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Shielding analyses for the REA-2023 and Castor-1C BWR storage casks

Conference ·
OSTI ID:5749801

A number of casks have been designed and several have been built for the storage of spent nuclear fuel rods. As part of the comprehensive demonstration test programs, spent fuel has been loaded into the REA-2023 and Castor-1C casks and radiation dose rates measured. Point kernel and discrete ordinates methods were used to predict radiation dose rates on the surface of the two casks. The QAD-CG code was used for primary gamma-ray calculations. The DOT-4 code was used for neutron and secondary gamma-ray calculations. Calculated dose rates agree resonably well with the measurements. Calculated neutron dose rates for the REA-2023 cask range from good agreement to a factor of four high. The calculated gamma-ray dose rates ranges from a factor of two high to a factor of four low. Calculated neutron dose rates for the Castor-1C cask range from a factor of two to a factor of four high. The calculated gamma-ray dose rates are a factor of two high. The sensitivity of the dose rates to the details of the calculation is discussed, and the importance of various assumptions made for the calculations is evaluated.

Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5749801
Report Number(s):
PNL-SA-13875; CONF-860417-9; ON: DE86011612
Country of Publication:
United States
Language:
English

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Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
BIOLOGICAL SHIELDING
CASKS
CONTAINERS
DOSE RATES
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IONIZING RADIATIONS
NEUTRON FLUX
RADIATION FLUX
RADIATIONS
SHIELDING
SPENT FUEL CASKS