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Hirayama, Hideo*; Nakashima, Hiroshi; Morishima, Makoto*; Uematsu, Mikio*; Sato, Osamu*
Journal of Nuclear Science and Technology, 52(11), p.1339 - 1361, 2015/11
Times Cited Count：7 Percentile：20.83(Nuclear Science & Technology)Progress in calculation methods for radiation shielding are reviewed based on basis of the activities of research committees related to radiation shielding fields established in the Atomic Energy Society of Japan. A technological roadmap for the field of radiation shielding, progress and prospects for specific shielding calculation methods such as the Monte Carlo, discrete ordinate Sn transport, and simplified methods, and shielding experiments used to validate calculation methods are presented in this paper.
Kawai, Masayoshi*; Hayashida, Yoshihisa*; Yamauchi, Michinori*; Uematsu, Mikio*; Sato, Yoshiaki*; Niidome, Jiro*; Nakai, Masaru*
PNC TJ201 82-03, 160 Pages, 1982/02
Analyses of JOYO shielding experimental data have been performed for the purpose of studying the shielding design technique of fast breeder reactor, confirming the shielding calculation procedure of prototype fast breeder reactor MONJU, and acquiring the data for the evaluation of the uncertainty shielding design. This paper describes the analyses for the effect of neutron streaming through the detector guide tube in the pedestal heavy concrete upon the experimental data, for the neutron streaming through the primary coolant and the argon cover gas pipe penetrations in the biological shield concrete and for the neutron behaviour in the primary pump room and in the intermediate heat exchanger room. The calculation was carried out by using the albedo monte carlo code morsealb with 21 neutron groups and p5anisotropic scattering cross section. The calculated results were compared with the shielding performance test data of JOYO. It was found that the present albedo monte carlo method predicted the therm
