Findings from a four year study by an international benchmarking group in the comparison of computational methods for evaluating burnup credit in criticality safety analyses are presented in this paper. Approximately 20 participants from 11 countries have provided results for most problems. Four detailed benchmark problems for Pressurized Water Reactor (PWR) fuel have been completed and are summarized in this paper. Preliminary results from current work addressing burnup credit for Boiling Water Reactor (BWR) fuel will also be discussed as well as planned activities for additional benchmarks including Mixed-Oxide (MOX) fuels, subcritical benchmarks, international databases, and other activities
New issues in criticality safety continue to emerge as spent fuel storage facilities reach the satur...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
Findings from a four year study by an international benchmarking group in the comparison of computat...
Findings from a four year study by an international benchmarking group in the comparison of computat...
Burnup credit is an ongoing technical concern for many countries that operate commercial nuclear pow...
Since the mid-1980s, a significant number of studies have been directed at understanding the phenome...
The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on ...
Enercon Services, Inc. (ENERCON) was requested under Task Order No.2 to identify scientific and tech...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the applicatio...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This report has been prepared to review relevant background information and provide technical discus...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
New issues in criticality safety continue to emerge as spent fuel storage facilities reach the satur...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
Findings from a four year study by an international benchmarking group in the comparison of computat...
Findings from a four year study by an international benchmarking group in the comparison of computat...
Burnup credit is an ongoing technical concern for many countries that operate commercial nuclear pow...
Since the mid-1980s, a significant number of studies have been directed at understanding the phenome...
The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on ...
Enercon Services, Inc. (ENERCON) was requested under Task Order No.2 to identify scientific and tech...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the applicatio...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
This report has been prepared to review relevant background information and provide technical discus...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
New issues in criticality safety continue to emerge as spent fuel storage facilities reach the satur...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...