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Ishikawa, Takatsugu*; Fujimura, Hisako*; Fukasawa, Hiroshi*; Hashimoto, Ryo*; He, Q.*; Honda, Yuki*; Hosaka, Atsushi; Iwata, Takahiro*; Kaida, Shun*; Kasagi, Jirota*; et al.
Physical Review C, 101(5), p.052201_1 - 052201_6, 2020/05
Times Cited Count:4 Percentile:44.35(Physics, Nuclear)Sakamoto, Yukio; Chiba, Satoshi; Nagaya, Yasunobu
Nihon Genshiryoku Gakkai-Shi ATOMO, 51(12), p.875 - 879, 2009/12
The MCNP/MCNPX codes are widely used for nuclear analyses and critical safety evaluations in nuclear facilities, shielding calculations of neutrons and photons, and behavior analyses and shielding calculations of high energy radiation in accelerators facilities. In this April, Radiation Safety Information Computational Center (RSICC) of Oak Ridge National Laboratory (ORNL) in USA sent the message that the new distributions of these codes should be stopped for the time being to Research Organization for Information Science & Technology (RIST) which can distribute codes registered by RSICC in Japan. The persons concerned were shocked by the news. These codes are used for design calculations and experimental analyses, and incorporated in newly developing codes. In this paper, the present status of these code usage and code development incorporated by these is reviewed. Fortunately codes and data set, the general-purpose neutron and photon transport Monte Carlo code MVP for reactor nuclear analyses, particle and heavy ion transport code system PHITS for behavior analyses of various radiation with wide range energy and JENDL-4 for nuclear data, are developing and preparing steadily in Japan.
Tobita, Kenji; Nishio, Satoshi; Sato, Masayasu; Sakurai, Shinji; Hayashi, Takao; Shibama, Yusuke; Isono, Takaaki; Enoeda, Mikio; Nakamura, Hirofumi; Sato, Satoshi; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2006/10
no abstracts in English
Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Sato, Masayasu; Isono, Takaaki; Sakurai, Shinji; Nakamura, Hirofumi; Sato, Satoshi; Suzuki, Satoshi; Ando, Masami; et al.
Fusion Engineering and Design, 81(8-14), p.1151 - 1158, 2006/02
Times Cited Count:124 Percentile:99.05(Nuclear Science & Technology)no abstracts in English