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SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
DOE Sends Proposal to Congress for Monitored Retrievable Storage Facility in Tennessee
DOE Sends Proposal to Congress for Monitored Retrievable Storage Facility in Tennessee
OCRWM Bulletin (DOE/RW-0130) - DOE Sends Proposal to Congress for Monitored Retrievable Storage Facility in Tennessee
Geological Challenges in Radioactive Waste Isolation Third Worldwide Review
Geological Challenges in Radioactive Waste Isolation Third Worldwide Review
The first worldwide review of geological problems in radioactive waste isolation was published by the Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) in 1991 (Witherspoon, 1991). This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9Ð19, 1989, in Washington, D.C.
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 spent fuel.
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
This report has been produced at the request of Congress. The House Appropriations Committee Print that accompanied the Consolidated Appropriations Act, 2008, requests that the U.S. Department of Energy (the Department):<br/>…develop a plan to take custody of spent fuel currently stored at decommissioned reactor sites to both reduce costs that are ultimately borne by the taxpayer and demonstrate that DOE can move forward in the near term with at least some element of nuclear waste policy.
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
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.
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
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Investigation of Average and Pin-Wise Burnup Modeling of PWR Fuel
Burnup Credit - Technical Basis for Spent-Fuel Burnup Verification
Burnup Credit - Technical Basis for Spent-Fuel Burnup Verification
Present regulatory practices provide as much burnup credit flexibility as can be currently
expected. Further progress is achievable by incorporating the negative reactivity effects of a
subset of neutron-absorbing fission-product isotopes, and by optimizing the procedural approach
for establishing the burnup characteristics of the spent fuel to be loaded in burnup-creditdesigned
storage and transportation systems. This report describes progress toward developing a
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.
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
Improved Radiochemical Assay Analyses Using TRITON Depletion Sequences in SCALE
Issues for Effective Implementation of Burnup Credit
Issues for Effective Implementation of Burnup Credit
In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
Regulatory Status of Burnup Credit for Spent-Fuel Storage and Transport Casks
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues - Results from Phase 1 on UOx Fuels
Although there are many reactor system benchmarks in the literature, they mostly
concentrate on the reactor system in isolation with only a few considering the fuel cycle.
However, there is currently increased emphasis on the performance of reactor systems
linked to their associated fuel cycle (Generation-IV for example). The published
international benchmark studies which relate to burn-up depletion calculations are
restricted to specific aspects of the fuel cycle:
Cross-Checking of the Operator Data Used for Burn Up Measurements
Cross-Checking of the Operator Data Used for Burn Up Measurements
Taking into account of the loss of reactivity of fuels at the end of their irradiation is known under the
term burnup credit (BUC). It is a question of dimensioning in a less penalizing way the devices of transport,
storage or of processing with respect to the risk of criticality. In the context of nuclear criticality safety a better
realism cannot be obtained at the price of conservatism. As a result the regulator requires measurements make it
possible to validate the adequacy between real fuels and the design assumptions. The sophistication of the