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PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.
Disposal Subcommittee Report to the Full Commission
Disposal Subcommittee Report to the Full Commission
The Disposal Subcommittee of the Blue Ribbon Commission on America’s Nuclear Future (BRC) addressed a wide-ranging set of issues, all bearing directly on the central question: “How can the United States go about establishing one or more disposal sites for high-level nuclear wastes in a manner and within a timeframe that is technically, socially, economically, and politically acceptable?”
Reactor and Fuel Cycle Technology Subcommittee Report to the Full Commission Updated Report
Reactor and Fuel Cycle Technology Subcommittee Report to the Full Commission Updated Report
The Reactor and Fuel Cycle Technology Subcommittee was formed to respond to the charge—set forth in the charter of the BRC—to evaluate existing fuel cycle technologies and R&D programs in terms of multiple criteria.
Westinghouse 17x17 MOX PWR Assembly- Waste Package Criticality Analysis (SCPB: N/A)
Westinghouse 17x17 MOX PWR Assembly- Waste Package Criticality Analysis (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to compare the criticality potential of Westinghouse 17x17 mixed oxide (MOX) PWR fuel with the Design Basis spent nuclear fuel (SNF) analyzed previously (Ref. 5.1, 5.2). The basis of comparison will be the conceptual design Multi- Purpose Canister (MPC) PWR waste package concepts.
Summary Report of Commercial Reactor Criticality Data for McGuire Unit 1
Summary Report of Commercial Reactor Criticality Data for McGuire Unit 1
The "Summary Report of Commercial Reactor Criticality Data for McGuire Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the McGuire Unit 1 reactor.
Summary Report of Laboratory Critical Experiment Analyses Performed for the Disposal Criticality Analysis Methodology
Summary Report of Laboratory Critical Experiment Analyses Performed for the Disposal Criticality Analysis Methodology
This report, Summary Report of Laboratory Critical Experiment Analyses Performed for the Disposal Criticality Analysis Methodology, contains a summary of the laboratory critical experiment (LCE) analyses used to support the validation of the disposal criticality analysis methodology.
Bias and Range of Applicability Determinations for Commercial Nuclear Fuels
Bias and Range of Applicability Determinations for Commercial Nuclear Fuels
The purpose of this calculation is to apply the process described in the Preclosure Criticality Analysis Process Report (Ref. 2.2.12) to establish the bias for keff calculations performed for commercial nuclear fuels using the MCNP code system. This bias will be used in criticality safety analyses as part of the basis for establishing the upper subcritical limit (USL). This calculation also defines the range of applicability (ROA) for which the bias may be used directly without need to consider additional penalties on the USL.
Commercial Reactor Reactivity Analysis for Grand Gulf, Unit 1
Commercial Reactor Reactivity Analysis for Grand Gulf, Unit 1
The objective of this calculation is to document the Grand Gulf Unit 1 (GGl) reactivity calculations for sixteen critical statepoints in· cycles 4 through 8. The GG1 reactor is a boiling water reactor (BWR) owned and operated by Entergy Operations Inc. The Commercial Reactor Criticality (CRC) evaluations support the development and validation of the neutronic models used for criticality analyses involving commercial spent nuclear fuel to be placed in a geologic repository. This calculation is performed as part of the evaluation in the CRC program.
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II
The objective of this analysis is to characterize the criticality safety aspects of a degraded Department of Energy spent nuclear fuel (DOESNF) canister containing Masachusetts Institute of Technology (MIT) or Oak Ridge Research (ORR) fuel in the Five Pack defense high level waste (DHLW) waste package to demonstrate concept viability related to use in the Minded Geologic Disposal System (MGDS) environment for the postclosure time frame.
Nuclear Criticality Calculations for the Wet Handling Facility
Nuclear Criticality Calculations for the Wet Handling Facility
The purpose of this calculation is to apply the process described in the TDR-DS0-NU-000001 Rev. 02, Preclosure Criticality Analysis Process Report (Ref. 2.2.25) to aid in establishing design and operational criteria important to criticality safety and to identify potential control parameters and their limits important to the criticality safety of commercial spent nuclear fuel (CSNF) handling operations in the Wet Handling Facility (WHF)
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
Waste Packages and Source Terms for the Commercial 1999 Design Basis Waste Streams
This calculation is prepared by the Monitored Geologic Repository Waste Package Requirements & Integration Department. The purpose of this calculation is to compile source term and commercial waste stream information for use in the analysis of waste package (WP) designs for commercial fuel. Information presented will consist of the number of WPs, source terms, metric tons of uranium, and the average characteristics of assemblies to be placed in each WP design. The source terms provide thermal output, radiation sources, and radionuclide inventories.
MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA
MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA
This analysis provides information necessary for total system performance assessment (TSPA) for the license application (LA) to include the excess U.S. Department of Energy (DOE) plutonium in the form of mixed oxide (MOX) spent nuclear fuel and lanthanide borosilicate (LaBS) glass. This information includes the additional radionuclide inventory due to MOX spent nuclear fuel and LaBS glass and the analysis that shows that the TSPA models for commercial spent nuclear fuel (CSNF) and high-level waste (HLW) degradation are appropriate for MOX spent nuclear fuel and LaBS glass, respectively.
Innovative Stakeholder Involvement Processes in Department of Energy Programs - A Selective Accounting
Innovative Stakeholder Involvement Processes in Department of Energy Programs - A Selective Accounting
The Blue Ribbon Commission staff requested this paper cataloging innovative stakeholder involvement programs within the Department of Energy (DOE). I reviewed a variety of material on public involvement, including papers and presentations on stakeholder involvement in DOE programs, published presentations and comments to the BRC, and research reports on stakeholder and public involvement.
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
Criticality Safety and Shielding Evaluations of the Codisposal Canister in the Five-Pack DHLW Waste Package
The objective of this analysis is to characterize a codisposal canister containing MIT or ORR fuel in the Five-Pack defense high level waste (DHLW) waste package (WP) to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame. The purpose of this analysis is to investigate the disposal criticality and shielding issues for the DHLW WP and establish DHLW WP and codisposal canister compatibility with the MGDS, and to provide criticality and shielding evaluations for the preliminary DHLW WP design.
Managing Commercial High-Level Radioactive Waste
Managing Commercial High-Level Radioactive Waste
After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue.
Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, Rev. 0
Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, Rev. 0
The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system as developed under the Nuclear Waste Policy Act of 1982. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document.
Development of Technical Data Needed to Justify Full Burnup Credit in Criticality Safety Licensing Analyses Involving Commercial Spent Nuclear Fuel
Development of Technical Data Needed to Justify Full Burnup Credit in Criticality Safety Licensing Analyses Involving Commercial Spent Nuclear Fuel
This technical work plan (TWP) describes the planning of burnup credit (BUC) experimental work to be implemented by the U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Lead Laboratory for Repository Systems. This TWP serves to coordinate and integrate a program to implement Work Packages S31023 to S31036 of the fiscal year 2007 annual work plan (AWP) for the Lead Laboratory.
Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2
Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2
The "Summary Report of Commercial Reactor Criticality Data for Sequoyah Unit 2" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Sequoyah Unit 2 reactor.
Safety and Security of Commercial Spent Nuclear Fuel Storage: Public Report - Summary
Safety and Security of Commercial Spent Nuclear Fuel Storage: Public Report - Summary
At the request of the U.S. Congress, the National Academies assessed the safety and
security of spent nuclear fuel stored in pools and dry casks at commercial nuclear power
plants in the United States. The public report can be viewed on the National Academies
Press website at http://books.nap.edu/catalog/11263.html.
Preliminary Site Requirements and Considerations for a Monitored Retrievable Storage Facility
Preliminary Site Requirements and Considerations for a Monitored Retrievable Storage Facility
In the November 1989 Report to Congress on Reassessment of the Civilian
Radioactive Waste Management Program (DOE/RW-0247), the Secretary of Energy
announced an initiative for developing a monitored retrievable storage (MRS) facility
that is to start spent-fuel acceptance in 1998. This facility, which will be licensed by
the U.S. Nuclear Regulatory Commission (NRC), will receive spent fuel from
commercial nuclear power plants and provide a limited amount of storage for this
Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology
Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology
The "Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology" contains a summary of the analyses that compare SNF measured isotopic concentrations (radiochemical assays) to calculated SNF isotop~c concentrations (SAS2H module ·orScale4.3). The results of these analyses are used to support the validation of the isotopic models for spent commercial light water reactor (LWR) fuel.
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to
Summary Report of Commercial Reactor Criticality Data for Catawba Unit 1
Summary Report of Commercial Reactor Criticality Data for Catawba Unit 1
The "Summary Report of Commercial Reactor Criticality Data for Catawba Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Catawba Unit 1 reactor.
Summary of the Nuclear Waste Administration Act of 2013 Discussion Draft
Summary of the Nuclear Waste Administration Act of 2013 Discussion Draft
The Nuclear Waste Administration Act of 2013 discussion draft is intended to implement the recommendations of the Blue Ribbon Commission on America’s Nuclear Future to establish a nuclear waste administration and create a consent-based process for siting nuclear waste facilities. The bill enables the federal government to fulfill its commitment to managing nuclear waste, ending the costly liability the government bears for its failure to dispose of commercial spent fuel.