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Takada, Kenta*; Sato, Tatsuhiko; Kumada, Hiroaki*; Koketsu, Junichi*; Takei, Hideyuki*; Sakurai, Hideyuki*; Sakae, Takeji*
Journal of Radiation Research, 59(1), p.91 - 99, 2018/01
Times Cited Count:32 Percentile:87.69(Biology)Evaluation of the relative biological effectiveness (RBE)-weighted dose is indispensable in the treatment planning of proton and carbon ion therapies. In this study, we validate the RBE-weighted dose calculated by microdosimetric kinetic model (MKM) in tandem with the Monte Carlo particle transport code PHITS for proton therapy using the full simulation geometry for the beam line of the Proton Medical Research Center at the University of Tsukuba. The physical dose and RBE-weighted dose on the central axis for a 155 MeV monoenergetic and spread-out Bragg peak beam of 60 mm width are evaluated by the method. The calculated results generally agree with the corresponding experimental data very well, though overestimations by approximately 3.2% and 15% at the maximum are observed for the physical and RBE-weighted doses, respectively. This research completes the computational microdosimetric approach based on a combination of PHITS and MKM for all types of radiotherapy that require RBE evaluations.
Shinohara, Masanori; Motegi, Toshihiro; Saito, Kenji; Haga, Hiroyuki; Sasaki, Shinji; Katsuyama, Kozo; Takada, Kiyoshi*; Higashimura, Keisuke*; Fujii, Junichi*; Ukai, Takayuki*; et al.
JAEA-Technology 2012-032, 29 Pages, 2012/11
An event, in which one of WRMs were disabled to detect the neutron flux in the reactor core, occurred during the period of reactor shut down of HTTR in March, 2010. The actual life time of WRM was unexpectedly shorter than the past developed life time. Investigation of the cause of the outage of WRM toward the recovery of the life time up to the past developed life is one of the issues to develop the technology basis of HTGR. Then, two experimental investigations were carried out to reveal the cause of the malfunction by specifying the damaged part causing the event in the WRM. One is an experiment using a mock-up sample test which strength degradation on assembly accuracy and heat cycle to specify the damaged part in the WRM. The other is a destructive test in FMF to specify the damaged part in the WRM. This report summarized the results of the destructive test and the experimental investigation using the mock-up to reveal the cause of malfunction of WRM.
Kaji, Yoshiyuki; Kondo, Keietsu; Aoyagi, Yoshiteru; Kato, Yoshiaki; Taguchi, Taketoshi; Takada, Fumiki; Nakano, Junichi; Ugachi, Hirokazu; Tsukada, Takashi; Takakura, Kenichi*; et al.
Proceedings of 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (CD-ROM), p.1203 - 1216, 2011/08
In order to investigate the effect of neutron dose rate on tensile property and irradiation assisted stress corrosion cracking (IASCC) growth behavior, the crack growth rate (CGR) test, tensile test and microstructure observation have been conducted with type 304 stainless steel specimens. The specimens were irradiated in high temperature water simulating the temperature of boiling water reactor (BWR) up to about 1dpa with two different dose rates at the Japan Materials Testing Reactor (JMTR). The radiation hardening increased with the dose rate, but there was little effect on CGR. Increase of the yield strength of specimens irradiated with the low dose rate condition was caused by the increase of number density of frank loops. Little difference of radiation-induced segregation at grain boundaries was observed in specimens irradiated by different dose rates. Furthermore, there was little effect on local plastic deformation behavior near crack tip in the crystal plasticity simulation.
Watanabe, Koji; Tashiro, Shinsuke; Abe, Hitoshi; Takada, Junichi; Morita, Yasuji
JAERI-Tech 2004-029, 48 Pages, 2004/03
In a part of building ventilating installation of a nuclear fuel facility, a reprocessing plant for example, the pre-filters are adopted as one of the ventilation filters. In a fire accident, it is supposed that, because of the pre-filter clogging by large smoke, its differential pressure (p) is evolved up to the value at its breakage. Therefore, in regard to maintaining the confinement of radioactive materials, it is important to predict the time course of p of the pre-filter accurately. In the current study, it was assumed that the empirical equation for the DF of the pre-filter as function of smoke particle diameter (SPD), between 0.7-2 m, could be applied to estimating its DF for SPD above 2 m. Under this assumption, the time corresponding to its p at its breakage, calculated by CELVA-1D, was agreed well with the experimental result.
Takada, Tomoyuki; Miyoshi, Yoshinori; Katakura, Junichi
JAERI-Tech 2003-036, 80 Pages, 2003/03
In order to perform accuracy evaluation of the critical calculation by the combination of multi-group constant library MGCL and 3-dimensional Monte Carlo code KENO-IV among critical safety evaluation code system JACS, benchmark calculation was carried out from 1980 in 1982. Some cases where the neutron multiplication factor calculated in the heterogeneous system in it was less than 0.95 were seen. In this report, it re-calculated by considering the cause about the heterogeneous system of the U+Pu nitric acid solution systems containing the neutron poison shown in JAERI-M 9859. The present study has shown that the keff value less than 0.95 given in JAERI-M 9859 is caused by the fact that the water reflector below a cylindrical container was not taken into consideration in the KENO-IV calculation model. By taking into the water reflector, the KENO-IV calculation gives a keff value greater than 0.95 and a good agreement with the experiment.
Takada, Junichi; Hayashi, Shiro*; Watanabe, Koji; Takita, Koji*; Tsukamoto, Michio; Tashiro, Shinsuke; Abe, Hitoshi*; Uchiyama, Gunzo*
JAERI-Tech 2002-102, 87 Pages, 2003/01
no abstracts in English
Ishii, Toshimitsu; Yonekawa, Minoru; Omi, Masao; Takada, Fumiki; Saito, Junichi; Ioka, Ikuo; Miwa, Yukio
KAERI/GP-192/2002, p.157 - 166, 2002/00
no abstracts in English
Abe, Hitoshi; Watanabe, Koji*; Tashiro, Shinsuke; Takada, Junichi; Uchiyama, Gunzo
JAERI-Research 2001-052, 18 Pages, 2001/11
no abstracts in English
Tsukamoto, Michio; Takada, Junichi; Koike, Tadao; Watanabe, Koji*; Miyata, Teijiro*; Nishio, Gunji*; Murata, Mikio*; Uchiyama, Gunzo
JAERI-Tech 2001-031, 47 Pages, 2001/03
no abstracts in English
Tsukamoto, Michio; Takada, Junichi; Koike, Tadao; Watanabe, Koji*; Miyata, Teijiro*; Nishio, Gunji*; Murata, Mikio
JAERI-Tech 2000-036, p.43 - 0, 2000/03
no abstracts in English
Miyata, Teijiro*; Takada, Junichi; Ida, Masaaki*; Nakagiri, Naotaka*; Koike, Tadao; Tsukamoto, Michio; Watanabe, Koji*; Nishio, Gunji*
JAERI-Tech 2000-035, p.64 - 0, 2000/03
no abstracts in English
Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.
JAERI-Research 99-056, p.278 - 0, 1999/09
no abstracts in English
Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; *; Murata, Mikio
Journal of Nuclear Science and Technology, 36(7), p.619 - 625, 1999/07
Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)no abstracts in English
Miyata, Teijiro; Takada, Junichi; Nakagiri, Naotaka*; Koike, Tadao; Tsukamoto, Michio; *; Nishio, Gunji*
JAERI-Tech 99-040, 194 Pages, 1999/05
no abstracts in English
Miyata, Teijiro; Takada, Junichi; Ida, Masaaki*; Nakagiri, Naotaka*; Tsukamoto, Michio; Koike, Tadao; *; Nishio, Gunji*
JAERI-Tech 99-039, 70 Pages, 1999/05
no abstracts in English
Murata, Mikio; Takada, Junichi; Tsukamoto, Michio
KURRI-KR-30, p.5 - 11, 1998/00
no abstracts in English
*; Takada, Junichi
Earozoru Kenkyu, 12(1), p.50 - 56, 1997/00
no abstracts in English
Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; *
JAERI-Tech 96-054, 237 Pages, 1996/12
no abstracts in English
Nishio, Gunji; Takada, Junichi; *; Murata, Mikio; Abe, Hitoshi; *
JAERI-Research 95-064, 45 Pages, 1995/09
no abstracts in English
Nishio, Gunji; Koike, Tadao; Miyata, Teijiro; Takada, Junichi; *
JAERI-Tech 95-029, 59 Pages, 1995/03
no abstracts in English