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Iwamoto, Yosuke; Sato, Tatsuhiko; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuda, Norihiro; Hosoyamada, Ryuji*; Niita, Koji*
Journal of Nuclear Science and Technology, 54(5), p.617 - 635, 2017/05
Times Cited Count：96 Percentile：99.72(Nuclear Science & Technology)We performed a benchmark study for 58 cases using the recent version 2.88 of the Particle and Heavy Ion Transport code System (PHITS) in the following fields: particle production cross-sections for nuclear reactions, neutron transport calculations, and electro-magnetic cascade. This paper reports details for 22 cases. In cases of nuclear reactions with energies above 100 MeV and electro-magnetic cascade, overall agreements were found to be satisfactory. On the other hand, PHITS did not reproduce the experimental data for an incident proton energy below 100 MeV, because the intranuclear cascade model INCL4.6 in PHITS is not suitable for the low-energy region. For proton incident reactions over 100 MeV, PHITS did not reproduce fission product yields due to the problem of high-energy fission process in the evaporation model GEM. To overcome these inaccuracies, we are planning to incorporate a high-energy version of the evaluated nuclear data library JENDL-4.0/HE, and so on.
Yamamoto, Kento*; Akie, Hiroshi; Suyama, Kenya; Hosoyamada, Ryuji*
JAEA-Technology 2015-019, 110 Pages, 2015/10
JAEA-Technology-2015-019.pdf:3.67MB
In the direct disposal of used nuclear fuel (UNF), criticality safety evaluation is one of the important issues since UNF contains some amount of fissile material. The recent development of higher-enrichment fuel has enhanced the benefit of the application of Burnup Credit. In the present study, the effects of the several parameters on the reactivity of disposal canister model were evaluated for used PWR fuel. The parameters are relevant to the uncertainties of depletion calculation code, irradiation history, and axial and horizontal burnup distribution, which are known to be important effect in the criticality safety evaluation adopting burnup credit. The latest data or methodology was adopted in this evaluation, based on the various latest studies. The appropriate margin of neutron multiplication factor in the criticality safety evaluation for UNF can be determined by adopting the methodology described in the present study.
Takahara, Shogo; Kimura, Masanori; Kinase, Sakae; Ishikawa, Jun; Suyama, Kenya; Hosoyamada, Ryuji; Homma, Toshimitsu
Progress in Nuclear Science and Technology (Internet), 3, p.25 - 29, 2012/10
Dose assessment is one of the important issues to make decisions in contaminated areas resulting from the Fukushima Daiichi Nuclear Power Plant accident. The doses to inhabitants of contaminated areas should be assessed prospectively and retrospectively taking into account the impact from various exposure pathways. The external exposure from deposited radioactive materials of short-lived and long-lived is one of the most important pathways. In the present study, the radionuclide compositions have been evaluated by source term analysis taking into account 54 radionuclides. This analysis consists in evaluating the inventory and the fraction of the radionuclides that were released into the atmosphere. On the assumption that dose rate may be decreased due to the radioactive decay as well as weathering effects, we have assessed the dose for future and past at the contaminated areas. The assessed values are almost consistent with the measured ones during the first month.
Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; et al.
JAEA-Review 2006-004, 226 Pages, 2006/03
JAEA-Review-2006-004.pdf:34.43MB
Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting.
Sasajima, Hideo; Nakamura, Takehiko; Chuto, Toshinori; Sugiyama, Tomoyuki; Hosoyamada, Ryuji; Fuketa, Toyoshi
no journal, ,
no abstracts in English
Nakamura, Jinichi; Nakamura, Takehiko; Hosoyamada, Ryuji; Suzuki, Motoe; Sugiyama, Tomoyuki; Fuketa, Toyoshi
no journal, ,
no abstracts in English
Hanawa, Satoshi; Ogiyanagi, Jin; Nakamura, Jinichi; Sasajima, Hideo; Takasa, Akira; Hosoyamada, Ryuji; Nakamura, Takehiko
no journal, ,
no abstracts in English
Matsuda, Norihiro; Iwamoto, Yosuke; Sato, Tatsuhiko; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Hosoyamada, Ryuji*; Iwase, Hiroshi*; et al.
no journal, ,
Iwamoto, Yosuke; Sato, Tatsuhiko; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuda, Norihiro; Hosoyamada, Ryuji*; Niita, Koji*
no journal, ,
Particles and Heavy Ions Transport code System (PHITS) is used for various purposes such as accelerator shielding design, medical physics calculations, and so on. In this study, we performed benchmark calculations for particle production cross sections (47 cases), neutron transport (6 cases) and electro-magnetic cascade (12 cases). For calculations of particle production cross sections, PHITS reproduced the experimental data for high-energy particle incident reactions with energies of above 100 MeV. On the other hands, PHITS did not reproduce the data for low-energy incident reactions due to outside of scope for the intra nuclear cascade model INCL4. We will incorporate the evaluated nuclear data library JENDL4.0/HE with PHITS to solve the problem. For calculations of electro-magnetic cascade, PHITS reproduced the data well. As a result, we validated the accuracy of PHITS calculations for various applied area and obtained guidelines for effective improvement of PHITS.
Iwamoto, Yosuke; Sato, Tatsuhiko; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuda, Norihiro; Hosoyamada, Ryuji*; Niita, Koji*
no journal, ,
Particles and Heavy Ions Transport code System (PHITS) is used for various purposes such as accelerator shielding design, medical physics calculations, and so on. In this study, we performed benchmark calculations for particle production cross sections (47 cases), neutron transport (6 cases) and electro-magnetic cascade (12 cases). For calculations of particle production cross sections, PHITS reproduced the experimental data for high-energy particle incident reactions with energies of above 100 MeV. On the other hands, PHITS did not reproduce the data for low-energy incident reactions due to outside of scope for the intra nuclear cascade model INCL4. We will incorporate the evaluated nuclear data library JENDL4.0/HE with PHITS to solve the problem. For calculations of electro-magnetic cascade, PHITS reproduced the data well. As a result, we validated the accuracy of PHITS calculations for various applied area and obtained guidelines for effective improvement of PHITS.
