Evaluation of shielding analysis methods for spent fuel casks

Conference · Sun Jan 01 04:00:00 EST 1989

OSTI ID:5584620

Parks, C V ^[1]

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

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.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5584620
• Report Number(s): CONF-891103-20; ON: DE89015893
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BARYONS
BURNUP
CASKS
COMPUTER CODES
CONTAINERS
CROSS SECTIONS
DOSIMETRY
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
FERMIONS
GAMMA RADIATION
HADRONS
IONIZING RADIATIONS
NEUTRONS
NUCLEONS
RADIATION TRANSPORT
RADIATIONS
SHIELDING
SPENT FUEL CASKS