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Title: SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configuration

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 United States, 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.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
885571
Report Number(s):
R00-106719
TRN: US0604056
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CONFIGURATION; CRITICALITY; DESIGN; DISTRIBUTION; GADOLINIUM; SENSITIVITY; SIMULATION; SPENT FUELS; WASTES; YUCCA MOUNTAIN

Citation Formats

Gauld, I.C. SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configuration. United States: N. p., 2000. Web. doi:10.2172/885571.
Gauld, I.C. SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configuration. United States. doi:10.2172/885571.
Gauld, I.C. Thu . "SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configuration". United States. doi:10.2172/885571. https://www.osti.gov/servlets/purl/885571.
@article{osti_885571,
title = {SCALE-4 Analysis of LaSalle Unit 1 BWR Commercial Reactor Critical Configuration},
author = {Gauld, I.C.},
abstractNote = {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 United States, 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.},
doi = {10.2172/885571},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 16 00:00:00 EST 2000},
month = {Thu Mar 16 00:00:00 EST 2000}
}

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