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Validation of Nuclear Calculations with the FENDL/E-1.1 and JENDL Fusion File Based on a Bulk-Shielding Experiment of a Large Type 316 Stainless Steel Assembly

Chikara Konno, Fujio Maekawa, Yukio Oyama, Yujiro Ikeda, Masayuki Wada, Hiroshi Maekawa

Fusion Science and Technology / Volume 34 / Number 1 / August 1998 / Pages 6-17

Technical Paper

An analysis of the bulk-shielding experiment on Type 316 stainless steel (SS316) for deuterium-tritium neutrons was performed at the Japan Atomic Energy Research Institute Fusion Neutronics Source to validate the nuclear data and transport codes used in the shielding design of the International Thermonuclear Experimental Reactor (ITER). The MCNP-4A and DORT3.1 codes with contemporary nuclear data libraries based on the FENDL/E-1.1 and JENDL Fusion File were used for the analyses. The MCNP calculations with the FENDL/E-1.1 and JENDL Fusion File agree within 30% with the measured data. The DORT calculations with the FENDL/E-1.1 and JENDL Fusion File with an energy structure of 175 neutrons and 42 gamma rays and a self-shielding correction represent the measurements with almost the same accuracy as the MCNP calculations. It is concluded that the uncertainty of the shielding calculation for the bulk-shielding configuration of MCNP-4A and DORT3.1 with the FENDL/E-1.1 and JENDL Fusion File on a 900-mm-thick SS316 shield is within 30%.

 
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