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Your search keyword '"Yoshioka, Kenichi"' showing total 122 results
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122 results on '"Yoshioka, Kenichi"'

1. Contributors

Author

Hino, Tetsushi, primary, Ikeda, Haruhiko, additional, Iwaki, Chikako, additional, Katayama, Yukihiro, additional, Kawai, Hiroki, additional, Koizumi, Yasuo, additional, Matsuura, Masayoshi, additional, Miyano, Hiroshi, additional, Mori, Michitsugu, additional, Morooka, Shinichi, additional, Narabayashi, Tadashi, additional, Nishida, Koji, additional, Nishimura, Akira, additional, Shirahama, Hisatoshi, additional, Suzuki, Hirotsugu, additional, Wakasugi, Kazuhiko, additional, Yabushita, Yukihisa, additional, Yokobori, Seiichi, additional, Yoshimoto, Yuichiro, additional, and Yoshioka, Kenichi, additional

Published
2023
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3. BWR innovations

Author

Hino, Tetsushi, primary, Morooka, Shinichi, additional, Yoshioka, Kenichi, additional, Narabayashi, Tadashi, additional, Mori, Michitsugu, additional, and Iwaki, Chikako, additional

Published
2023
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8. FUEL-CYCLE SCENARIO TO REDUCE RADIOACTIVE WASTE FROM LIGHT-WATER REACTOR

Author

Wada Satoshi, Hiraiwa Kouji, Yoshioka Kenichi, Sugita Tsukasa, and Kimura Rei

Subjects
nuclear-fuel cycle, light-water reactor, trans-uranium, forseti, Physics, QC1-999
Abstract

It is important to reduce the amount of trans-uranium (TRU) produced from the existing nuclear power plants to realize sustainable nuclear energy since the some TRU nuclides remain for a long time and have high radioactivity and radiotoxicity. One of the promising solutions is to transmute the TRU nuclides to those with lesser radioactivity and radiotoxicity in the existing nuclear reactors. In the current scheme, the TRU nuclides are transmuted in fast reactors and/or accelerator-driven-systems, however, this scenario seems unpromising in Japan: after the Fukushima Daiichi accident, it is required to reduce the production of TRU nuclides from the light-water reactors. In the previous studies, a concept of FORSETI was investigated, and a nuclear-fuel cycle simulation code ATRUNCYS was developed to study the low TRU production scenario. The FORSETI concept consists of two types of fuels: 1) UO2 fuels with high-assay low-enriched-uranium, and 2) MOX fuels with highly fissile concentrated plutonium reprocessed from the FORSETI-UO2 fuels. The current paper focuses on the following two scenarios: a) once-recycled scenario with the current fuel design, and b) once-recycled scenario with the FORSETI concept. The two scenarios were compared by using the ATRUNCYS code where the simulation studies showed that the amount, radioactivity, and radiotoxicity of resulting waste can be decreased in the FORSETI concept: In the case 1), the production of TRU nuclides decreased in the UO2 fuel; In the case 2), the fission rate increased and neutron-capture reactions of 240Pu and 241Pu decreased in the MOX fuels.

Published
2021
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15. 5 - BWR innovations

Author

Hino, Tetsushi, Morooka, Shinichi, Yoshioka, Kenichi, Narabayashi, Tadashi, Mori, Michitsugu, and Iwaki, Chikako

Published
2023
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22. FUEL-CYCLE SCENARIO TO REDUCE RADIOACTIVE WASTE FROM LIGHT-WATER REACTOR.

Author

Margulis, M., Blaise, P., Wada, Satoshi, Hiraiwa, Kouji, Yoshioka, Kenichi, Sugita, Tsukasa, and Kimura, Rei

Subjects
NUCLEAR power plants, LIGHT water reactors, RADIOACTIVE waste management, NUCLEAR reactors, NEUTRON transport theory
Abstract

It is important to reduce the amount of trans-uranium (TRU) produced from the existing nuclear power plants to realize sustainable nuclear energy since the some TRU nuclides remain for a long time and have high radioactivity and radiotoxicity. One of the promising solutions is to transmute the TRU nuclides to those with lesser radioactivity and radiotoxicity in the existing nuclear reactors. In the current scheme, the TRU nuclides are transmuted in fast reactors and/or accelerator-driven-systems, however, this scenario seems unpromising in Japan: after the Fukushima Daiichi accident, it is required to reduce the production of TRU nuclides from the light-water reactors. In the previous studies, a concept of FORSETI was investigated, and a nuclear-fuel cycle simulation code ATRUNCYS was developed to study the low TRU production scenario. The FORSETI concept consists of two types of fuels: 1) UO2 fuels with high-assay low-enriched-uranium, and 2) MOX fuels with highly fissile concentrated plutonium reprocessed from the FORSETI-UO2 fuels. The current paper focuses on the following two scenarios: a) once-recycled scenario with the current fuel design, and b) once-recycled scenario with the FORSETI concept. The two scenarios were compared by using the ATRUNCYS code where the simulation studies showed that the amount, radioactivity, and radiotoxicity of resulting waste can be decreased in the FORSETI concept: In the case 1), the production of TRU nuclides decreased in the UO2 fuel; In the case 2), the fission rate increased and neutron-capture reactions of 240Pu and 241Pu decreased in the MOX fuels. [ABSTRACT FROM AUTHOR]

Published
2021
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28. Streaming Effect of Void Reactivity in LWR Critical Experiments with Streaming Channel.

Author

Yoshioka, Kenichi, Yamaoka, Mitsuaki, Hiraiwa, Kouji, and Kitada, Takanori

Subjects
*MONTE Carlo method, *REACTIVITY (Chemistry), *ALUMINUM
Abstract

The void reactivity of a fuel assembly with a streaming channel was measured in a simulated light water reactor critical lattice. The void reactivity was defined as the difference of reactivity ρ between different void conditions. Stainless steel and Zircaloy are candidates for the streaming channel material. Aluminum was used in this measurement because it is inexpensive and its absorption cross section is similar to that of Zircaloy. Two types of streaming channels were used: one made of aluminum and the other made of stainless steel. The two streaming channels were compared in terms of the difference in void reactivity. Measured values were calculated using a continuous-energy Monte Carlo code, MCNP6.1, with the JENDL-4.0 and ENDF/B-VIII.0 nuclear data libraries. The measured values and the calculated values agree within an error range of approximately 10% for the aluminum streaming channel and approximately 20% for the stainless steel streaming channel. The streaming effect of reactivity was deduced from the changes of migration area and buckling, which were measured using the water-height coefficient of reactivity and the axial fission-rate distribution. [ABSTRACT FROM AUTHOR]

Published
2021
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32. Neutron Radiography Using Inertial Electrostatic Confinement (IEC) Fusion

Author

TAKAKURA, Kei, primary, SAKO, Takayuki, additional, MIYADERA, Haruo, additional, YOSHIOKA, Kenichi, additional, KARINO, Yoshiji, additional, NAKAYAMA, Kohichi, additional, SUGITA, Tsukasa, additional, UEMATSU, Daisuke, additional, OKUTOMO, Kohei, additional, HASEGAWA, Jun, additional, KOHNO, Toshiyuki, additional, and HOTTA, Eiki, additional

Published
2018
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44. ICONE23-1569 FUKUSHIMA DAIICHI MUON IMAGING

Author

Miyadera, Haruo, primary, Morris, Christopher, additional, Bacon, Jeffery, additional, Borozdin, Konstantin, additional, Durham, Matthew, additional, Fujita, Kyouichi, additional, Guardincerri, Elena, additional, Izumi, Mikio, additional, Kume, Naoto, additional, Nakayama, Kohichi, additional, Saltus, Mark, additional, Sudo, Kazuo, additional, Sugita, Tsukasa, additional, Takakura, Kei, additional, and Yoshioka, Kenichi, additional

Published
2015
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47. Void reactivity evaluation by modified conversion ratio measurements in LWR critical experiments

Author

Yoshioka, Kenichi, primary, Kikuchi, Tsukasa, additional, Gunji, Satoshi, additional, Kumanomido, Hironori, additional, Mitsuhashi, Ishi, additional, Umano, Takuya, additional, Yamaoka, Mitsuaki, additional, Okajima, Shigeaki, additional, Fukushima, Masahiro, additional, Nagaya, Yasunobu, additional, Mori, Takamasa, additional, Kitada, Takanori, additional, and Takeda, Toshikazu, additional

Published
2014
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48. Cosmic-Ray Muon Imaging of Fukushima Daiichi

Author

Miyadera, Haruo, primary, Morris, Christopher, additional, Bacon, Jeffery D., additional, Borozdin, Konstantin N., additional, Fujita, Kyouichi, additional, Kume, Naoto, additional, Mizokami, Shinya, additional, Nakayama, Kohichi, additional, Otsuka, Yasuyuki, additional, Perry, John O., additional, Sano, Yuji, additional, Sugita, Tsukasa, additional, Takakura, Kei, additional, Yamada, Daichi, additional, and Yoshioka, Kenichi, additional

Published
2014
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49. Cosmic-ray muon radiography of UO2fuel assembly

Author

Sugita, Tsukasa, primary, Bacon, Jeffery, additional, Ban, Yuichiro, additional, Borozdin, Konstantin, additional, Izumi, Mikio, additional, Karino, Yoshiji, additional, Kume, Naoto, additional, Miyadera, Haruo, additional, Mizokami, Shinya, additional, Morris, Christopher L., additional, Nakayama, Kohichi, additional, Otsuka, Yasuyuki, additional, Perry, John O., additional, Ramsey, John, additional, Sano, Yuji, additional, Yamada, Daichi, additional, Yoshida, Noriyuki, additional, and Yoshioka, Kenichi, additional

Published
2014
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