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Characterization of Spent Fuel Approved Testing Material
Characterization of Spent Fuel Approved Testing Material
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Analyses have been completed that indicate the consideration of spent fuel histories (''burnup credit'') in the design of spent fuel shipping casks is a justifiable concept that would result in cost savings and public risk benefits in the transport of spent nuclear fuel. Since cask capacities could be increased over those of casks without burnup credit, the number of shipments necessary to transport a given amount of fuel could be reduced.
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
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
Fission Product Benchmarking for Burnup Credit Applications
Fission Product Benchmarking for Burnup Credit Applications
Progress toward developing a technical basis for a cost-effective burnup credit methodology for
spent nuclear fuel with initial U-235 enrichment up to 5% is presented. 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. Progress also depends on optimizing the procedure for establishing the
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
Research to Support Expansion of U.S. Regulatory Position on Burnup Credit for Transport and Storage Casks
In 1999, the United States Nuclear Regulatory Commission (U.S. NRC) initiated a research program
to support the development of technical bases and guidance that would facilitate the implementation of burnup
credit into licensing activities for transport and dry cask storage. This paper reviews the following major areas of
investigation: (1) specification of axial burnup profiles, (2) assumption on cooling time, (3) allowance for
assemblies with fixed and removable neutron absorbers, (4) the need for a burnup margin for fuel with initial
HTC Experimental Program: Validation and Calculational Analysis
HTC Experimental Program: Validation and Calculational Analysis
In the 1980s a series of the Haut Taux de Combustion (HTC) critical experiments with fuel pins in a water-moderated lattice was conducted at the Apparatus B experimental facility in Valduc (Commissariat à l'Energie Atomique, France) with the support of the Institut de Radioprotection et de Sûreté Nucléaire and AREVA NC. Four series of experiments were designed to assess profit associated with actinide-only burnup credit in the criticality safety evaluation for fuel handling, pool storage, and spent-fuel cask conditions.
Validation Issues for Depletion and Criticality Analysis in Burnup Credit
Validation Issues for Depletion and Criticality Analysis in Burnup Credit
This paper reviews validation issues associated with implementation of burnup credit in transport, dry storage,
and disposal. The issues discussed are ones that have been identified by one or more constituents of the
United States technical community (national laboratories, licensees, and regulators) that have been exploring the
use of burnup credit. There is not necessarily agreement on the importance of the various issues, which
sometimes is what creates the issue. The broad issues relate to the paucity of available experimental data
Phenomena and Parameters Important to Burnup Credit
Phenomena and Parameters Important to Burnup Credit
Since the mid-1980s, a significant number of studies have been directed at understanding the phenomena and
parameters important to implementation of burnup credit in out-of-reactor applications involving pressurizedwater-
reactor (PWR) spent fuel. The efforts directed at burnup credit involving boiling-water-reactor (BWR)
spent fuel have been more limited. This paper reviews the knowledge and experience gained from work
performed in the United States and other countries in the study of burnup credit. Relevant physics and analysis
Temperature Effects on Reactivity of Commercial Reactor Criticals
Temperature Effects on Reactivity of Commercial Reactor Criticals
Temperature Effects on Reactivity of Commercial Reactor Criticals
Temperature Effects on Reactivity of Commercial Reactor Criticals
Overview of the Burnup Credit Activities at OECD/NEA/NSC
Overview of the Burnup Credit Activities at OECD/NEA/NSC
Value Rankings of Selected Critical Experiments for Burnup Credit Validations
Value Rankings of Selected Critical Experiments for Burnup Credit Validations
The Effect of Half-Life and Branching Fraction Uncertainties on the Effective Neutron Multiplication Factor
The Effect of Half-Life and Branching Fraction Uncertainties on the Effective Neutron Multiplication Factor
Dry Cask Storage and Transportation Burnup Credit
Dry Cask Storage and Transportation Burnup Credit
NRC Burnup Credit Research Program
NRC Burnup Credit Research Program
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
The Nuclear Energy Research Initiative Burnup Credit Critical Experiment
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
Reconciliation of Isotopic Uncertainty Between Assays and Integral Benchmarks
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
IAEA TCM 2000: An International Meeting on Burnup Credit Applications
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel
This report has been prepared to review relevant background information and provide technical discussion that will help initiate a PIRT (Phenomena Identification and Ranking Tables) process for use of burnup credit in light-water reactor (LWR) spent fuel storage and transport cask applications. The PIRT process will be used by the NRC Office of Nuclear Regulatory Research to help prioritize and guide a coordinated program of research and as a means to obtain input/feedback from industry and other interested parties.
Safety Evaluation Report for Disposal Criticality Analysis Methodology Topical Report, Revision 0
Safety Evaluation Report for Disposal Criticality Analysis Methodology Topical Report, Revision 0
In January 1999, the U.S. Department of Energy (DOE)/Office of Civilian Radioactive
Waste Management (OCRWM) submitted the Disposal Criticality Analysis Methodology
Topical Report, Revision 0 (TR) to the U.S. Nuclear Regulatory Commission (NRC) for
review and approval. The TR presents an overall approach for consideration of postclosure
disposal criticality of commercial and defense high-level waste to be placed at
the proposed Yucca Mountain site. During the course of the review and interactions