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Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments
- Source :
- Nuclear Technology. 117:206-222
- Publication Year :
- 1997
- Publisher :
- Informa UK Limited, 1997.
-
Abstract
- The three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, is applied 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. The quantification of uncertainties in a typical shielding analysis process for transport/storage casks can be accomplished by 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, however, generally measure the overall validity of the calculational procedure. A total of five storage cask problems and two simple geometry problems were analyzed to determine the expected accur...
- Subjects :
- Nuclear and High Energy Physics
Measure (data warehouse)
Source code
Scale (ratio)
020209 energy
Nuclear engineering
media_common.quotation_subject
02 engineering and technology
Condensed Matter Physics
Spent nuclear fuel
Nuclear physics
020303 mechanical engineering & transports
0203 mechanical engineering
Nuclear Energy and Engineering
Electromagnetic shielding
0202 electrical engineering, electronic engineering, information engineering
Benchmark (computing)
Environmental science
CASK
Analysis method
media_common
Subjects
Details
- ISSN :
- 19437471 and 00295450
- Volume :
- 117
- Database :
- OpenAIRE
- Journal :
- Nuclear Technology
- Accession number :
- edsair.doi...........8a6d0a9a11d87ca8dcc2de0b01e4e2ec
- Full Text :
- https://doi.org/10.13182/nt97-a35326