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SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations.

DE2001769368

Publication Date	2000
Personal Author	Gauld, I. C.
Page Count	98
Abstract	Five commercial reactor criticals (CRCs) for the LaSalle Unit 1 boiling-water reactor have been analyzed using KENO V.a, the Monte Carlo criticality code of the SCALE 4 code system. The irradiated fuel assembly isotopics for the criticality analyses were provided by the Waste Package Design team at the Yucca Mountain Project in the US, who performed the depletion calculations using the SAS2H sequence of SCALE 4. The reactor critical measurements involved two beginning-of-cycle and three middle-of-cycle configurations. The CRCs involved relatively low-cycle burnups, and therefore contained a relatively high gadolinium poison content in the reactor assemblies. This report summarizes the data and methods used in analyzing the critical configurations and assesses the sensitivity of the results to some of the modeling approximations used to represent the gadolinium poison distribution within the assemblies. The KENO V.a calculations, performed using the SCALE 44GROUPNDF5 ENDF/B-V cross-section library, yield predicted k(sub eff) values within about 1% (Delta)k/k relative to reactor measurements for the five CRCs using general 8-pin and 9-pin heterogeneous gadolinium poison pin assembly models.
Keywords	Reactor safety Criticality Sensitivity Monte Carlo method Design Distribution Gadolinium Wastes Yucca mountain
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Oak Ridge National Lab., TN.; Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200124
Contract Number	AC05-00OR22725

SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations.

SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configurations.
DE2001769368

Publication Date	2000
Personal Author	Gauld, I. C.
Page Count	98
Abstract	Five commercial reactor criticals (CRCs) for the LaSalle Unit 1 boiling-water reactor have been analyzed using KENO V.a, the Monte Carlo criticality code of the SCALE 4 code system. The irradiated fuel assembly isotopics for the criticality analyses were provided by the Waste Package Design team at the Yucca Mountain Project in the US, who performed the depletion calculations using the SAS2H sequence of SCALE 4. The reactor critical measurements involved two beginning-of-cycle and three middle-of-cycle configurations. The CRCs involved relatively low-cycle burnups, and therefore contained a relatively high gadolinium poison content in the reactor assemblies. This report summarizes the data and methods used in analyzing the critical configurations and assesses the sensitivity of the results to some of the modeling approximations used to represent the gadolinium poison distribution within the assemblies. The KENO V.a calculations, performed using the SCALE 44GROUPNDF5 ENDF/B-V cross-section library, yield predicted k(sub eff) values within about 1% (Delta)k/k relative to reactor measurements for the five CRCs using general 8-pin and 9-pin heterogeneous gadolinium poison pin assembly models.
Keywords	Reactor safety Criticality Sensitivity Monte Carlo method Design Distribution Gadolinium Wastes Yucca mountain
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Oak Ridge National Lab., TN.; Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200124
Contract Number	AC05-00OR22725