Benchmarked analyses of neutrons and secondary gamma rays for a spent-fuel shipping cask using MORSE-CGA and MCNP 4A

Journal Article · Tue Dec 31 00:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:426497

Golshani, M ^[1]

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1. 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-; ISSN 0003-018X; TRN: 96:006307-0226
• Journal Information: Transactions of the American Nuclear Society, Vol. 75; Conference: Winter meeting of the American Nuclear Society (ANS) and the European Nuclear Society (ENS), Washington, DC (United States), 10-14 Nov 1996; Other Information: PBD: 1996
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
05 NUCLEAR FUELS
SPENT FUEL CASKS
DOSE RATES
BENCHMARKS
NEUTRONS
GAMMA RADIATION
M CODES