OSTI)

Volume II contains appendices for the following: (1) remote sensing and surface mapping techniques; (2) subsurface mapping methods for site characterization; (3) gravity technique; (4) audio-frequency magnetotelluric technique; (5) seismic refraction technique; (6) direct-current electrical resistivity method; (7) magnetic technique; (8) seismic reflection technique; (9) seismic crosshole method; (10) mechanical downhole seismic velocity survey method; (11) borehole geophysical logging techniques; (12) drilling and coring methods for precharacterization studies; (13) subsurface drilling methods for site characterization; (14) geomechanical/thermomechanical techniques for precharacterization studies; (15)geomechanical/thermal techniques for site characterization studies; (16) exploratory geochemical techniques for precharacterization studies; (17) geochemical techniques for site characterization; (18) hydrologic techniques for precharacterization studies; (19) hydrologic techniques for site characterization; and (20) seismological techniques.

NONE

1985-05-01T23:59:59.000Z

319

Multiple-code simulation study of the long-term EDZ evolution of geological nuclear waste repositories  

SciTech Connect (OSTI)

This simulation study shows how widely different model approaches can be adapted to model the evolution of the excavation disturbed zone (EDZ) around a heated nuclear waste emplacement drift in fractured rock. The study includes modeling of coupled thermal-hydrological-mechanical (THM) processes, with simplified consideration of chemical coupling in terms of time-dependent strength degradation or subcritical crack growth. The different model approaches applied in this study include boundary element, finite element, finite difference, particle mechanics, and elastoplastic cellular automata methods. The simulation results indicate that thermally induced differential stresses near the top of the emplacement drift may cause progressive failure and permeability changes during the first 100 years (i.e., after emplacement and drift closure). Moreover, the results indicate that time-dependent mechanical changes may play only a small role during the first 100 years of increasing temperature and thermal stress, whereas such time-dependency is insignificant after peak temperature, because decreasing thermal stress.

Rutqvist, J.; Backstrom, A.; Chijimatsu, M.; Feng, X.-T.; Pan, P.-Z.; Hudson, J.; Jing, L.; Kobayashi, A.; Koyama, T.; Lee, H.-S.; Huang, X.-H.; Rinne, M.; Shen, B.

2008-10-23T23:59:59.000Z

320

Multiple-code simulation study of the long-term EDZ evolution of geological nuclear waste repositories  

E-Print Network [OSTI]

subcritical crack growth were determined from laboratory experiments under water-subcritical crack growth with time- dependent parameters determined from laboratory experiments under water

Rutqvist, J.

2008-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Deep Maps”: A Brief for Digital Palimpsest Mapping Projects (DPMPs, or “Deep Maps”)  

E-Print Network [OSTI]

DEEP  MAPS”:  A  Brief  for   Digital  Palimpsest  DPMPs,  or  “Deep  Maps”)   SHELLEY  FISHER  FISHKIN  paintings,   drawings,   maps,   photos,   books,  

Fishkin, Shelley Fisher

2011-01-01T23:59:59.000Z

322

Marine geology of the Bay of Campeche  

E-Print Network [OSTI]

LIBRARY /i & L IBRRAYA B/ iA&Co MARINE GEOLOGY OP SHE BAT OF CAMPECHE A Dissertation By JOE SCOTT CREAGER ? ? ? Submitted to the Graduate School of the Agricultural and Mechanical College of Texas in partial fulfillment of the requirements... for the degree of DOCTOR OF PHILOSOPHY August, 1958 Major Subject: Geological Oceanography MARINE GEOLOGY OF THE BAT OF CAMPECHE A Dissertation By JOE SCOTT CREAGEB Approved as to style and content by: JLN. Chairman of Committee Heady Department...

Creager, Joe S.

1958-01-01T23:59:59.000Z

323

A geologic investigation of Longhorn Cavern  

E-Print Network [OSTI]

A GEOLOGIC INVESTIGATION OF LONGHORN CAVERN A Thesis by VICTORIA LYNN WALTERS Submitted to the Office of Graduate Studies of Texas ASM University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 1992... Major Subject: Geology A GEOLOGIC INVESTIGATION OF LONGHORN CAVERN A Thesis by VICTORIA LYNN WALTERS Approved as to style and content by: Christ pher C. Mathewson (Chair of Committee) Wy M Ah (Member) J. R. Giardino (Member) John H. Spang...

Walters, Victoria Lynn

1992-01-01T23:59:59.000Z

324

Carbonic Acid Shows Promise in Geology, Biology  

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

The Surprising Secrets of Carbonic Acid Probing the Surprising Secrets of Carbonic Acid Berkeley Lab Study Holds Implications for Geological and Biological Processes October 23,...

325

United States Geological Survey Geospatial Information Response  

E-Print Network [OSTI]

1 United States Geological Survey Geospatial Information Response Standard Operating Procedures May 20, 2013 Executive Summary The Geospatial, reporting requirements, and business processes for acquiring and providing geospatial

Torgersen, Christian

326

Regional geophysics, Cenozoic tectonics and geologic resources...  

Open Energy Info (EERE)

and adjoining regions Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Proceedings: Regional geophysics, Cenozoic tectonics and geologic resources of...

327

GEOLOGIC CARBON SEQUESTRATION STRATEGIES FOR CALIFORNIA  

E-Print Network [OSTI]

CALIFORNIA ENERGY COMMISSION GEOLOGIC CARBON SEQUESTRATION STRATEGIES FOR CALIFORNIA to extend our thanks to the authors of various West Coast Regional Carbon Sequestration Partnership

328

WIPP Celebrates 14th Anniversary  

Broader source: Energy.gov [DOE]

CARLSBAD, N.M. – The Waste Isolation Pilot Plant (WIPP) recently marked its 14th year as America’s only operational deep geologic repository for the disposal of radioactive waste.

329

Title 40 CFR Part 191 Subparts B and C  

E-Print Network [OSTI]

Carlsbad Field Office Carlsbad, New Mexico #12;Compliance Recertification Application 2014 Executive Pilot Plant (WIPP), located near Carlsbad, New Mexico, is a deep geologic3 repository for the disposal

330

Title 40 CFR Part 191 Subparts B and C  

E-Print Network [OSTI]

Carlsbad Field Office Carlsbad, New Mexico #12;Executive Summary #12;Title 40 CFR Part 191 Subparts B and C Carlsbad, New Mexico, is a deep geologic repository for the disposal of transuranic (TRU) wastes generated

331

Geology and engineering geology of a Wilcox lignite deposit in northeastern Rusk County, Texas  

E-Print Network [OSTI]

GEOLOGY AND ENGINEERING GEOLOGY OF A WILCOX LIGNITE DEPOSIT IN NORTHEASTERN RUSK COUNTY, TEXAS A Thesis by William F. Cole Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree...) (Member) (Member) (Member) (Member) ad of Department) August 1980 ABSTRACT Geology and Engineering Geology of a Wilcox Lignite Deposit in Northeastern Rusk County, Texas (August, 1980) William 7. Cole, B. S. , Texas ASM University Chairman...

Cole, William F.

1980-01-01T23:59:59.000Z

332

Effects of some common geological features on two-dimensional variably saturated flow  

SciTech Connect (OSTI)

This paper presents results of unsaturated flow simulations undertaken as an auxiliary analysis for the Iterative Performance Assessment (IPA) project, one of the approaches adopted by the U.S. NRC to develop repository license application review capabilities. The effects on flow of common geological features, such as nonhorizontal stratification and vertical or near-vertical fault zones intersecting the strata, in a two-dimensional (2D) domain are studied. Results indicate that the presence of layers and crosscutting fault zones tend to induce three-dimensional (3D) unstable flows in the unsaturated zone. The instability is manifested in our simulations by an oscillatory behavior of steady state. This numerical instability imposes extremely stringent criteria on the time step used in the simulation. Finally, once stable steady-state solutions are attained, the effect of the crossing point in the matrix-fault unsaturated hydraulic conductivity curve on groundwater flux vectors and moisture content distributions is studied.

Bagtzoglou, A.C.; Ababou, R.; Sagar, B.; Islam, M.R. [Southwest Research Institute, San Antonio, TX (United States)

1993-12-31T23:59:59.000Z

333

Coda-wave interferometry analysis of time-lapse VSP data for monitoring geological carbon sequestration  

E-Print Network [OSTI]

Monitoring Geological Carbon Sequestration Authors: RongmaoGeological Carbon Sequestration ABSTRACT Injection andmonitoring geological carbon sequestration. ACKNOWLEDGEMENTS

Zhou, R.

2010-01-01T23:59:59.000Z

334

26 AUGUST 2009, GSA TODAY Murray Hitzman, Dept. of Geology and Geological  

E-Print Network [OSTI]

geology. Economic geology flourished from the end of World War II into the early 1970s, with major, industrial minerals, construction aggregates, and uranium but excludes carbon-based energy resources geology in academia: An impending crisis? (~15%) of the 2007 U.S. gross domestic product. The United

Barton, Mark D.

335

Petroleum Geology Conference series doi: 10.1144/0070921  

E-Print Network [OSTI]

Petroleum Geology Conference series doi: 10.1144/0070921 2010; v. 7; p. 921-936Petroleum Geology Collection to subscribe to Geological Society, London, Petroleum Geologyhereclick Notes on January 5, 2011Downloaded by by the Geological Society, London © Petroleum Geology Conferences Ltd. Published #12;An

Demouchy, Sylvie

336

Repository Integration Program: RIP performance assessment and strategy evaluation model theory manual and user`s guide  

SciTech Connect (OSTI)

This report describes the theory and capabilities of RIP (Repository Integration Program). RIP is a powerful and flexible computational tool for carrying out probabilistic integrated total system performance assessments for geologic repositories. The primary purpose of RIP is to provide a management tool for guiding system design and site characterization. In addition, the performance assessment model (and the process of eliciting model input) can act as a mechanism for integrating the large amount of available information into a meaningful whole (in a sense, allowing one to keep the ``big picture`` and the ultimate aims of the project clearly in focus). Such an integration is useful both for project managers and project scientists. RIP is based on a `` top down`` approach to performance assessment that concentrates on the integration of the entire system, and utilizes relatively high-level descriptive models and parameters. The key point in the application of such a ``top down`` approach is that the simplified models and associated high-level parameters must incorporate an accurate representation of their uncertainty. RIP is designed in a very flexible manner such that details can be readily added to various components of the model without modifying the computer code. Uncertainty is also handled in a very flexible manner, and both parameter and model (process) uncertainty can be explicitly considered. Uncertainty is propagated through the integrated PA model using an enhanced Monte Carlo method. RIP must rely heavily on subjective assessment (expert opinion) for much of its input. The process of eliciting the high-level input parameters required for RIP is critical to its successful application. As a result, in order for any project to successfully apply a tool such as RIP, an enormous amount of communication and cooperation must exist between the data collectors, the process modelers, and the performance. assessment modelers.

NONE

1995-11-01T23:59:59.000Z

337

E-Print Network 3.0 - alternative repository criticality-control...  

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

approach called Product Data... a repository design that addresses the requirements. Section 4 concludes with an overview of how we plan Source: Bieman, James M. - Department...

338

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone  

E-Print Network [OSTI]

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone formations, the French national radioactive waste management agency (ANDRA) started in 2000

Boyer, Edmond

339

EA-1404: Actinide Chemistry and Repository Science Laboratory, Carlsbad, New Mexico  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts for the proposal to construct and operate an Actinide Chemistry and Repository Science Laboratory to support chemical research activities related to the...

340

Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect  

E-Print Network [OSTI]

Mallants, D. , 2002. Gas generation and migration in Boomof Post-Disposal Gas Generation in a Repository for SpentCorrosion-Induced Gas Generation in a Nuclear Waste

Xu, T.

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

The U.S. Geological Survey  

E-Print Network [OSTI]

U sing a geology-based assessment methodology, the U.S. Geological Survey estimated a total of 1.525 trillion barrels of oil in place in seventeen oil shale zones in the Eocene Green River Formation in the Piceance Basin, western Colorado.

unknown authors

342

Geological Sciences Jeffrey D. Keith, Chair  

E-Print Network [OSTI]

, such as assessment and forecasting of natural hazards, environmental change, and discovery of energy and mineral resources. Some of the diverse disciplines that can be studied in this department include general geology Catalog. Global Geology Program Each year the department provides opportunities for advanced

Hart, Gus

343

Geology, Society and the Environmental health  

E-Print Network [OSTI]

management Environmental analysis Sustainability Learning Objectives #12; As members of the biological The water we drink The air we breathe Geologic factors in environmental health #12; Health can be definedChapter 19 Geology, Society and the Future #12; Environmental health Air pollution Waste

Pan, Feifei

344

Careers in Geology Department of Geosciences  

E-Print Network [OSTI]

, coal, and water. Environmental geology ­ study of problems associated with pollution, waste disposal ­ study of earth materials of economic interest, including metals, minerals, building stone, petroleum Army Corps of Engineers, state geological surveys Industry Oil companies, environmental firms, mining

Logan, David

345

SRS Geology/Hydrogeology Environmental Information Document  

SciTech Connect (OSTI)

The purpose of the Savannah River Site Geology and Hydrogeology Environmental Information Document (EID) is to provide geologic and hydrogeologic information to serve as a baseline to evaluate potential environmental impacts. This EID is based on a summary of knowledge accumulated from research conducted at the Savannah River Site (SRS) and surrounding areas.

Denham, M.E.

1999-08-31T23:59:59.000Z

346

Sandhills Geology Response by Professor James Goeke  

E-Print Network [OSTI]

. As it turns out, a good portion of the pipeline is not in the Sandhills and doesn't overlie the Ogallala1 Sandhills Geology Response by Professor James Goeke Providing a short, succinct description of the sandhills geology is a difficult and nebulous request. The sandhills themselves are primarily eolian

Nebraska-Lincoln, University of

347

GEOLOGICAL SURVEY OF CANADA OPEN FILE 7462  

E-Print Network [OSTI]

and the McArthur River uranium deposit, Athabasca Basin; Geological Survey of Canada, Open File 7462, 35 pGEOLOGICAL SURVEY OF CANADA OPEN FILE 7462 Alteration within the basement rocks associated with the P2 fault and the McArthur River uranium deposit, Athabasca Basin E.E. Adlakha, K. Hattori, G

348

Brigham Young University Geology Studies Volume 28, Part 3  

E-Print Network [OSTI]

#12;Brigham Young University Geology Studies Volume 28, Part 3 CONTENTS Three Creeks Caldera ................................................................................................................................... Scott Dean Geology of the Antelope Peak Area of the Southern .................................................................................................................. Craig D. Hall Geology of the Longlick and White Mountain Area, Southern San Francisco Mountains

Seamons, Kent E.

349

BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 27, Part I  

E-Print Network [OSTI]

#12;BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 27, Part I Preble Formation, a Cambrian Outer ..........................................................................J. Roger Olsen Geology of the Sterling Quadrangle, Sanpete County, Utah ..............................................................................James Michael Taylor Publications and Maps of the Geology Department Cover: Aertalphorograph rhowing

Seamons, Kent E.

350

Converting repository storage criteria into rules for materials conditioning  

SciTech Connect (OSTI)

Productions of waste containers, waste forms and, consequently, waste packages are based on the regulations issued by the German Federal Ministry for the Environment and on the repository storage criteria of the Federal Office for Radiation Protection. Waste treatment facilities must install quality assurance systems and introduce detailed conditioning rules in order to verify these requirements. The conditioning rules incorporate descriptions of all conditioning steps as well as instructions to operators; they are laid down in conditioning manuals. By way of example, the procedure for evaporator concentrate cementation is outlined.

Becker, R.; Stegmaier, W. [Karlsruhe Nuclear Research Center (Germany)

1993-12-31T23:59:59.000Z

351

DEEP Summer Academy 2015 Request for Proposals  

E-Print Network [OSTI]

DEEP Summer Academy 2015 Request for Proposals Deadline: November 30th 2014 Primary Contact: DEEP Request for Proposals: DEEP Summer Academy 2015 About the Engineering Outreach Office The Engineering Office, visit: http://outreach.engineering.utoronto.ca/aboutus.htm Overview of DEEP Summer Academy

Prodiæ, Aleksandar

352

Geology and alteration of the Coso Geothermal Area, Inyo County...  

Open Energy Info (EERE)

California Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Geology and alteration of the Coso Geothermal Area, Inyo County, California Abstract Geology...

353

International Symposium on Site Characterization for CO2 Geological Storage  

E-Print Network [OSTI]

Treatise of Petroleum Geology, Atlas of Oil and Gas Fields,A-A’). phy, geology, stratigraphic contacts, oil and gas andgeology, initial information available from hydrogeology, oil

Tsang, Chin-Fu

2006-01-01T23:59:59.000Z

354

Idaho Geological Survey and University of Idaho Explore for Geothermal...  

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

Idaho Geological Survey and University of Idaho Explore for Geothermal Energy Idaho Geological Survey and University of Idaho Explore for Geothermal Energy January 11, 2013 -...

355

Geologic map of the Sulphur Springs Area, Valles Caldera Geothermal...  

Open Energy Info (EERE)

Area are described. Geologic faults, sheared or brecciated rock, volcanic vents, geothermal wells, hydrothermal alteration, springs, thermal springs, fumaroles, and geologic...

356

On leakage and seepage from geological carbon sequestration sites  

E-Print Network [OSTI]

from Geologic Carbon Sequestration Sites Orlando Lawrencefrom Geologic Carbon Sequestration Sites Farrar, C.D. , M.L.1999. Reichle, D. et al. , Carbon sequestration research and

Oldenburg, C.M.; Unger, A.J.A.; Hepple, R.P.; Jordan, P.D.

2002-01-01T23:59:59.000Z

357

WebDeep Web Surface Web  

E-Print Network [OSTI]

Web WebWeb WebWeb WebHTML Web WebDeep Web Surface Web " " Deep Web21 Dot-ComWebWeb2.0 WebWeb ""Web WebWeb Deep Web WebWeb SNS Web WebWeb 20017BrightPlanet.comDeep Web Web43,000-96,000Web7,500TB(Surface Web500) UIUCDeep Web2004Deep Web 307,000366,000-535,000 WebDeep Web "" Deep Web 1 Web Web #12

358

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4  

E-Print Network [OSTI]

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 Radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 s the UK radioactive waste legacy comprises difficult material which is complex, of mixed origin

359

Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan  

E-Print Network [OSTI]

Benchmarking DAML+OIL Repositories Yuanbo Guo, Jeff Heflin, and Zhengxiang Pan Department, heflin, zhp2}@cse.lehigh.edu Abstract. We present a benchmark that facilitates the evaluation of DAML+OIL repositories in a standard and systematic way. This benchmark is intended to evaluate the performance of DAML+OIL

Heflin, Jeff

360

CVS-Vintage: A Dataset of 14 CVS Repositories of Java Software  

E-Print Network [OSTI]

CVS-Vintage: A Dataset of 14 CVS Repositories of Java Software Martin Monperrus and Matias Martinez INRIA Technical Report, 2012. Abstract This paper presents a dataset of 14 CVS repositories of Java applications. This dataset aims at supporting the replication of early papers in the field of software

Paris-Sud XI, Université de

Note: This page contains sample records for the topic "deep geologic repository" 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

Mining Modern Repositories with Elasticsearch Oleksii Kononenko, Olga Baysal, Reid Holmes, and Michael W. Godfrey  

E-Print Network [OSTI]

Mining Modern Repositories with Elasticsearch Oleksii Kononenko, Olga Baysal, Reid Holmes and highlight its strengths and weaknesses for performing modern mining software repositories research. Categories and Subject Descriptors D.2.3 [Software Engineering]: Coding Tools and Tech- niques General Terms

Godfrey, Michael W.

362

Version control: Answers 1. Create a directory in your svn repository.  

E-Print Network [OSTI]

Version control: Answers 1. Create a directory in your svn repository. Answer: For example: export the directory project_name in your user account (svn requires you to provide a log message using an editor the commit log. Answer: svn log 4. Checkout your repository into another directory. Make a commit from

Alavi, Ali

363

FORT UNION DEEP  

SciTech Connect (OSTI)

Coalbed methane (CBM) is currently the hottest area of energy development in the Rocky Mountain area. The Powder River Basin (PRB) is the largest CBM area in Wyoming and has attracted the majority of the attention because of its high permeability and relatively shallow depth. Other Wyoming coal regions are also being targeted for development, but most of these areas have lower permeability and deeper coal seams. This project consists of the development of a CBM stimulation system for deep coal resources and involves three work areas: (1) Well Placement, (2) Well Stimulation, and (3) Production Monitoring and Evaluation. The focus of this project is the Washakie Basin. Timberline Energy, Inc., the cosponsor, has a project area in southern Carbon County, Wyoming, and northern Moffat County, Colorado. The target coal is found near the top of the lower Fort Union formation. The well for this project, Evans No.1, was drilled to a depth of 2,700 ft. Three coal seams were encountered with sandstone and some interbedded shale between seams. Well logs indicated that the coal seams and the sandstone contained gas. For the testing, the upper seam at 2,000 ft was selected. The well, drilled and completed for this project, produced very little water and only occasional burps of methane. To enhance the well, a mild severity fracture was conducted to fracture the coal seam and not the adjacent sandstone. Fracturing data indicated a fracture half-length of 34 ft, a coal permeability of 0.2226 md, and permeability of 15.3 md. Following fracturing, the gas production rate stabilized at 10 Mscf/day within water production of 18 bpd. The Western Research Institute (WRI) CBM model was used to design a 14-day stimulation cycle followed by a 30-day production period. A maximum injection pressure of 1,200 psig to remain well below the fracture pressure was selected. Model predictions were 20 Mscf/day of air injection for 14 days, a one-day shut-in, then flowback. The predicted flowback was a four-fold increase over the prestimulation rate with production essentially returning to prestimulation rates after 30 days. The physical stimulation was conducted over a 14-day period. Problems with the stimulation injection resulted in a coal bed fire that was quickly quenched when production was resumed. The poststimulation, stabilized production was three to four times the prestimulation rate. The methane content was approximately 45% after one day and increased to 65% at the end of 30 days. The gas production rate was still two and one-half times the prestimulation rate at the end of the 30-day test period. The field results were a good match to the numerical simulator predictions. The physical stimulation did increase the production, but did not produce a commercial rate.

Lyle A. Johnson Jr.

2002-03-01T23:59:59.000Z

364

FORT UNION DEEP  

SciTech Connect (OSTI)

Coalbed methane (CBM) is currently the hottest area of energy development in the Rocky Mountain area. The Powder River Basin (PRB) is the largest CBM area in Wyoming and has attracted the majority of the attention because of its high permeability and relatively shallow depth. Other Wyoming coal regions are also being targeted for development, but most of these areas have lower permeability and deeper coal seams. This project consists of the development of a CBM stimulation system for deep coal resources and involves three work areas: (1) Well Placement, (2) Well Stimulation, and (3) Production Monitoring and Evaluation. The focus of this project is the Washakie Basin. Timberline Energy, Inc., the cosponsor, has a project area in southern Carbon County, Wyoming, and northern Moffat County, Colorado. The target coal is found near the top of the lower Fort Union formation. The well for this project, Evans No.1, was drilled to a depth of 2,700 ft. Three coal seams were encountered with sandstone and some interbedded shale between seams. Well logs indicated that the coal seams and the sandstone contained gas. For the testing, the upper seam at 2,000 ft was selected. The well, drilled and completed for this project, produced very little water and only occasional burps of methane. To enhance the well, a mild severity fracture was conducted to fracture the coal seam and not the adjacent sandstone. Fracturing data indicated a fracture half-length of 34 ft, a coal permeability of 0.2226 md, and permeability of 15.3 md. Following fracturing, the gas production rate stabilized at 10 Mscf/day within water production of 18 bpd. The Western Research Institute (WRI) CBM model was used to design a 14-day stimulation cycle followed by a 30-day production period. A maximum injection pressure of 1,200 psig to remain well below the fracture pressure was selected. Model predictions were 20 Mscf/day of air injection for 14 days, a one-day shut-in, then flowback. The predicted flowback was a four-fold increase over the prestimulation rate with production essentially returning to prestimulation rates after 30 days. The physical stimulation was conducted over a 14-day period. Problems with the stimulation injection resulted in a coal bed fire that was quickly quenched when production was resumed. The poststimulation, stabilized production was three to four times the prestimulation rate. The methane content was approximately 45% after one day and increased to 65% at the end of 30 days. The gas production rate was still two and one-half times the prestimulation rate at the end of the 30-day test period. The field results were a good match to the numerical simulator predictions. The physical stimulation did increase the production, but did not produce a commercial rate.

Lyle A. Johnson Jr.

2002-09-01T23:59:59.000Z

365

Lessons Learned from Natural and Industrial Analogues for Storage of Carbon Dioxide in Deep Geological Formations  

E-Print Network [OSTI]

types of potential reservoirs: abandoned and producing oilgeological reservoirs, including abandoned and producing oilreservoir; Salt: Salt dome or bedded salt; Coal: Abandoned

Benson, Sally M.; Hepple, Robert; Apps, John; Tsang, Chin-Fu; Lippmann, Marcelo

2002-01-01T23:59:59.000Z

366

Lessons Learned from Natural and Industrial Analogues for Storage of Carbon Dioxide in Deep Geological Formations  

E-Print Network [OSTI]

backfill materials, such as porosity, permeability, and deformation Deformation (salt creep) of roof, wall, and floor of the tunnels

Benson, Sally M.; Hepple, Robert; Apps, John; Tsang, Chin-Fu; Lippmann, Marcelo

2002-01-01T23:59:59.000Z

367

Lessons Learned from Natural and Industrial Analogues for Storage of Carbon Dioxide in Deep Geological Formations  

E-Print Network [OSTI]

in the Yaggy natural gas storage field (a mined salt-cavernnatural gas to leak from a mined salt cavern used for storage.

Benson, Sally M.; Hepple, Robert; Apps, John; Tsang, Chin-Fu; Lippmann, Marcelo

2002-01-01T23:59:59.000Z

368

Deep in Data: Empirical Data Based Software Accuracy Testing Using the Building America Field Data Repository: Preprint  

SciTech Connect (OSTI)

An opportunity is available for using home energy consumption and building description data to develop a standardized accuracy test for residential energy analysis tools. That is, to test the ability of uncalibrated simulations to match real utility bills. Empirical data collected from around the United States have been translated into a uniform Home Performance Extensible Markup Language format that may enable software developers to create translators to their input schemes for efficient access to the data. This may facilitate the possibility of modeling many homes expediently, and thus implementing software accuracy test cases by applying the translated data. This paper describes progress toward, and issues related to, developing a usable, standardized, empirical data-based software accuracy test suite.

Neymark, J.; Roberts, D.

2013-06-01T23:59:59.000Z

369

Dessicant materials screening for backfill in a salt repository  

SciTech Connect (OSTI)

Maintaining an anhydrous environment around nuclear waste stored in a salt repository is a concern which can be alleviated by using a desiccant material for backfilling. Such a desiccant should desiccate a brine yet be non deliquescent, the hydrated product should have moderate thermal stability, and the desiccant should have a high capacity and be readily available. From a literature search MgO and CaO were identified for detailed study. These oxides, and an intimate mixture of the two obtained by calcining dolomite, were used in experiments to further determine their suitability. They proved to be excellent desiccants with a high water capacity. The hydrates of both have moderate thermal stability and a high water content. Both MgO and CaO react in an alkaline chloride brine forming oxychloride compounds with different waters of crystallization. Some of these compounds are the Sorel Cements. CaO hydrates to Ca(OH)/sub 2/ which carbonates with CO/sub 2/ in air to form CaCO/sub 3/ and release the hydrated water. Thus the intimate mixture of CaO and MgO from calcined dolomite may serve as a desiccant and remove CO/sub 2/ from the repository atmosphere.

Simpson, D.R.

1980-10-01T23:59:59.000Z

370

Reaction Mechanisms in Petroleum: From Experimentation to Upgrading and Geological Conditions  

E-Print Network [OSTI]

Among the numerous questions that arise concerning the exploitation of petroleum from unconventional reservoirs, lie the questions of the composition of hydrocarbons present in deep seated HP-HT reservoirs or produced during in-situ upgrading steps of heavy oils and oil shales. Our research shows that experimental hydrocarbon cracking results obtained in the laboratory cannot be extrapolated to geological reservoir conditions in a simple manner. Our demonstration is based on two examples: 1) the role of the hydrocarbon mixture composition on reaction kinetics (the "mixing effect") and the effects of pressure (both in relationship to temperature and time). The extrapolation of experimental data to geological conditions requires investigation of the free-radical reaction mechanisms through a computed kinetic model. We propose a model that takes into account 52 reactants as of today, and which can be continuously improved by addition of new reactants as research proceeds. This model is complete and detailed enou...

Lannuzel, Frédéric; Bounaceur, Roda; Marquaire, Paul-Marie; Michels, Raymond

2009-01-01T23:59:59.000Z

371

Global Warming in Geologic Time  

ScienceCinema (OSTI)

The notion is pervasive in the climate science community and in the public at large that the climate impacts of fossil fuel CO2 release will only persist for a few centuries. This conclusion has no basis in theory or models of the atmosphere / ocean carbon cycle, which we review here. The largest fraction of the CO2 recovery will take place on time scales of centuries, as CO2 invades the ocean, but a significant fraction of the fossil fuel CO2, ranging in published models in the literature from 20-60%, remains airborne for a thousand years or longer. Ultimate recovery takes place on time scales of hundreds of thousands of years, a geologic longevity typically associated in public perceptions with nuclear waste. The glacial / interglacial climate cycles demonstrate that ice sheets and sea level respond dramatically to millennial-timescale changes in climate forcing. There are also potential positive feedbacks in the carbon cycle, including methane hydrates in the ocean, and peat frozen in permafrost, that are most sensitive to the long tail of the fossil fuel CO2 in the atmosphere.

David Archer

2010-01-08T23:59:59.000Z

372

Global Warming in Geologic Time  

SciTech Connect (OSTI)

The notion is pervasive in the climate science community and in the public at large that the climate impacts of fossil fuel CO2 release will only persist for a few centuries. This conclusion has no basis in theory or models of the atmosphere / ocean carbon cycle, which we review here. The largest fraction of the CO2 recovery will take place on time scales of centuries, as CO2 invades the ocean, but a significant fraction of the fossil fuel CO2, ranging in published models in the literature from 20-60%, remains airborne for a thousand years or longer. Ultimate recovery takes place on time scales of hundreds of thousands of years, a geologic longevity typically associated in public perceptions with nuclear waste. The glacial / interglacial climate cycles demonstrate that ice sheets and sea level respond dramatically to millennial-timescale changes in climate forcing. There are also potential positive feedbacks in the carbon cycle, including methane hydrates in the ocean, and peat frozen in permafrost, that are most sensitive to the long tail of the fossil fuel CO2 in the atmosphere.

David Archer

2008-02-27T23:59:59.000Z

373

JUDSON MEAD GEOLOGIC FIELD STATION OF INDIANA UNIVERSITY 2013 APPLICATION FOR ADMISSION  

E-Print Network [OSTI]

Geology G Structural Geology G Sedimentology/Stratigraphy G Sedimentology/Stratigraphy G Sophomore G

Polly, David

374

GEOL 102: Historical Geology Exam 1 Review  

E-Print Network [OSTI]

& Last Appearance Datum; Zone #12;Other Methods of Stratigraphy Magnetostratigraphy (Chron); Sequence Stratigraphy (Sequence) Geologic Column Chronostratigraphy (Rock) Geochronology (Time) Eonthem Eon Erathem Era (= clastic = siliciclastic), biogenic, chemical; strata Detrital Sedimentary Cycle: Source Weathering

Holtz Jr., Thomas R.

375

Carbon Trading Protocols for Geologic Sequestration  

E-Print Network [OSTI]

expensive, real reduction in CO2 emissions from their ownstored CO2 must create an actual reduction in the emissionsCO2 is instead obtained from geologic formations then the goal of the emission reduction

Hoversten, Shanna

2009-01-01T23:59:59.000Z

376

Deep Vadose Zone - Hanford Site  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINL isSeparationsRelevantDeep ReactiveDeep

377

A geologic application of Biot's buckling theory  

E-Print Network [OSTI]

Subject: Geophysics A GEOLOGIC APPLlCATION OF BIOT'S BUCKLING THEORY A Thesis by WILLIAM DANIEL HEINZE Approved as to style and content by: (Chairman of Commit e) (Head of Department-Member) (Member) (Member) May 1972 ABSTRACT A Geologic..., et al. , (1967) indicates that the Georgetown was never buried by more than 2000 meters of sediment. The Del Rio Mark, 20 m thick, is predominantly clay and calcareous clay intercalated with thin lenses of clayey limestone. The thick-bedded Buda...

Heinze, William Daniel

1972-01-01T23:59:59.000Z

378

STIMULATION TECHNOLOGIES FOR DEEP WELL COMPLETIONS  

SciTech Connect (OSTI)

The Department of Energy (DOE) is sponsoring a Deep Trek Program targeted at improving the economics of drilling and completing deep gas wells. Under the DOE program, Pinnacle Technologies is conducting a project to evaluate the stimulation of deep wells. The objective of the project is to assess U.S. deep well drilling & stimulation activity, review rock mechanics & fracture growth in deep, high pressure/temperature wells and evaluate stimulation technology in several key deep plays. Phase 1 was recently completed and consisted of assessing deep gas well drilling activity (1995-2007) and an industry survey on deep gas well stimulation practices by region. Of the 29,000 oil, gas and dry holes drilled in 2002, about 300 were drilled in the deep well; 25% were dry, 50% were high temperature/high pressure completions and 25% were simply deep completions. South Texas has about 30% of these wells, Oklahoma 20%, Gulf of Mexico Shelf 15% and the Gulf Coast about 15%. The Rockies represent only 2% of deep drilling. Of the 60 operators who drill deep and HTHP wells, the top 20 drill almost 80% of the wells. Six operators drill half the U.S. deep wells. Deep drilling peaked at 425 wells in 1998 and fell to 250 in 1999. Drilling is expected to rise through 2004 after which drilling should cycle down as overall drilling declines.

Stephen Wolhart

2003-06-01T23:59:59.000Z

379

Geological Society of America 3300 Penrose Place  

E-Print Network [OSTI]

correlation is available (e.g., Thomas, 1998). Rapid extinction of many deep-sea benthic foraminiferal species the extinction faunas were dominated by small species, which resemble opportunistic taxa under high A major extinction of deep-sea benthic foraminifera in open ocean occurred at the Paleocene

Royer, Dana

380

BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 25,Part 1  

E-Print Network [OSTI]

#12;BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 25,Part 1 Papers reviewing geology of field trip areas, 31st annual meeting, Rocky Mountain Section, Geological Society of America, April 28 ....................................................................................................................................................... Geology of Volcanic Rocks and Mineral Deposits in the Southern Thomas Range, Utah: A Brief Summary

Seamons, Kent E.

Note: This page contains sample records for the topic "deep geologic repository" 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

Missouri University of Science and Technology 1 Geology and Geophysics  

E-Print Network [OSTI]

Missouri University of Science and Technology 1 Geology and Geophysics Graduate work in Geology are designed to provide you with an understanding of the fundamentals and principles of geology, geochemistry and Environmental Geochemistry · Mineralogy/Petrology/Economic Geology · Geophysics/Tectonics/Remote Sensing

Missouri-Rolla, University of

382

Stimulation Technologies for Deep Well Completions  

SciTech Connect (OSTI)

The Department of Energy (DOE) is sponsoring the Deep Trek Program targeted at improving the economics of drilling and completing deep gas wells. Under the DOE program, Pinnacle Technologies conducted a study to evaluate the stimulation of deep wells. The objective of the project was to review U.S. deep well drilling and stimulation activity, review rock mechanics and fracture growth in deep, high-pressure/temperature wells and evaluate stimulation technology in several key deep plays. This report documents results from this project.

Stephen Wolhart

2005-06-30T23:59:59.000Z

383

NOVEL CONCEPTS RESEARCH IN GEOLOGIC STORAGE OF CO2 PHASE III  

SciTech Connect (OSTI)

As part of the Department of Energy's (DOE) initiative on developing new technologies for storage of carbon dioxide in geologic reservoirs, Battelle has been investigating the feasibility of CO{sub 2} sequestration in the deep saline reservoirs in the Ohio River Valley region. In addition to the DOE, the project is being sponsored by American Electric Power (AEP), BP, The Ohio Coal Development Office (OCDO) of the Ohio Air Quality Development Authority, Schlumberger, and Battelle. The main objective of the project is to demonstrate that CO{sub 2} sequestration in deep formations is feasible from engineering and economic perspectives, as well as being an inherently safe practice and one that will be acceptable to the public. In addition, the project is designed to evaluate the geology of deep formations in the Ohio River Valley region in general and in the vicinity of AEP's Mountaineer Power Plant in particular, in order to determine their potential use for conducting a long-term test of CO{sub 2} disposal in deep saline formations. The current technical progress report summarizes activities completed for the January-March 2006 period of the project. As discussed in the following report, the main accomplishments were analysis of Copper Ridge ''B-zone'' reservoir test results from the AEP No.1 well and design and feasibility support tasks. Reservoir test results indicate injection potential in the Copper Ridge ''B-zone'' may be significantly higher than anticipated for the Mountaineer site. Work continued on development of injection well design options, engineering assessment of CO{sub 2} capture systems, permitting, and assessment of monitoring technologies as they apply to the project site. In addition, organizational and scheduling issues were addressed to move the project toward an integrated carbon capture and storage system at the Mountaineer site. Overall, the current design feasibility phase project is proceeding according to plans.

Neeraj Gupta

2006-05-18T23:59:59.000Z

384

NOVEL CONCEPTS RESEARCH IN GEOLOGIC STORAGE OF CO2 PHASE III  

SciTech Connect (OSTI)

As part of the Department of Energy's (DOE) initiative on developing new technologies for storage of carbon dioxide in geologic reservoirs, Battelle has been investigating the feasibility of CO{sub 2} sequestration in the deep saline reservoirs in the Ohio River Valley region. In addition to the DOE, the project is being sponsored by American Electric Power (AEP), BP, The Ohio Coal Development Office (OCDO) of the Ohio Air Quality Development Authority, Schlumberger, and Battelle. The main objective of the project is to demonstrate that CO{sub 2} sequestration in deep formations is feasible from engineering and economic perspectives, as well as being an inherently safe practice and one that will be acceptable to the public. In addition, the project is designed to evaluate the geology of deep formations in the Ohio River Valley region in general and in the vicinity of AEP's Mountaineer Power Plant in particular, in order to determine their potential use for conducting a long-term test of CO{sub 2} disposal in deep saline formations. The current technical progress report summarizes activities completed for the October through December 2005 period of the project. As discussed in the following report, the main field activity was reservoir testing in the Copper Ridge ''B-zone'' in the AEP No.1 well. In addition reservoir simulations were completed to assess feasibility of CO{sub 2} injection for the Mountaineer site. These reservoir testing and computer simulation results suggest that injection potential may be substantially more than anticipated for the Mountaineer site. Work also continued on development of injection well design options, engineering assessment of CO{sub 2} capture systems, permitting, and assessment of monitoring technologies as they apply to the project site. Overall, the current design feasibility phase project is proceeding according to plans.

Neeraj Gupta

2006-01-23T23:59:59.000Z

385

Large-scale impact of CO2 storage in deep saline aquifers: A sensitivity study on pressure response in stratified systems  

E-Print Network [OSTI]

Large-scale impact of CO2 storage in deep saline aquifers: A sensitivity study on pressure response storage potential of all the geological CO2 storage options and are widely distributed throughout the globe in all sedimentary basins.ForCO2 storage tohaveasignificantimpact on atmospheric levels

Zhou, Quanlin

386

Well injectivity during CO2 storage operations in deep saline aquifers6 1: Experimental investigation of drying effects, salt precipitation and7  

E-Print Network [OSTI]

Carbon Capture and Storage (CCS) is a technique than can potentially limit the accumulation29-17Jan2014 #12;3 1. Introduction51 52 Geological sequestration of CO2 into deep saline aquifers studied54 much less than mature oil & gas reservoirs. Injection of carbon dioxide into saline aquifers55

Boyer, Edmond

387

DOE Geothermal Data Repository - Tethering Data to Information: Preprint  

SciTech Connect (OSTI)

Data are not inherently information. Without context, data are just numbers, figures, names, or points on a line. By assigning context to data, we can validate ideas, form opinions, and generate knowledge. This is an important distinction to information scientists, as we recognize that the context in which we keep our data plays a big part in generating its value. The mechanisms used to assign this context often include their own data, supplemental to the data being described and defining semantic relationships, commonly referred to as metadata. This paper provides the status of the DOE Geothermal Data Repository (DOE GDR), including recent efforts to tether data submissions to information, discusses the important distinction between data and information, outlines a path to generate useful knowledge from raw data, and details the steps taken in order to become a node on the National Geothermal Data System (NGDS).

Weers, J.; Anderson, A.

2014-02-01T23:59:59.000Z

388

Page 1 | B.S. in Geology | Academic Plan of Study Updated April 2014 B.S. in Geology  

E-Print Network [OSTI]

Page 1 | B.S. in Geology | Academic Plan of Study Updated April 2014 B.S. in Geology Academic Plan Available: No · Other Information: GEO (Geology & Earth Science Organization); GTU (Gamma Theta Upsilon coordinator for METR, thsirle@uncc.edu PROGRAM REQUIREMENTS Geology at UNC Charlotte is for students who

Raja, Anita

389

Chemistry of transuranium elements in salt-base repository  

SciTech Connect (OSTI)

The mobility and potential release of actinides into the accessible environment continues to be the key performance assessment concern of nuclear repositories. Actinide, in particular plutonium speciation under the wide range of conditions that can exist in the subsurface is complex and depends strongly on the coupled effects of redox conditions, inorganic/organic complexation, and the extent/nature of aggregation. Understanding the key factors that define the potential for actinide migration is, in this context, an essential and critical part of making and sustaining a licensing case for a nuclear repository. Herein we report on recent progress in a concurrent modeling and experimental study to determine the speciation of plutonium, uranium and americium in high ionic strength Na-CI-Mg brines. This is being done as part of the ongomg recertification effort m the Waste Isolation Pilot Plant (WIPP). The oxidation-state specific solubility of actinides were established in brine as function of pC{sub H+}, brine composition and the presence and absence of organic chelating agents and carbonate. An oxidation-state invariant analog approach using Nd{sup 3+} and Th{sup 4+} was used for An{sup 3+} and An{sup 4+} respectively. These results show that organic ligands and hydrolysis are key factors for An(III) solubility, hydrolysis at pC{sub H+} above 8 is predominate for An(IV) and carbonates are the key factor for U(VI) solubility. The effect of high ionic strength and brine components measured in absence of carbonates leads to measurable increased in overall solubility over analogous low ionic strength groundwater. Less is known about the bioreduction of actinides by halo-tolerant microorganisms, but there is now evidence that bioreduction does occur and is analogous, in many ways, to what occurs with soil bacteria. Results of solubility studies that focus on Pitzer parameter corrections, new species (e.g. borate complexation), and the thermodynamic parameters for modeling are discussed.

Borkowski, Marian [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory; Lucchini, Jean - Francois [Los Alamos National Laboratory; Richmann, Michael K [Los Alamos National Laboratory; Khaing, H [Los Alamos National Laboratory; Swanson, J [Los Alamos National Laboratory; Ams, D [Los Alamos National Laboratory

2010-12-02T23:59:59.000Z

390

The Construction of the Konrad Repository - Status and Perspective - 13034  

SciTech Connect (OSTI)

Due to the Atomic Energy Act of Germany the Federation is responsible for the construction and operation of installations for the safekeeping and disposal of radioactive waste. The Federal Office for Radiation Protection (Bundesamt fuer Strahlenschutz - BfS) is assigned with this duty. In 1982 the abandoned iron ore mine Konrad near Salzgitter (Federal State of Lower Saxony) was proposed as a repository for low and intermediate level radioactive waste with negligible heat generation. After 20 years of plan approval procedure the license was granted by the Ministry for Environment of Lower Saxony in May 2002. This decision was finally confirmed by the Federal Administrative Court in March 2007. The construction has started, but former assumptions about the beginning of waste emplacement tuned out to be too optimistic. In the course of the preparatory work and the implementation planning it turned out that many changes need to be done. As a matter of fact most of the documents and planning originate from the 1990's and need to be revised because from that time on until now no adaptation was appropriate. The necessity to apply the state-of-the-art technology and other legal implications give rise to further changes and new licensing procedures, especially building licenses. Furthermore, the license from 2002 also includes a lot of collateral clauses that need to be fulfilled before radioactive waste can be emplaced. With this in mind, the time frame for the construction of the Konrad repository was revised in 2010. As a result, the completion of the erection before 2019 does not seem to be realistic. (authors)

Kunze, V. [Bundesamt fuer Strahlenschutz - BfS, Postfach 10 01 49, 38201 Salzgitter (Germany)] [Bundesamt fuer Strahlenschutz - BfS, Postfach 10 01 49, 38201 Salzgitter (Germany)

2013-07-01T23:59:59.000Z

391

Mainstreaming Preservation through Slicing and Dicing of Digital Repositories: Investigating Alternative Service and Resource Options for ContextMiner Using Data Grid Technology  

E-Print Network [OSTI]

efficiencies of resource use, (2) management of dependencies across entities, and (3) the repository business model

Lee, Christopher; Marciano, Richard; Hou, Chien-Yi; Shah, Chirag

2009-01-01T23:59:59.000Z

392

An Assessment of Geological Carbon Sequestration Options in the Illinois Basin  

SciTech Connect (OSTI)

The Midwest Geological Sequestration Consortium (MGSC) has investigated the options for geological carbon dioxide (CO{sub 2}) sequestration in the 155,400-km{sup 2} (60,000-mi{sup 2}) Illinois Basin. Within the Basin, underlying most of Illinois, western Indiana, and western Kentucky, are relatively deeper and/or thinner coal resources, numerous mature oil fields, and deep salt-water-bearing reservoirs that are potentially capable of storing CO{sub 2}. The objective of this Assessment was to determine the technical and economic feasibility of using these geological sinks for long-term storage to avoid atmospheric release of CO{sub 2} from fossil fuel combustion and thereby avoid the potential for adverse climate change. The MGSC is a consortium of the geological surveys of Illinois, Indiana, and Kentucky joined by six private corporations, five professional business associations, one interstate compact, two university researchers, two Illinois state agencies, and two consultants. The purpose of the Consortium is to assess carbon capture, transportation, and storage processes and their costs and viability in the three-state Illinois Basin region. The Illinois State Geological Survey serves as Lead Technical Contractor for the Consortium. The Illinois Basin region has annual emissions from stationary anthropogenic sources exceeding 276 million metric tonnes (304 million tons) of CO{sub 2} (>70 million tonnes (77 million tons) carbon equivalent), primarily from coal-fired electric generation facilities, some of which burn almost 4.5 million tonnes (5 million tons) of coal per year. Assessing the options for capture, transportation, and storage of the CO{sub 2} emissions within the region has been a 12-task, 2-year process that has assessed 3,600 million tonnes (3,968 million tons) of storage capacity in coal seams, 140 to 440 million tonnes (154 to 485 million tons) of capacity in mature oil reservoirs, 7,800 million tonnes (8,598 million tons) of capacity in saline reservoirs deep beneath geological structures, and 30,000 to 35,000 million tonnes (33,069 to 38,580 million tons) of capacity in saline reservoirs on a regional dip >1,219 m (4,000 ft) deep. The major part of this effort assessed each of the three geological sinks: coals, oil reservoirs, and saline reservoirs. We linked and integrated options for capture, transportation, and geological storage with the environmental and regulatory framework to define sequestration scenarios and potential outcomes for the region. Extensive use of Geographic Information Systems (GIS) and visualization technology was made to convey results to project sponsors, other researchers, the business community, and the general public. An action plan for possible technology validation field tests involving CO{sub 2} injection was included in a Phase II proposal (successfully funded) to the U.S. Department of Energy with cost sharing from Illinois Clean Coal Institute.

Robert Finley

2005-09-30T23:59:59.000Z

393

TECHNICAL ADVANCEMENTS AND ISSUES ASSOCIATED WITH  

E-Print Network [OSTI]

Lessons Learned from Yucca Mountain and Other Programs June 2011 A Report to Congress and the Secretary's efforts to develop a deep geologic repository for high-activity waste1 at Yucca Mountain in Nevada Commission (NRC) to construct a repository at Yucca Mountain. An important part of the Board's mission

394

Deep-web search engine ranking algorithms  

E-Print Network [OSTI]

The deep web refers to content that is hidden behind HTML forms. The deep web contains a large collection of data that are unreachable by link-based search engines. A study conducted at University of California, Berkeley ...

Wong, Brian Wai Fung

2010-01-01T23:59:59.000Z

395

Reference design and operations for deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

A reference design and operational procedures for the disposal of high-level radioactive waste in deep boreholes have been developed and documented. The design and operations are feasible with currently available technology and meet existing safety and anticipated regulatory requirements. Objectives of the reference design include providing a baseline for more detailed technical analyses of system performance and serving as a basis for comparing design alternatives. Numerous factors suggest that deep borehole disposal of high-level radioactive waste is inherently safe. Several lines of evidence indicate that groundwater at depths of several kilometers in continental crystalline basement rocks has long residence times and low velocity. High salinity fluids have limited potential for vertical flow because of density stratification and prevent colloidal transport of radionuclides. Geochemically reducing conditions in the deep subsurface limit the solubility and enhance the retardation of key radionuclides. A non-technical advantage that the deep borehole concept may offer over a repository concept is that of facilitating incremental construction and loading at multiple perhaps regional locations. The disposal borehole would be drilled to a depth of 5,000 m using a telescoping design and would be logged and tested prior to waste emplacement. Waste canisters would be constructed of carbon steel, sealed by welds, and connected into canister strings with high-strength connections. Waste canister strings of about 200 m length would be emplaced in the lower 2,000 m of the fully cased borehole and be separated by bridge and cement plugs. Sealing of the upper part of the borehole would be done with a series of compacted bentonite seals, cement plugs, cement seals, cement plus crushed rock backfill, and bridge plugs. Elements of the reference design meet technical requirements defined in the study. Testing and operational safety assurance requirements are also defined. Overall, the results of the reference design development and the cost analysis support the technical feasibility of the deep borehole disposal concept for high-level radioactive waste.

Herrick, Courtney Grant; Brady, Patrick Vane; Pye, Steven; Arnold, Bill Walter; Finger, John Travis; Bauer, Stephen J.

2011-10-01T23:59:59.000Z

396

Wave Propagation in Jointed Geologic Media  

SciTech Connect (OSTI)

Predictive modeling capabilities for wave propagation in a jointed geologic media remain a modern day scientific frontier. In part this is due to a lack of comprehensive understanding of the complex physical processes associated with the transient response of geologic material, and in part it is due to numerical challenges that prohibit accurate representation of the heterogeneities that influence the material response. Constitutive models whose properties are determined from laboratory experiments on intact samples have been shown to over-predict the free field environment in large scale field experiments. Current methodologies for deriving in situ properties from laboratory measured properties are based on empirical equations derived for static geomechanical applications involving loads of lower intensity and much longer durations than those encountered in applications of interest involving wave propagation. These methodologies are not validated for dynamic applications, and they do not account for anisotropic behavior stemming from direcitonal effects associated with the orientation of joint sets in realistic geologies. Recent advances in modeling capabilities coupled with modern high performance computing platforms enable physics-based simulations of jointed geologic media with unprecedented details, offering a prospect for significant advances in the state of the art. This report provides a brief overview of these modern computational approaches, discusses their advantages and limitations, and attempts to formulate an integrated framework leading to the development of predictive modeling capabilities for wave propagation in jointed and fractured geologic materials.

Antoun, T

2009-12-17T23:59:59.000Z

397

Remote geologic structural analysis of Yucca Flat  

SciTech Connect (OSTI)

The Remote Geologic Analysis (RGA) system was developed by Pacific Northwest Laboratory (PNL) to identify crustal structures that may affect seismic wave propagation from nuclear tests. Using automated methods, the RGA system identifies all valleys in a digital elevation model (DEM), fits three-dimensional vectors to valley bottoms, and catalogs all potential fracture or fault planes defined by coplanar pairs of valley vectors. The system generates a cluster hierarchy of planar features having greater-than-random density that may represent areas of anomalous topography manifesting structural control of erosional drainage development. Because RGA uses computer methods to identify zones of hypothesized control of topography, ground truth using a well-characterized test site was critical in our evaluation of RGA's characterization of inaccessible test sites for seismic verification studies. Therefore, we applied RGA to a study area centered on Yucca Flat at the Nevada Test Site (NTS) and compared our results with both mapped geology and geologic structures and with seismic yield-magnitude models. This is the final report of PNL's RGA development project for peer review within the US Department of Energy Office of Arms Control (OAC) seismic-verification community. In this report, we discuss the Yucca Flat study area, the analytical basis of the RGA system and its application to Yucca Flat, the results of the analysis, and the relation of the analytical results to known topography, geology, and geologic structures. 41 refs., 39 figs., 2 tabs.

Foley, M.G.; Heasler, P.G.; Hoover, K.A. (Pacific Northwest Lab., Richland, WA (United States)); Rynes, N.J. (Northern Illinois Univ., De Kalb, IL (United States)); Thiessen, R.L.; Alfaro, J.L. (Washington State Univ., Pullman, WA (United States))

1991-12-01T23:59:59.000Z

398

Remote geologic structural analysis of Yucca Flat  

SciTech Connect (OSTI)

The Remote Geologic Analysis (RGA) system was developed by Pacific Northwest Laboratory (PNL) to identify crustal structures that may affect seismic wave propagation from nuclear tests. Using automated methods, the RGA system identifies all valleys in a digital elevation model (DEM), fits three-dimensional vectors to valley bottoms, and catalogs all potential fracture or fault planes defined by coplanar pairs of valley vectors. The system generates a cluster hierarchy of planar features having greater-than-random density that may represent areas of anomalous topography manifesting structural control of erosional drainage development. Because RGA uses computer methods to identify zones of hypothesized control of topography, ground truth using a well-characterized test site was critical in our evaluation of RGA`s characterization of inaccessible test sites for seismic verification studies. Therefore, we applied RGA to a study area centered on Yucca Flat at the Nevada Test Site (NTS) and compared our results with both mapped geology and geologic structures and with seismic yield-magnitude models. This is the final report of PNL`s RGA development project for peer review within the US Department of Energy Office of Arms Control (OAC) seismic-verification community. In this report, we discuss the Yucca Flat study area, the analytical basis of the RGA system and its application to Yucca Flat, the results of the analysis, and the relation of the analytical results to known topography, geology, and geologic structures. 41 refs., 39 figs., 2 tabs.

Foley, M.G.; Heasler, P.G.; Hoover, K.A. [Pacific Northwest Lab., Richland, WA (United States); Rynes, N.J. [Northern Illinois Univ., De Kalb, IL (United States); Thiessen, R.L.; Alfaro, J.L. [Washington State Univ., Pullman, WA (United States)

1991-12-01T23:59:59.000Z

399

Deep reflection-mode photoacoustic imaging of  

E-Print Network [OSTI]

near-infrared laser pulses of 804-nm wavelength for PA excitation to achieve deep penetration-frequency PAM system. To achieve deep penetration of light, we chose the 804-nm near-infrared wavelengthDeep reflection-mode photoacoustic imaging of biological tissue Kwang Hyun Song and Lihong V. Wang

Wang, Lihong

400

Deep Web Entity Monitoring Mohammadreza Khelghati  

E-Print Network [OSTI]

Deep Web Entity Monitoring Mohammadreza Khelghati Database Group University of Twente, Netherlands. This data is defined as hidden web or deep web which is not accessible through search engines. It is estimated that deep web contains data in a scale several times bigger than the data accessible through

Hiemstra, Djoerd

Note: This page contains sample records for the topic "deep geologic repository" 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

Sampling the National Deep Web Denis Shestakov  

E-Print Network [OSTI]

Sampling the National Deep Web Denis Shestakov Department of Media Technology, Aalto University pages filled with information from myriads of online databases. This part of the Web, known as the deep a problem of deep Web characterization: how to estimate the total number of online databases on the Web? We

Hammerton, James

402

Ground-water hydraulics of the deep-basin brine aquifer, Palo Duro Basin, Texas panhandle  

SciTech Connect (OSTI)

The Deep-Basin Brine aquifer of the Palo Duro Basin (Texas Panhandle) underlies thick Permian bedded evaporites that are being evaluated as a potential high-level nuclear waste isolation repository. Potentiometric surface maps of 5 units of the Deep-Basin Brine aquifer were drawn using drill-stem test (DST) pressure data, which were analyzed by a geostatistical technique (kriging) to smooth the large variation in the data. The potentiometric surface maps indicate that the Deep-Basin Brine aquifer could be conceptually modeled as 5 aquifer units; a Lower Permian (Wolfcamp) aquifer, upper and lower Pennsylvanian aquifers, a pre-Pennsylvanian aquifer, and a Pennsylvanian to Wolfcampian granite-wash aquifer. The hydraulic head maps indicate that ground-water flow in each of the units is west to east with a minor northerly component near the Amarillo Uplift, the northern structural boundary of the basin. The Wolfcamp potentiometric surface indicates the strongest component of northerly flow. Inferred flow direction in Pennsylvanian aquifers is easterly, and in the pre-Pennsylvanian aquifer near its pinch-out in the basin center, flow is inferred to be to the north. In the granite-wash aquifer the inferred flow direction is east across the northern edge of the basin and southeast along the Amarillo Uplift.

Smith, D.A.

1985-01-01T23:59:59.000Z

403

North African geology: exploration matrix for potential major hydrocarbon discoveries  

SciTech Connect (OSTI)

Based on results and models presented previously, it is possible to consider an exploration matrix that examines the 5 basic exploration parameters: source, reservoir, timing, structure, and seal. This matrix indicates that even those basins that have had marginal exploration successes, including the Paleozoic megabasin and downfaulted Triassic grabens of Morocco, the Cyrenaican platform of Libya, and the Tunisia-Sicily shelf, have untested plays. The exploration matrix also suggests these high-risk areas could change significantly, if one of the 5 basic matrix parameters is upgraded or if adjustments in political or financial risk are made. The Sirte basin and the Gulf of Suez, 2 of the more intensely explored areas, also present attractive matrix prospects, particularly with deeper Nubian beds or with the very shallow Tertiary sections. The Ghadames basin of Libya and Tunisia shows some potential, but its evaluation responds strongly to stratigraphic and external nongeologic matrix variations based on degree of risk exposure to be assumed. Of greatest risk in the matrix are the very deep Moroccan Paleozoic clastic plays and the Jurassic of Sinai. However, recent discoveries may upgrade these untested frontier areas. Based on the matrix generated by the data presented at a North African Petroleum Geology symposium, significant hydrocarbon accumulations are yet to be found. The remaining questions are: where in the matrix does each individual company wish to place its exploration capital and how much should be the risk exposure.

Kanes, W.H.; O'Connor, T.E.

1985-02-01T23:59:59.000Z

404

Brine flow in heated geologic salt.  

SciTech Connect (OSTI)

This report is a summary of the physical processes, primary governing equations, solution approaches, and historic testing related to brine migration in geologic salt. Although most information presented in this report is not new, we synthesize a large amount of material scattered across dozens of laboratory reports, journal papers, conference proceedings, and textbooks. We present a mathematical description of the governing brine flow mechanisms in geologic salt. We outline the general coupled thermal, multi-phase hydrologic, and mechanical processes. We derive these processes' governing equations, which can be used to predict brine flow. These equations are valid under a wide variety of conditions applicable to radioactive waste disposal in rooms and boreholes excavated into geologic salt.

Kuhlman, Kristopher L.; Malama, Bwalya

2013-03-01T23:59:59.000Z

405

Proceedings of 3rd US/German Workshop on Salt Repository Research...  

Office of Environmental Management (EM)

New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop...

406

Design of a high-level waste repository system for the United States  

E-Print Network [OSTI]

This report presents a conceptual design for a High Level Waste disposal system for fuel discharged by U.S. commercial power reactors, using the Yucca Mountain repository site recently designated by federal legislation. ...

Driscoll, Michael J.

1988-01-01T23:59:59.000Z

407

Planned Emplacement of Magnesium Oxide in the WIPP Repository 1.0 Overview  

E-Print Network [OSTI]

Planned Emplacement of Magnesium Oxide in the WIPP Repository 1.0 Overview In December 2002 received approval to dispose of AMWTF's supercompacted waste provided magnesium oxide (MgO), the approved

408

Risk-informing decisions about high-level nuclear waste repositories  

E-Print Network [OSTI]

Performance assessments (PAs) are important sources of information for societal decisions in high-level radioactive waste (HLW) management, particularly in evaluating safety cases for proposed HLW repository development. ...

Ghosh, Suchandra Tina, 1973-

2004-01-01T23:59:59.000Z

409

Safety Assessment for VLLW Disposal at the National Radioactive Waste Repository Mochovce in Slovakia - 13508  

SciTech Connect (OSTI)

Recent developments in the Slovak Republic have prompted the need to introduce the new category of very low level waste (VLLW) in the operation of the country's repository for low and intermediate level radioactive waste (LILW). By doing this, significant savings are expected to be achieved while disposing the waste resulting from early decommissioning of older, Soviet type reactors. To study the feasibility and the likely impact of such introduction, a project was launched and assigned in international competition to a German-Spanish consortium. The study confirmed by means of a safety assessment the feasibility of this waste category in the specific context of the Slovakian repository. Moreover, the advantages that such new waste category would render were stressed and the best option for enlargement of the repository, the construction of a module for LILW disposal within the limits of the existing repository, was identified. (authors)

Biurrun, E.; Haverkamp, B. [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Lazaro, A.; Miralles, A. [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain)] [Westinghouse Electric Spain SAR, Padilla 17, E-28006 Madrid (Spain)

2013-07-01T23:59:59.000Z

410

The Adoption of Advanced Fuel Cycle Technology Under a Single Repository Policy  

SciTech Connect (OSTI)

Develops the tools to investiage the hypothesis that the savings in repository space associated with the implementation of advanced nuclear fuel cycles can result in sufficient cost savings to offset the higher costs of those fuel cycles.

Paul Wilson

2009-11-02T23:59:59.000Z

411

Active Cores in Deep Fields  

E-Print Network [OSTI]

Deep field observations are an essential tool to probe the cosmological evolution of galaxies. In this context, X-ray deep fields provide information about some of the most energetic cosmological objects: active galactic nuclei (AGN). Astronomers are interested in detecting sufficient numbers of AGN to probe the accretion history at high redshift. This talk gives an overview of the knowledge resulting from a highly complete soft X-ray selected sample collected with ROSAT, XMM-Newton and Chandra deep fields. The principal outcome based on X-ray luminosity functions and space density evolution studies is that low-luminosity AGN evolve in a dramatically different way from high-luminosity AGN: The most luminous quasars perform at significantly earlier cosmic times and are most numerous in a unit volume at cosmological redshift z~2. In contrast, low-luminosity AGN evolve later and their space density peaks at z~0.7. This finding is also interpreted as an anti-hierarchical growth of supermassive black holes in the Universe. Comparing this with star formation rate history studies one concludes that supermassive black holes enter the cosmic stage before the bulk of the first stars. Therefore, first solutions of the so-called hen-egg problem are suggested. Finally, status developments and expectations of ongoing and future extended observations such as the XMM-COSMOS project are highlighted.

G. Hasinger; A. Mueller

2005-10-14T23:59:59.000Z

412

Method of fracturing a geological formation  

DOE Patents [OSTI]

An improved method of fracturing a geological formation surrounding a well bore is disclosed. A relatively small explosive charge is emplaced in a well bore and the bore is subsequently hydraulically pressurized to a pressure less than the formation breakdown pressure and preferably greater than the fracture propagation pressure of the formation. The charge is denoted while the bore is so pressurized, resulting in the formation of multiple fractures in the surrounding formation with little or no accompanying formation damage. Subsequent hydraulic pressurization can be used to propagate and extend the fractures in a conventional manner. The method is useful for stimulating production of oil, gas and possibly water from suitable geologic formations.

Johnson, James O. (2679-B Walnut, Los Alamos, NM 87544)

1990-01-01T23:59:59.000Z

413

ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT  

SciTech Connect (OSTI)

The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

2012-04-25T23:59:59.000Z

414

Kinetics of the Dissolution of Scheelite in Groundwater: Implications for Environmental and Economic Geology  

E-Print Network [OSTI]

Tungsten, Its History, Geology, Ore-dressing, Metallurgy,5.1 Implications for Environmental Geology…………………………..26 5.2Implications for Economic Geology………………………………..27 6. Future

Montgomery, Stephanie Danielle

2012-01-01T23:59:59.000Z

415

Case studies of the application of the Certification Framework to two geologic carbon sequestration sites  

E-Print Network [OSTI]

from geologic carbon sequestration sites: unsaturated zoneverification of geologic carbon sequestration, Geophys. Res.to two geologic carbon sequestration sites Curtis M.

Oldenburg, Curtis M.

2009-01-01T23:59:59.000Z

416

Geologic carbon sequestration as a global strategy to mitigate CO2 emissions: Sustainability and environmental risk  

E-Print Network [OSTI]

from geologic carbon sequestration sites: unsaturated zone2 from geologic carbon sequestration sites: CO 2 migrationGeologic Carbon Sequestration as a Global Strategy to

Oldenburg, C.M.

2012-01-01T23:59:59.000Z

417

Model Components of the Certification Framework for Geologic Carbon Sequestration Risk Assessment  

E-Print Network [OSTI]

to two geologic carbon sequestration sites, Energy Procedia,for Geologic Carbon Sequestration Based on Effectivefor geologic carbon sequestration risk assessment, Energy

Oldenburg, Curtis M.

2009-01-01T23:59:59.000Z

418

Repository site data report for unsaturated tuff, Yucca Mountain, Nevada  

SciTech Connect (OSTI)

The US Department of Energy is currently considering the thick sequences of unsaturated, fractured tuff at Yucca Mountain, on the southwestern boundary of the Nevada Test Site, as a possible candidate host rock for a nuclear-waste repository. Yucca Mountain is in one of the most arid areas in the United States. The site is within the south-central part of the Great Basin section of the Basin and Range physiographic province and is located near a number of silicic calderas of Tertiary age. Although localized zones of seismic activity are common throughout the province, and faults are present at Yucca Mountain, the site itself is basically aseismic. No data are available on the composition of ground water in the unsaturated zone at Yucca Mountain. It has been suggested that the composition is bounded by the compositions of water from wells USW-H3, UE25p-1, J-13, and snow or rain. There are relatively few data available from Yucca Mountain on the moisture content and saturation, hydraulic conductivity, and characteristic curves of the unsaturated zone. The available literature on thermomechanical properties of tuff does not always distinguish between data from the saturated zone and data from the unsaturated zone. Geochemical, hydrologic, and thermomechanical data available on the unsaturated tuffs of Yucca Mountain are tabulated in this report. Where the data are very sparse, they have been supplemented by data from the saturated zone or from areas other than Yucca Mountain. 316 refs., 58 figs., 37 tabs.

Tien, P.L.; Updegraff, C.D.; Siegel, M.D.; Wahi, K.K.; Guzowski, R.V.

1985-11-01T23:59:59.000Z

419

Water, Vapor, and Salt Dynamics in a Hot Repository  

SciTech Connect (OSTI)

The purpose of this paper is to report the results of a new model study examining the high temperature nuclear waste disposal concept at Yucca Mountain using MULTIFLUX, an integrated in-drift- and mountain-scale thermal-hydrologic model. The results show that a large amount of vapor flow into the drift is expected during the period of above-boiling temperatures. This phenomenon makes the emplacement drift a water/moisture attractor during the above-boiling temperature operation. The evaporation of the percolation water into the drift gives rise to salt accumulation in the rock wall, especially in the crown of the drift for about 1500 years in the example. The deposited salts over the drift footprint, almost entirely present in the fractures, may enter the drift either by rock fall or by water drippage. During the high temperature operation mode, the barometric pressure variation creates fluctuating relative humidity in the emplacement drift with a time period of approximately 10 days. Potentially wet and dry conditions and condensation on salt-laden drift wall sections may adversely affect the storage environment. Salt accumulations during the above-boiling temperature operation must be sufficiently addressed to fully understand the waste package environment during the thermal period. Until the questions are resolved, a below-boiling repository design is favored where the Alloy-22 will be less susceptible to localized corrosion. (authors)

Bahrami, Davood; Danko, George [Department of Mining Engineering, University of Nevada, Reno, 1664 N. Virginia St., Reno, NV, 89557 (United States); Walton, John [Department of Civil Engineering, University of Texas at El Paso, 500 W. University, El Paso, TX, 79968 (United States)

2007-07-01T23:59:59.000Z

420

Mechanical interaction between rock, buffer and canister in repositories  

SciTech Connect (OSTI)

The bentonite clay buffer, which is used in the repository concept of Sweden as well as many other countries, has an important role for mechanical protection of the canister. Of special interest is the effect of a rock shear, i.e. displacement of the rock along a fracture intersecting the deposition hole, on the canister. The article shows the results of some FEM calculations of a rock shear when the new composite copper/steel canister, is used. The effect of the swelling pressure from the bentonite before shear and the effect of a symmetric as well as an asymmetric rock shear will be shown. The calculations have been preceded by extensive laboratory tests and verification calculations by which material models for the buffer and proper calculation techniques have been developed. The material model for the clay is an elastic plastic model in which porous elasticity, based on the effective stress theory, is combined with Drucker-Prager plasticity. The results indicate that the bentonite clay acts as a very good mechanical buffer against such rock displacements. Although plastic yielding may occur, mainly in the copper, the plastic strain is not more than a few percent just after the shear.

Borgesson, L. [Clay Technology AB, Lund (Sweden)

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "deep geologic repository" 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

Department of Geological Sciences Undergraduate Handbook 2014  

E-Print Network [OSTI]

about future sea-level rise, and are there untapped energy and mineral resources both onshore and offshore New Zealand; are also increasingly important concerns both at the regional and global scales. Come-exploration, volcanology, hazard management, engineering geology, environmental planning, water resources, science teaching

Hickman, Mark

422

Department of Geological Sciences Postgraduate Handbook 2013  

E-Print Network [OSTI]

about future sea-level rise, and are there untapped energy and mineral resources both onshore and offshore New Zealand; are also increasingly important concerns both at the regional and global scales. Come-exploration, volcanology, hazard management, engineering geology, environmental planning, water resources, science teaching

Hickman, Mark

423

Geologic characterization of tight gas reservoirs  

SciTech Connect (OSTI)

The objectives of US Geological Survey (USGS) work during FY 89 were to conduct geologic research characterizing tight gas-bearing sandstone reservoirs and their resources in the western United States. Our research has been regional in scope but, in some basins, our investigations have focused on single wells or small areas containing several wells where a large amount of data is available. The investigations, include structure, stratigraphy, petrography, x-ray mineralogy, source-rock evaluation, formation pressure and temperature, borehole geophysics, thermal maturity mapping, fission-track age dating, fluid-inclusion thermometry, and isotopic geochemistry. The objectives of these investigations are to provide geologic models that can be compared and utilized in tight gas-bearing sequences elsewhere. Nearly all of our work during FY 89 was devoted to developing a computer-based system for the Uinta basin and collecting, analyzing, and storage of data. The data base, when completed will contain various types of stratigraphic, organic chemistry, petrographic, production, engineering, and other information that relate to the petroleum geology of the Uinta basin, and in particular, to the tight gas-bearing strata. 16 refs., 3 figs.

Law, B.E.

1990-12-01T23:59:59.000Z

424

145Department of Geology Graduate Catalogue 201314  

E-Print Network [OSTI]

in the exploration for petroleum and other resources. GEOL 305 Geophysics II 3.0; 3 cr. A course on electrical and their methods of interpretation. Pre- or corequisites: GEOL 221 and GEOL 222. GEOL 306 Economic Minerals Geology of their formation; ore forming processes and ore deposit models; advanced techniques to evaluate ore genesis

Shihadeh, Alan

425

APPLIED GEOPHYSICS FIELD CLASS GEOLOGY 437  

E-Print Network [OSTI]

APPLIED GEOPHYSICS FIELD CLASS GEOLOGY 437 SPRING 2014 OF NATURAL RESOURCES INCLUDING OIL, COAL, MINERALS AND GROUNDWATER. OTHER APPLICATIONS OF GEOPHYSICS MAY, IF AVAILABLE, WE WILL VISIT AN OIL DRILLING RIG IN OPERATION. DATES FOR FIELD TRIPS WILL DEPEND ON THE WEATHER

Nickrent, Daniel L.

426

INTEGRATING GEOLOGIC AND GEOPHYSICAL DATA THROUGH  

E-Print Network [OSTI]

INTEGRATING GEOLOGIC AND GEOPHYSICAL DATA THROUGH ADVANCED CONSTRAINED INVERSIONS by Peter George framework (i.e. minimization of an objective function). I developed several methods to reach this goal constraints to the inverse problem. Lastly, I developed an iterative procedure for cooperatively inverting

Oldenburg, Douglas W.

427

Internal Geology and Evolution of the Redondo Dome, Valles Caldera...  

Open Energy Info (EERE)

Geology and Evolution of the Redondo Dome, Valles Caldera, New Mexico Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Internal Geology and...

428

System-level modeling for geological storage of CO2  

E-Print Network [OSTI]

of Geologic Storage of CO2, in Carbon Dioxide Capture forFormations - Results from the CO2 Capture Project: GeologicBenson, Process Modeling of CO2 Injection into Natural Gas

Zhang, Yingqi; Oldenburg, Curtis M.; Finsterle, Stefan; Bodvarsson, Gudmundur S.

2006-01-01T23:59:59.000Z

429

Paleontology and Geology of Indiana Department of Geological Sciences | P. David Polly 1  

E-Print Network [OSTI]

. Iowa Tracheophyta (vascular plants) Spores, New Albany Shale Sporing bodies, Dugger Fm. #12;Department (conifers) Walchia, Abo Fm. New Mexico (Permian) #12;Department of Geological Sciences | P. David Polly 5

Polly, David

430

Deep Reactive Ion Etching | EMSL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINL isSeparationsRelevantDeep Reactive Ion

431

Deep forest rebounds from H...  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to UserProduct: CrudeOffice ofINL isSeparationsRelevantDeepSUBSCRIBE:

432

GEOLOGY O F THE NORTHERN PCIRT O F DRY MOUNTAXN,  

E-Print Network [OSTI]

GEOLOGY O F THE NORTHERN PCIRT O F DRY MOUNTAXN, SOUTHERN UASCSTCH H Q - W T A X H E i i - UT&H #12;BRIGHAM YOUNG UNIVERSITY RESEARCH STUDIES Geology Seri,es Vol. 3 No. 2 April, 1956 GEOLOGY OF THE NORTHERN Department of Gedogy Provo, Utah #12;GEOLOGY OF THE NORTHERN PART OF DRY MOUNTAIN, SOUTHERN WASATCH M O U N

Seamons, Kent E.

433

What can I do with a degree in Geology?  

E-Print Network [OSTI]

What can I do with a degree in Geology? Science Planning your career Choosing a career involves.canterbury.ac.nz/liaison/best_prep.shtml What is Geology? Geology in the twenty-first century is a fascinating, exciting,incredibly diverse,earthquakes,dramatic and varied geomorphology,and its 500 million years of pre and post-Gondwana geological history,is one

Hickman, Mark

434

FRAMEWORK GEOLOGY OF FORT UNION COAL IN THE WILLISTON BASIN  

E-Print Network [OSTI]

Chapter WF FRAMEWORK GEOLOGY OF FORT UNION COAL IN THE WILLISTON BASIN By R.M. Flores,1 C.W. Keighin,1 A.M. Ochs,2 P.D. Warwick,1 L.R. Bader,1 and E.C. Murphy3 in U.S. Geological Survey Professional Paper 1625-A 1 U.S. Geological Survey 2 Consultant, U.S. Geological Survey, Denver, Colorado 3 North

435

Panel Organization 1. Panel on Structural Geology & Geoengineering  

E-Print Network [OSTI]

in Geological Engineering CEE 330 & GLE 474 or instructor consent 3 0.0 CEE 631 Toxicants in the Environment

436

area geological characterization: Topics by E-print Network  

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

and Utilization Websites Summary: Geological Characterization of California's Offshore Carbon Dioxide Storage Capacity ENVIRONMENTAL sequestration pilot studies to determine...

437

Summary Report on CO2 Geologic Sequestration & Water Resources Workshop  

E-Print Network [OSTI]

geochemistry in carbon sequestration environments. Abstractimplications for carbon sequestration. Environ Earth Sci. ,from geologic carbon sequestration: Static and dynamic

Varadharajan, C.

2013-01-01T23:59:59.000Z

438

Assessment of Brine Management for Geologic Carbon Sequestration  

E-Print Network [OSTI]

for  Geologic  Carbon  Sequestration. ”   International  of  Energy.  “Carbon  Sequestration  Atlas  of  the  Water  Extracted  from  Carbon  Sequestration  Projects."  

Breunig, Hanna M.

2014-01-01T23:59:59.000Z

439

Map of Geologic Sequestration Training and Research Projects  

Broader source: Energy.gov [DOE]

A larger map of FE's Geologic Sequestration Training and Research Projects awarded as part of the Recovery Act.

440

Panel Organization 1. Panel on Structural Geology & Geoengineering  

E-Print Network [OSTI]

to ductivities. Geologic logs sometimes show thin layers limit further spreading of contaminants. This flow model accounts for of potentially high hydraulic conductivity embedded complex geologic units that vary measured different methods can be employed to represent thein a geologic unit. A composite model was used

Note: This page contains sample records for the topic "deep geologic repository" 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

BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 27, Part 3  

E-Print Network [OSTI]

#12;BRIGHAM YOUNG UNIVERSITY GEOLOGY STUDIES Volume 27, Part 3 CONTENTS Studies for Students #lo, Geologic Guide to Provo Canyon and Weber Canyon, Central Wasatch Mountains, Utah ............................................................................................................................. Randy L. Chamberlain The Geology of the Drum Mountains, Millard and Juab Counties, Utah

Seamons, Kent E.

442

Brigham Young University Geology Studies Volume 26, Part I  

E-Print Network [OSTI]

#12;Brigham Young University Geology Studies Volume 26, Part I Papers presented at the 31st annual meeting, Rocky Mountain Section, Geological Society of America, April 28-29, 1978, at Brig- ham Young ............................................................................................................................Publications and Maps of the Geology Department 91 Cover The Great Basrn seen from a htgh

Seamons, Kent E.

443

Brigham Young University Geology Studies Volume 27, Part 2  

E-Print Network [OSTI]

#12;Brigham Young University Geology Studies Volume 27, Part 2 CONTENTS The Kinnikinic Quartzite ........................................................Robert Q. Oaks,Jr., and W . Calvin James Geology of the Sage Valley 7 W'Quadrangle, Caribou County, Idaho, and Lincoln County, Wyoming ....................J ohn L. Conner Geology of the Elk Valley Quadrangle, Bear

Seamons, Kent E.

444

Semantic e-Science and Geology Clinton Smyth1  

E-Print Network [OSTI]

Semantic e-Science and Geology Clinton Smyth1 , David Poole2 and Rita Sharma3 1 Georeference Online@cs.ubc.ca Abstract e-Science, as implemented for the study of geology with Geographic Information Systems over the Internet, has highlighted the need for standardization in the semantics of geology, and stimulated

Poole, David

445

CHAPTER II GEOLOGY Blank page retained for pagination  

E-Print Network [OSTI]

CHAPTER II GEOLOGY #12;Blank page retained for pagination #12;SHORELINES AND COASTS OF THE GULF or discordant with the grain (dominant trend) of the geologic structures of a coastal regi?n, but King (1942, pIOnal geology, geomorphology, sedimentation, oceanography of the inshore zone, meteorology, climatology, biol

446

SEPM (Society for Sedementary Geology) Twenhofel medal awarded to USGS  

E-Print Network [OSTI]

SEPM (Society for Sedementary Geology) Twenhofel medal awarded to USGS Scientist Emeritus Walter the highest award given by the Society for Sedimentary Geology (SEPM) -- the Twenhofel medal. Walt joins an illustrious list of past Twenhofel recipients, which reads as a veritable "Who's Who"