The reactivity loss of PWR fuel with burnup has been investigated experimentally by measuring the reactivity worths of highly-burnt fuel samples in a PWR test lattice in the framework of the LWR-PROTEUS Phase II program. Seven UO2 samples cut from fuel rods irradiated in a Swiss PWR plant with burnups ranging up to ∼ 120 MWd/kg and four MOX samples with burnups up to ∼ 70 MWd/kg were inserted and withdrawn repeatedly in a test region constituted of actual PWR UO2 fuel rods in the center of the PROTEUS zero-power experimental facility. The measurements were analyzed using the CASMO-5 fuel assembly code and a cross-section library based on the ENDF/B-VII release 1 evaluation for the calculation of both the isotopic inventories of the samples ...
Use of the reconstructed fuel assemblies from partially burnt nuclear fuel pins is analyzed. This re...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
This paper presents an improved uncertainty quantification method for the validation of CASMO-5 on t...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
This paper presents an improved uncertainty quantification technique for the validation of CASMO-5 o...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Studies related to severe core accidents constitute a crucial element in the safety design of Gen-IV...
One of the significant issues yet to be resolved for using burnup credit (BUC) for spent nuclear fue...
This paper has presented the results of a computational benchmark and independent calculations to ve...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
Use of the reconstructed fuel assemblies from partially burnt nuclear fuel pins is analyzed. This re...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...
This paper presents an improved uncertainty quantification method for the validation of CASMO-5 on t...
Fuel rods with burnup values beyond 50GWd/t are characterised by relatively large amounts of fission...
This paper presents an improved uncertainty quantification technique for the validation of CASMO-5 o...
Spent fuel transportation and storage cask designs based on a burnup credit approach must consider i...
The purpose of this activity is to develop a representative ''limiting'' axial burnup profile for pr...
This report proposes and documents a computational benchmark problem for the estimation of the addit...
Studies related to severe core accidents constitute a crucial element in the safety design of Gen-IV...
One of the significant issues yet to be resolved for using burnup credit (BUC) for spent nuclear fue...
This paper has presented the results of a computational benchmark and independent calculations to ve...
The Interim Staff Guidance on burnup credit (ISG-8) issued by the United States Nuclear Regulatory C...
This report is one of the several recent NUREG/CR reports documenting benchmark-quality radiochemica...
The fuel matrix and the cladding constitute the first barrier against radioactive fission product re...
Use of the reconstructed fuel assemblies from partially burnt nuclear fuel pins is analyzed. This re...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuc...