Evaluation of shielding analysis methods in spent fuel cask environments. Final report

Technical Report · Mon May 01 00:00:00 EDT 1995

OSTI ID:95554

Broadhead, B L; Tang, J S; Childs, R L; Parks, C V; Taniuchi, H ^[1]

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1. Oak Ridge National Lab., TN (United States)

This report describes the application of the three-dimensional (3-D) Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of simple geometry benchmark experiments and prototypic spent fuel storage cask measurements. The simple geometry experiments were performed in Japan and at the General Electric-Morris Operation facility; the cask measurements were performed at the Idaho National Engineering Laboratory (INEL). The quantification of uncertainties in a typical shielding analysis process for transport/storage casks can be accomplished by a comparison of consistent trends between calculated and measured dose-rate quantities in both benchmark and prototypic environments. Benchmark results typically measure the validity of cross-section data and computer code adequacy; prototypic environments generally measure the overall validity of the calculational procedure. Five storage cask problems and two simple geometry problems were analyzed to determine the expected accuracies of computational analyses using well-established source-generation and Monte Carlo codes.

• Research Organization: Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 95554
• Report Number(s): EPRI-TR-104329
• Resource Relation: Other Information: PBD: May 1995
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
05 NUCLEAR FUELS
SPENT FUEL CASKS
SHIELDING
BENCHMARKS
RECOMMENDATIONS
GAMMA RADIATION
FUEL ASSEMBLIES
RADIATION DOSES
SOURCE TERMS
RADIATION SOURCES
O CODES
S CODES
MONTE CARLO METHOD
COMPUTER CALCULATIONS
SPENT FUEL STORAGE
D CODES
M CODES
CROSS SECTIONS