Published 1989 | Version v1
Report Open

Evaluation of shielding analysis methods for spent fuel casks

Creators

  • 1. Oak Ridge National Lab., TN (USA)

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.

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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