The Interim Staff Guidance on burnup credit (ISG-8) for pressurized water reactor (PWR) spent nuclear fuel (SNF), issued by the Nuclear Regulatory Commission's (NRC) Spent Fuel Project Office, recommends the use of analyses that provide an ''adequate representation of the physics'' and notes particular concern with the ''need to consider the more reactive actinide compositions of fuels burned with fixed absorbers or with control rods fully or partly inserted.'' In the absence of readily available information on the extent of control rod (CR) usage in U.S. PWRs and the subsequent reactivity effect of CR exposure on discharged SNF, NRC staff have indicated a need for greater understanding in these areas. In response, this paper presents resul...
The purpose of this calculation is to develop axial profiles for estimating the axial variation in b...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
This report presents studies to assess reactivity margins and loading curves for pressurized water r...
This paper summarizes efforts related to developing a technically justifiable approach for addressin...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
One of the significant issues yet to be resolved for using burnup credit (BUC) for spent nuclear fue...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
When representing the behavior of commercial spent nuclear fuel (SNF), credit is sought for the redu...
The purpose of this calculation is to develop axial profiles for estimating the axial variation in b...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
The concept of taking credit for the reduction in reactivity of burned or spent nuclear fuel (SNF) d...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
This report presents studies to assess reactivity margins and loading curves for pressurized water r...
This paper summarizes efforts related to developing a technically justifiable approach for addressin...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
In the past, criticality safety analyses for spent fuel storage and transport canisters assumed the ...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
One of the significant issues yet to be resolved for using burnup credit (BUC) for spent nuclear fue...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
When representing the behavior of commercial spent nuclear fuel (SNF), credit is sought for the redu...
The purpose of this calculation is to develop axial profiles for estimating the axial variation in b...
The fuel irradiation and burnup causes geometrical and dimensional changes in the fuel rod which ...
This study performed criticality analysis for the GBC-68 storage cask loaded with boiling water reac...