Published 1989
| Version v1
Report
Open
Evaluation of shielding analysis methods for spent fuel casks
Description
Accurate results from shielding analyses of spent fuel casks are increasingly important as the desire for optimized designs increases. ALARA concerns also contribute to the need for accurate dose evaluations for casks. Three areas require the attention of cask shielding analysts --- radiation source generation, utilization of cross-section data, and the radiation transport and dose evaluation. This paper reviews recent efforts carried out at Oak Ridge National Laboratory (ORNL) to evaluate the impact of various codes, data, and analysis assumptions on the calculation of radiation doses from spent fuel casks. 9 refs., 1 tab
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE89015893; OSTI; INIS; US Govt. Printing Office Dep.Files
21020008.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- CONF-891103--20
Conference
- Title
- Winter meeting of the American Nuclear Society.
- Dates
- 26-30 Nov 1989.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21020008
- Subject category
- S42: ENGINEERING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BURNUP; CASKS; CROSS SECTIONS; DOSIMETRY; GAMMA RADIATION; NEUTRONS; RADIATION TRANSPORT; SHIELDING
- Descriptors DEC
- BARYONS; COMPUTER CODES; CONTAINERS; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; FERMIONS; HADRONS; IONIZING RADIATIONS; NUCLEONS; RADIATIONS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400