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Validation of important fission product evaluations through CERES integral benchmarks
Validation of important fission product evaluations through CERES integral benchmarks
Optimization of energy resources suggests increased fuel residence in reactor cores and hence improved
fission product evaluations are required. For thermal reactors the fission product cross sections in the JEF2.2 and
JEFF3.1 libraries plus new evaluations from WPEC23 are assessed through modelling the CERES experiment in
the DIMPLE reactor. The analysis uses the lattice code WIMS10. Cross sections for 12 nuclides are assessed. The
thermal cross section and low energy resonance data for 147,152Sm and 155Gd are accurate to within 4%. Similar data
OCRWM Bulletin Fall 1995
OCRWM Bulletin Fall 1995
<p>A report from the US Deparement of Energy's Office of Civilian Radioactive Waste Management</p>
<p>Regulatory Drop Tests Planned for a Model Transportation Cask</p>
<p>Implementation Plan for the environmental Impact Statement for a Multi-Purpose Canister System for Management of Civilian and Naval Spent Nuclear Fuel Issued</p>
<p>Nuclear Waste Technical Review Board (NWTRB) Update</p>
<p>The NWTRB</p>
<p>Dry Transfer System Design Under Way</p>
OCRWM Bulletin Spring 1995
OCRWM Bulletin Spring 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights Include....</p>
<p>OCRWM FY 1996 Budget Presented to Congress</p>
<p>Public Responds to Waste Acceptance Issues</p>
<p>Transportation External Coordination Working Group Convenes in North Carolina</p>
<p>OCRWM Completes Draft Public Participation Plan</p>
<p>International Program Update</p>
OCRWM Bulletin Winter 1995
OCRWM Bulletin Winter 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>OCRWM Director Briefs US. Nuclear Regulatory Commission .</p>
<p>Notice of Inquiry: Technical Assistance and Training for Safe Transportation of Radioactive Waste</p>
<p>OCRWM Program Plan</p>
<p>Environmental Impact Statement Scoping for the Multi-Purpose Canister-Based System</p>
<p>Nuclear Waste Technical Review Board Update,</p>
<p>Nuclear Wasre Negotiator Update</p>
OCRWM Bulletin Special Edition August 1994
OCRWM Bulletin Special Edition August 1994
<p>MULTI-PURPOSE CANISTER PROCUREMENT: A SIGNIFICANT STEP FOR THE DEPARTMENT OF ENERGY'S CIVILIAN RADIOACTIVE WASTE MANAGEMENT PROGRAM</p>
OCRWM Bulletin Summer 1995
OCRWM Bulletin Summer 1995
<p>A newsletter from the Office of Civilian Radioactive Waste Management</p>
<p>Highlights include...</p>
<p>Westinghouse begins designing multi-purpose canister</p>
<p>DOE accepts General Atomics-9 assembly transportation cask trailer</p>
<p>Final interpretation of nuclear waste acceptance issues published</p>
Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life
Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life
Dry cask storage systems are deployed at nuclear power plants for used nuclear fuel (UNF)
Average Burnup and Axial Burnup Profile Measurement for Burnup Credit Application
Average Burnup and Axial Burnup Profile Measurement for Burnup Credit Application
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
Effects of the Presence of Axial Blankets and Integral Burnable Absorbers on the End Effect of PWR Burnup Profiles
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Limited Burnup Credit for Increased Fuel Enrichments in a Swiss PWR Storage Pool
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Spent Fuel Criticality Benchmark Experiments
Spent Fuel Criticality Benchmark Experiments
The Burn-Up Credit Experimental Programme REBUS
The Burn-Up Credit Experimental Programme REBUS
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Reactivity End-Effects Estimates Using a K Perturbation Model
Reactivity End-Effects Estimates Using a K Perturbation Model
Criticality Safety Evaluation of Fuel Storage Pools in Spain
Criticality Safety Evaluation of Fuel Storage Pools in Spain
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Recommendations Related to Browns Ferry Fire (NUREG-0050)
Recommendations Related to Browns Ferry Fire (NUREG-0050)
On March 22, 1975, a fire was experienced at the Browns Ferry Nuclear Plant near Decatur, Alabama. The Special Review Group was established by the Executive Director for Operations of the Nuclear Regulatory Commission (NRC) soon after the fire to identify the lessons learned from this event and to make recommendations for the future in the light of these lessons. Unless further developments indicate a need to reconvene the Review Group, its task is considered complete with the publication of this report.