Benchmarked analyses of neutrons and secondary gamma rays for a spent-fuel shipping cask using MORSE-CGA and MCNP 4A
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:426497
- New York Power Authority, White Plains, NY (United States)
This paper presents a benchmarked analysis of neutrons and secondary gamma rays emanating from a spent-fuel shipping cask. It compares calculated radiation dose rates using the MORSE-CGA program and the BUGLE-80 cross-section set with the MCNP program and available measured data. Neutron radiation from spent fuel is predominantly from spontaneous fission and the ({alpha},n) reaction from {sup 242}Cm and {sup 244}Cm. Therefore, the neutron source employed in the experiment was {sup 252}Cf, whose spectrum is similar to the fission spectrum expected from pressurized water reactor spent fuel. Secondary gammas are also produced during neutron transport. The experimental cask was designed to hold three PWR or seven boiling water reactor fuel assemblies. Casks were analyzed in both damaged and undamaged conditions.
- OSTI ID:
- 426497
- Report Number(s):
- CONF-961103--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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