Category of Content
Siting Experience Documents Only
Publication Date
Subject Matter
Keywords
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
Why DOE's Messages on Transportation Don't Resonate with the Public (and What DOE Can Do to Fix the Problem)
Why DOE's Messages on Transportation Don't Resonate with the Public (and What DOE Can Do to Fix the Problem)
Yankee Atomic Electric Company vs The United States, November 14, 2013
Yankee Atomic Electric Company vs The United States, November 14, 2013
Spent Nuclear Fuel Litigation - Court of Federal Claims decision in Maine Yankee II, Conn Yankee II and Yankee Atomic II
ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS
ORDER GRANTING APPLICATIONS TO REDUCE RATES UNDER WHOLESALE POWER CONTRACTS
<div class="page" title="Page 1">
<div class="layoutArea">
<div class="column">
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>
Lessons Learned from the West Valley Spent Nuclear Fuel Shipment within the United States
Lessons Learned from the West Valley Spent Nuclear Fuel Shipment within the United States
This paper describes the lessons learned from the U.S. Department of Energy (DOE) transportation of
125 DOE-owned commercial spent nuclear fuel (SNF) assemblies by railroad from the West Valley Demonstration
Project to the Idaho National Engineering and Environmental Laboratory (INEEL). On July 17, 2003, DOE made
the largest single shipment of commercial SNF in the history of the United States. This was a highly visible and
political shipment that used two specially designed Type B transportation and storage casks. This paper describes
WCS Resolution
WCS Resolution
In the commissioners court of Andrews County, Texas
A resolution in support of establishing a site in Andrews County for consolidated interim storage of spent nuclear fuel and high-level radioactive waste.
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)
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
Validation of SCALE-4 for Burnup Credit Applications
Validation of SCALE-4 for Burnup Credit Applications
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews.
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases.
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Fission Product Experiment Program: Validation and Calculational Analysis
Fission Product Experiment Program: Validation and Calculational Analysis
From 1998 to 2004, a series of critical experiments referred to as the fission product (FP) experimental program was performed at the Commissariat à l'Energie Atomique Valduc research facility. The experiments were designed by Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and funded by AREVA NC and IRSN within the French program supporting development of a technical basis for burnup credit validation.