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Strasser, P.*; Abe, Mitsushi*; Aoki, Masaharu*; Choi, S.*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; et al.
EPJ Web of Conferences, 198, p.00003_1 - 00003_8, 2019/01
Times Cited Count：15 Percentile：98.44(Quantum Science & Technology)Satoh, Daiki; Maeda, Yoshikazu*; Tameshige, Yuji*; Nakashima, Hiroshi; Shibata, Tokushi*; Endo, Akira; Tsuda, Shuichi; Sasaki, Makoto*; Maekawa, Motokazu*; Shimizu, Yasuhiro*; et al.
Journal of Nuclear Science and Technology, 49(11), p.1097 - 1109, 2012/11
Times Cited Count：16 Percentile：73.48(Nuclear Science & Technology)At the Fukui Prefectural Hospital Proton Therapy Center, neutron doses behind concrete shields and at maze have been measured by using radiation monitors, DARWIN, Wendi-2, a rem meter, and solid state nuclear track detectors. The measured data were compared with the estimations by analytical models and Monte Carlo code PHITS. The analytical model with the parameters employed in shielding design of the facility gave considerably larger estimates than the measured data. This means that the facility was designed with an enough safety margin. The calculation results of PHITS were less than those of the analytical model, and were about 3 times larger than the measured data. From the view point of a safety policy with conservative estimation for shielding design, Monte Carlo simulation is a better tool for estimating radiation safety at accelerator-based proton treatment facilities.
Satoh, Daiki; Nakashima, Hiroshi; Shibata, Tokushi; Endo, Akira; Tsuda, Shuichi; Tameshige, Yuji*; Maeda, Yoshikazu*; Sasaki, Makoto*; Maekawa, Motokazu*; Shimizu, Yasuhiro*; et al.
no journal, ,
In order to investigate the optimal design of a proton radiotherapy facility, neutron doses behind shielding walls were measured at the proton therapy center in Fukui prefectural hospital. The radiation monitors, DARWIN, WENDI-2, and REM, were used to assess the neutron doses. The doses obtained by DARWIN and WENDI-2 agreed well. It was found that the REM monitor underestimate the doses due to the lack of sensitivity to neutrons whose energy is above several tens of MeV.
Tameshige, Yuji*; Maeda, Yoshikazu*; Sasaki, Makoto*; Maekawa, Motokazu*; Shimizu, Yasuhiro*; Satoh, Daiki; Nakashima, Hiroshi; Endo, Akira; Shibata, Tokushi; Tsuda, Shuichi; et al.
no journal, ,
no abstracts in English
Saito, Fumihiro; Kasugai, Yoshimi; Seki, Kazunari; Nakane, Yoshihiro; Tani, Norio; Sato, Koichi; Yamazaki, Hirohito*; Bessho, Kotaro; Numajiri, Masaharu
no journal, ,
no abstracts in English
Matsui, Yoshiki; Kimura, Yoshiki; Umino, Yuji*; Hosoi, Masaharu*; Matsumoto, Tetsuya*; Shinohara, Nobuo; Yamazaki, Hitoshi; Yamaguchi, Tomoki
no journal, ,
Kato, Saori; Kasugai, Yoshimi; Saito, Fumihiro; Masukawa, Fumihiro; Numajiri, Masaharu*; Nakamura, Hajime*; Yamazaki, Hirohito*; Saito, Kiwamu*; Fujiwara, Kazuya*
no journal, ,
no abstracts in English
Matsui, Yoshiki; Kimura, Yoshiki; Umino, Yuji*; Hosoi, Masaharu*; Matsumoto, Tetsuya*; Shinohara, Nobuo; Yamazaki, Hitoshi; Yamaguchi, Tomoki
no journal, ,
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) is developing technologies for nuclear forensics to identify the origin and intended use of nuclear and radioactive materials. In order to share the experience on nuclear forensics analysis and to improve analytical techniques in the international community, the Nuclear Forensics International Technical Working Group (ITWG) regularly holds the Collaborative Materials Exercise (CMX). The ISCN participated in the 7th exercise (CMX-7) this time. This paper reports the experience of the exercise, and discusses nuclear forensics analytical capability of the ISCN based on the review of the exercise.
