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Hydrogen-Induced Cracking of the Drip Shield
Hydrogen-Induced Cracking of the Drip Shield
Hydrogen-induced cracking is characterized by the decreased ductility and fracture toughness of a material due to the absorption of atomic hydrogen in the metal crystal lattice. Corrosion is the source of hydrogen generation. For the current design of the engineered barrier without backfill, hydrogen-induced cracking may be a concern because the titanium drip shield can be galvanically coupled to rock bolts (or wire mesh), which may fall onto the drip shield, thereby creating conditions for hydrogen production by electrochemical reaction.
Analysis of Dust Deliquescence for FEP Screening
Analysis of Dust Deliquescence for FEP Screening
The purpose of this report is to evaluate the potential for penetration of the Alloy 22 (UNS N06022) waste package outer barrier by localized corrosion due to the deliquescence of soluble constituents in dust present on waste package surfaces. The results support a recommendation to exclude deliquescence-induced localized corrosion (pitting or crevice corrosion) of the outer barrier from the total system performance assessment for the license application (TSPA-LA).
CSNF Loading Curve Sensitivity Analysis
CSNF Loading Curve Sensitivity Analysis
The purpose of this scientific analysis report, CSNF Loading Curve Sensitivity Analysis, is to establish the required minimum burnup as a function of initial enrichment for both pressurized water reactor (PWR) and boiling water reactor (BWR) commercial spent nuclear fuel (CSNF) that would allow permanent disposal of these waste forms in the geologic repository at Yucca Mountain. The relationship between the required minimum burnup and fuel assembly initial enrichment forms a loading curve.
DOE SNF Phase I and II Summary Report
DOE SNF Phase I and II Summary Report
There are more than 250 forms of U.S. Department of Energy (DOE)owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program (NSNFP) has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. For each fuel group, a fuel type that represents the characteristics of all fuels in that group has been selected for detailed analysis.
Evaluation of Codisposal Viability for MOX (FFTF) DOE-Owned Fuel
Evaluation of Codisposal Viability for MOX (FFTF) DOE-Owned Fuel
There are more than 250 forms of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program (NSNFP) has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. Fast Flux Test Facility (FFTF) fuel has been designated as the representative fuel for the mixed-oxide (MOX) fuel group which is a mixture of uranium and plutonium oxides.
Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.
Overview of the Section 180(c) Program: History, Lessons Learned, and Potential Next Steps
Overview of the Section 180(c) Program: History, Lessons Learned, and Potential Next Steps
The U.S. Department of Energy’s (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible, under the Nuclear Waste Policy Act of 1982, for the transportation of spent nuclear fuel and high-level radioactive waste from point of origin to destination at a federal storage or disposal facility. Section 180(c), written into the Nuclear Waste Policy Act Amendments of 1987, requires OCRWM to prepare public safety officials along the routes for these shipments.
ANS Position Statement: Licensing of Yucca Mountain as a Geological Repository for Radioactive Wastes
ANS Position Statement: Licensing of Yucca Mountain as a Geological Repository for Radioactive Wastes
The American Nuclear Society (ANS) supports (1) the development and use of geological
repositories for disposal of high-level radioactive wastes and (2) expeditious processing of the
Yucca Mountain license application in an open, technically sound manner. Geological disposal
means placing the wastes hundreds of feet underground and far from the biosphere. The U.S.
Nuclear Regulatory Commission (NRC) is following a legislatively well-defined regulatory
process to evaluate the safety of the proposed Yucca Mountain Site to meet both the scientific
Public Beliefs, Concerns and Preferences Regarding the Management of Used Nuclear Fuel and High Level Radioactive Waste
Public Beliefs, Concerns and Preferences Regarding the Management of Used Nuclear Fuel and High Level Radioactive Waste
US policy for management of used nuclear fuel (UNF) and high level radioactive wastes (HLRW) is at a crossroads, and the success of new policy directions will depend in part on broad public acceptance and support. In this paper I provide an overview of the evidence concerning the beliefs and concerns of members of the American public regarding UNF and HLNW. I also characterize the evidence on American’s policy preferences for management of these materials.
Drift-Scale THC Seepage Model
Drift-Scale THC Seepage Model
The purpose of this report is to document the thermal-hydrologic-chemical (THC) seepage model and model simulations. The simulations predict the composition of fracture water that could potentially seep into repository emplacement drifts and the composition of the associated gas phase. The THC seepage model is not used to feed the total system performance assessment (TSPA) for the license application (LA).
THC Sensitivity Study of Heterogeneous Permeability and Capillarity Effects
THC Sensitivity Study of Heterogeneous Permeability and Capillarity Effects
The purpose of this report is to <,locument the sensitivity of the drift-scale thermal-hydrologic- chemical (THC) seepage model (SNL 2007 [DIRS 177404]) to heterogeneities in permeability and capillarity, which could affect predicted fluxes and chemistries of water and gases seeping into the emplacement drifts. This report has been developed following Technical Work Plan for: Revision of Model Reports for Near-Field and In-Drift Water Chemistry (SNL 2007 [DIRS 179287]).
Summary Report of Commercial Reactor Criticality Data for Crystal River Unit 3
Summary Report of Commercial Reactor Criticality Data for Crystal River Unit 3
The "Summary Report of Commercial Reactor Criticality Data for Crystal River Unit 3" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Crystal River Unit 3 (CR3) reactor.
Disposal of High-Level Radioactive Wastes in a Proposed Geologic Repository at Yucca Mountain, Nevada; Final Rule
Disposal of High-Level Radioactive Wastes in a Proposed Geologic Repository at Yucca Mountain, Nevada; Final Rule
The Nuclear Regulatory Commission (NRC) is publishing licensing criteria for disposal of spent nuclear fuel and high-level radioactive wastes in the proposed geologic repository at Yucca Mountain, Nevada. As mandated by law, this final rule changes the Commissions technical requirements and criteria, as necessary, to be consistent with final environmental standards for Yucca Mountain issued by the U.S. Environmental Protection Agency (EPA).
Funding Issues
Funding Issues
The purpose of this paper is to allow CoRWM to consider the range of issues concerning funding of a geological disposal facility (GDF) and of safe and secure interim storage, to note current developments and to identify issues that require further consideration or where CORWM should develop advice to Government.
Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel
Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel
This report was prepared for the Secretary of Energy by a team of federal and contractor
personnel led by the Department’s Office of Nuclear Energy. The report assesses the technical
options for the permanent disposal of high-level radioactive waste (HLW) and spent nuclear fuel
(SNF) managed by the Department of Energy. Specifically, it considers whether DOE-managed HLW and
SNF should be disposed of with commercial SNF and HLW in one geologic repository or whether there
On Petitions for Review of Orders of the EPA, the DOE, and the NRC
On Petitions for Review of Orders of the EPA, the DOE, and the NRC
In sum, we vacate 40 C.F.R. part 197 to the extent that it incorporates a 10,000-year compliance period because, contrary to EnPA section 801(a), that compliance period is not<br> "based upon and consistent with " the recommendations of the National Academy of Sciences. The remaining challenges to the EPA rule are without merit. We vacate the NRC rule insofar as it incorporates EPAÕs 10,000-year compliance period. In all other respects, we deny NevadaÕs petition for review challenging the NRC rule.
Analysis of the MUA Decision Methodology for HLW Repository Siting: Preclosure Utilities
Analysis of the MUA Decision Methodology for HLW Repository Siting: Preclosure Utilities
Utilities and ranking of the preclosure attributes of the proposed high-level radioactive waste repository are examined, in order to provide insights into the propriety of using this approach for this type of decision and an assessment of the adequacy of the analysis itself. The postclosure utilities obtained in the previous study were greater than 80% for all five sites considered, but showed a greater spread than those in the MUA. The preclosure multiattribute utilities also show a wider spread than in the MUA.
Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants
Application of Spatial Data Modeling Systems, Geographical Information Systems (GIS), and Transportation Routing Optimization Methods for Evaluating Integrated Deployment of Interim Spent Fuel Storage Installations and Advanced Nuclear Plants
The objective of this siting study work is to support DOE in evaluating integrated advanced nuclear plant and ISFSI deployment options in the future. This study looks at several nuclear power plant growth scenarios that consider the locations of existing and planned commercial nuclear power plants integrated with the establishment of consolidated interim spent fuel storage installations (ISFSIs).
Response to Comments from the U.S. Department of Interior, State of Nevada, and Affected Counties on the Report of Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
Response to Comments from the U.S. Department of Interior, State of Nevada, and Affected Counties on the Report of Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
Comments contained in this document were received by the U.S. Department of Energy (DOE) on the Report of Early Site Suitability Evaluation (ESSE) of the Potential Repository Site at Yucca Mountain, Nevada, (Younker et al., 1992, SAIC 91/8000). Comments were received from the U.S. Department of Interior, the U.S. Nuclear Regulatory Commission, the State of Nevada, and several local affected governments in Nevada. No comments were received from members of the public.
Disposal Concepts/Thermal Load Management (FY11/12 Summary Report)
Disposal Concepts/Thermal Load Management (FY11/12 Summary Report)
This report is part of study to identify reference geologic disposal concepts for generic studies in the Used Fuel Disposition R&D Campaign. This report summarizes the work on both enclosed and open modes, which has been expanded to include thermal analysis of open modes, a range of spent nuclear fuel (SNF) burnup, additional disposal system description, and cost estimation.
A MOUNTAIN OF TROUBLE: A NATION AT RISK REPORT ON IMPACTS OF THE PROPOSED YUCCA MOUNTAIN HIGH-LEVEL NUCLEAR WASTE PROGRAM
A MOUNTAIN OF TROUBLE: A NATION AT RISK REPORT ON IMPACTS OF THE PROPOSED YUCCA MOUNTAIN HIGH-LEVEL NUCLEAR WASTE PROGRAM
Enclosed is the State of Nevada s report on impacts of the proposed Yucca Mountain nuclear waste repository program. This report is being provided pursuant to Section 114(a)(1)(H) and Section 116 of the Nuclear Waste Policy Act of 1982, as amended.
House of Representatives Letter to Secretary of Energy regarding split of defense and commercial nuclear waste disposal
House of Representatives Letter to Secretary of Energy regarding split of defense and commercial nuclear waste disposal
House of Representatives Letter to Secretary of Energy regarding split of defense and commercial nuclear waste disposal.
Response to Comments from the U.S. Nuclear Regulatory Commission on the Report of Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
Response to Comments from the U.S. Nuclear Regulatory Commission on the Report of Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
Comments contained in this document were received by the U.S. Department of Energy (DOE) on the Report of Early Site Suitability Evaluation (ESSE) of the Potential Repository Site at Yucca Mountain, Nevada, (Younker et al., 1992, SAIC 91/8000). Comments were received from the U.S. Department of Interior, the U.S. Nuclear Regulatory Commission, the State of Nevada, and several local affected governments in Nevada. No comments were received from members of the public.
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.