The Shielding Effect of Iron Louvers for Neutrons and Gamma Rays

The interim storage facility for spent fuel metallic cask is designed as a concrete building structure with air inlet and outlet for circulating the natural cooling. The feature of the interim storage facility is big capacity of spent fuel at several thousands MTU and restricted site usage. It is important to evaluate realistic dose rate in shielding design of the interim storage facility, therefore the three-dimensional continuous-energy Monte Carlo radiation transport code MCNP that exactly treating the complicated geometry was applied. The validation of dose evaluation for interim storage facility by MCNP code were performed by three kinds of neutron shielding benchmark experiments; cask shadow shielding experiment, duct streaming experiment and concrete deep penetration experiment. Dose rate distributions at each benchmark were measured and compared with the calculated results. The comparison showed a good consistency between calculation and experiment results.

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Application of Dose Evaluation of the MCNP Code for Interim Spent Fuel Cask Storage Facility

Kosako¹,

Iimoto²,

Ishikawa³

et al. 2007

Nihon Genshiryoku Gakkai wabun rombunshi

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The Shielding Effect of Iron Louvers for Neutrons and Gamma Rays

Cited by 1 publication

References 15 publications

Application of Dose Evaluation of the MCNP Code for Interim Spent Fuel Cask Storage Facility

Application of Dose Evaluation of the MCNP Code for Interim Spent Fuel Cask Storage Facility

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