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 pressurized-water-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 US and other countries in the study of burnup credit. Relevant physics and analysis phenomenon are identified, and an assessment of their importance to burnup credit implementation for transport and dry cask storage is given
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
Storage, transportation and disposal of spent nuclear fuel continue to be significant problems faced...
Findings from a four year study by an international benchmarking group in the comparison of computat...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
This report has been prepared to review relevant background information and provide technical discus...
Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the applicatio...
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...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
Storage, transportation and disposal of spent nuclear fuel continue to be significant problems faced...
Findings from a four year study by an international benchmarking group in the comparison of computat...
In 1999 the U.S. Nuclear Regulatory Commission (U.S. NRC) initiated a research program to support th...
This report has been prepared to review relevant background information and provide technical discus...
Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the applicatio...
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...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
International audienceBurnup credit for used fuel assemblies, in particular, pressurized water react...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
Storage, transportation and disposal of spent nuclear fuel continue to be significant problems faced...