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Omer, M.; Shizuma, Toshiyuki*; Koizumi, Mitsuo; Taira, Yoshitaka*; Zen, H.*; Ogaki, Hideaki*; Hajima, Ryoichi
UVSOR-50, P. 37, 2023/08
no abstracts in English
Taira, Yoshitaka*; Endo, Shunsuke; Kawamura, Shiori*; Nambu, Taro*; Okuizumi, Mao*; Shizuma, Toshiyuki*; Omer, M.; Zen, H.*; Okano, Yasuaki*; Kitaguchi, Masaaki*
Physical Review A, 107(6), p.063503_1 - 063503_10, 2023/06
Times Cited Count：0 Percentile：0.01(Optics)no abstracts in English
Endo, Shunsuke; Shizuma, Toshiyuki*; Zen, H.*; Taira, Yoshitaka*; Omer, M.; Kawamura, Shiori*; Abe, Ryota*; Okudaira, Takuya*; Kitaguchi, Masaaki*; Shimizu, Hirohiko*
UVSOR-49, P. 38, 2022/08
Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Al
GaO
scintillators by gamma-ray-induced positron annihilation lifetime spectroscopyFujimori, Kosuke*; Kitaura, Mamoru*; Taira, Yoshitaka*; Fujimoto, Masaki*; Zen, H.*; Watanabe, Shinta*; Kamada, Kei*; Okano, Yasuaki*; Kato, Masahiro*; Hosaka, Masahito*; et al.
Applied Physics Express, 13(8), p.085505_1 - 085505_4, 2020/08
Times Cited Count：5 Percentile：33.01(Physics, Applied)To clarify the existence of cation vacancies in Ce-doped GdAlGaO (Ce:GAGG) scintillators, we performed gamma-ray-induced positron annihilation lifetime spectroscopy (GiPALS). GiPAL spectra of GAGG and Ce:GAGG comprised two exponential decay components, which were assigned to positron annihilation at bulk and defect states. By an analogy with Ce:YAl
O, the defect-related component was attributed to Al/Ga-O divacancy complexes. This component was weaker for Ce, Mg:GAGG, which correlated with the suppression of shallow electron traps responsible for phosphorescence. Oxygen vacancies were charge compensators for Al/Ga vacancies. The lifetime of the defect-related component was significantly changed by Mg co-doping. This was understood by considering aggregates of Mg
ions at Al/Ga sites with oxygen vacancies, which resulted in the formation of vacancy clusters.
Mori, Takero; Ohira, Hiroaki; Sotsu, Masutake; Fukano, Yoshitaka
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 9 Pages, 2017/04
Since safety measures against severe accidents (SAs) such as a long-term station blackout (SBO) are required for Japanese prototype fast breeder reactor Monju, a validation is necessary for the plant dynamics code during SBO. In order to take into account the phenomena in natural circulation: a heat transfer among subassemblies and a flow redistribution, a whole core model has been developed for the plant dynamics code, Super-COPD. This model has been validated by test results of natural circulation in actual facility. In this study, this whole core model was applied to Monju core to evaluate safety measures against SBO, and the pressure loss model of Monju was validated by comparing with results of the plant trip test from the power of 40%. In addition, an analysis was conducted for SBO to investigate the applicability of this model to Monju. The applicability of this model was confirmed by comparing with analytical results using the model without heat transfer between assemblies.
Ueta, Shohei; Inoi, Hiroyuki; Mizutani, Yoshitaka; Ohashi, Hirofumi; Iwatsuki, Jin; Sakaba, Nariaki; Sawa, Kazuhiro
Proceedings of 21st International Conference on Nuclear Engineering (ICONE-21) (DVD-ROM), 4 Pages, 2013/07
Japan Atomic Energy Agency (JAEA) has planned to investigate on iodine release behavior from fuel through the testing operation of High Temperature Engineering Test Reactor (HTTR) in order to contribute to the reasonable estimation of the radiation exposure necessary for the realization of HTGR in the future. In this test, the fractional release of iodine will be measured and evaluated by measuring xenon isotopes, the daughter nuclides of iodine isotopes, in the primary coolant sampling under the loss-of-forced cooling (LOFC) test by which the primary coolant circulator is shut down and/or the manual scram test of HTTR. In parallel, the local area of primary coolant circuit where iodine is plated-out will be evaluated. This paper describes the testing plan and the preliminary analytical study on the release behavior of iodine and xenon isotopes through the operation of HTTR.
Yokobori, Shinichi*; Yang, Y.*; Fujisaki, Kenta*; Kawaguchi, Yuko*; Kobayashi, Kensei*; Hashimoto, Hirofumi*; Kawai, Hideyuki*; Mita, Hajime*; Narumi, Issei; Okudaira, Kyoko*; et al.
no journal, ,
no abstracts in English
Yokobori, Shinichi*; Yang, Y.*; Fujisaki, Kenta*; Kawaguchi, Yuko*; Hashimoto, Hirofumi*; Yamashita, Masamichi*; Yano, Hajime*; Okudaira, Kyoko*; Yoshimura, Yoshitaka*; Narumi, Issei; et al.
no journal, ,
no abstracts in English
Yokobori, Shinichi*; Fujisaki, Kenta*; Kawaguchi, Yuko*; Yang, Y.*; Fushimi, Hidehiko*; Hashimoto, Hirofumi*; Yamashita, Masamichi*; Yano, Hajime*; Okudaira, Kyoko*; Hayashi, Nobuhiro*; et al.
no journal, ,
no abstracts in English
Yokobori, Shinichi*; Yang, Y.*; Sugino, Tomohiro*; Kawaguchi, Yuko*; Itahashi, Shiho*; Fujisaki, Kenta*; Fushimi, Hidehiko*; Hasegawa, Sunao*; Hashimoto, Hirofumi*; Hayashi, Nobuhiro*; et al.
no journal, ,
Yokobori, Shinichi*; Yang, Y.*; Sugino, Tomohiro*; Kawaguchi, Yuko*; Fushimi, Hidehiko*; Narumi, Issei; Hashimoto, Hirofumi*; Hayashi, Nobuhiro*; Kawai, Hideyuki*; Kobayashi, Kensei*; et al.
no journal, ,
Kawaguchi, Yuko*; Sugino, Tomohiro*; Yang, Y.*; Takahashi, Yuta*; Yoshimura, Yoshitaka*; Tsuji, Takashi*; Kobayashi, Kensei*; Tabata, Makoto*; Hashimoto, Hirofumi*; Narumi, Issei; et al.
no journal, ,
no abstracts in English
Yokobori, Shinichi*; Yang, Y.*; Kawaguchi, Yuko*; Sugino, Tomohiro*; Takahashi, Yuta*; Narumi, Issei; Takahashi, Yuichi*; Hayashi, Nobuhiro*; Yoshimura, Yoshitaka*; Tabata, Makoto*; et al.
no journal, ,
no abstracts in English
Sugino, Tomohiro*; Yokobori, Shinichi*; Yang, Y.*; Kawaguchi, Yuko*; Hasegawa, Sunao*; Hashimoto, Hirofumi*; Imai, Eiichi*; Okudaira, Kyoko*; Kawai, Hideyuki*; Tabata, Makoto*; et al.
no journal, ,
Yokobori, Shinichi*; Yang, Y.*; Sugino, Tomohiro*; Kawaguchi, Yuko*; Takahashi, Yuta*; Narumi, Issei; Hashimoto, Hirofumi*; Hayashi, Nobuhiro*; Imai, Eiichi*; Kawai, Hideyuki*; et al.
no journal, ,
Ueta, Shohei; Aihara, Jun; Mizutani, Yoshitaka; Ohashi, Hirofumi; Sakaba, Nariaki; Tachibana, Yukio; Honda, Masaki*; Tanaka, Hideki*; Furihata, Noboru*
no journal, ,
In the small-sized high temperature gas-cooled reactor, the improved fuel of which the burnup is designed over 100 GWd/t is used in order to upgrade economy and to decrease radioactive waste. On the other hand, to attain over three times higher burnup than that of a conventional HTTR fuel, 33 GWd/t, researches and developments of the fuel should be needed with regards to the design preventing the fuel from the failure by internal pressure due to gases in the coated fuel particle, the technologies for fabrication of the improved fuel, and the irradiation test to confirm its integrity under the irradiation. A design work, fabrication tests and a plan of the irradiation test for the improved fuel in order to demonstrate the performance are reported.
Ueta, Shohei; Aihara, Jun; Mizutani, Yoshitaka; Ohashi, Hirofumi; Sakaba, Nariaki; Tachibana, Yukio; Kunitomi, Kazuhiko
no journal, ,
Clean Burn High Temperature Gas-cooled Reactor (CBHTR) is loaded with the coated fuel particle having a fuel kernel made with solid solution of plutonium dioxide (PuO) and yttrium stabilized zirconia (YSZ) as the inert matrix. To establish the fundamental technique of fabrication of PuO-YSZ coated fuel particle, research plans on fabrications of the fuel kernel by sol-gel process and of multi-ceramics coatings by chemical vapor deposition are reported.
Ueta, Shohei; Mizutani, Yoshitaka; Sakaba, Nariaki; Furihata, Noboru*; Honda, Masaki*; Asset, S.*; Gizatulin, S.*; Chakrov, P.*
no journal, ,
A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel by WWR-K in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) is being carried out. The HTGR fuel specimens were newly designed at the target burnup of 100 GWd/t. A plan of the irradiation test and results on evaluation of the integrity of the HTGR fuel specimen based on fission gas (FP) release rate under the irradiation are reported.
Mori, Takero; Ohira, Hiroaki; Sotsu, Masutake; Fukano, Yoshitaka
no journal, ,
In order to evaluate the availability of the decay heat removal by natural circulation which is a measure for the Protected Loss of Heat Sink (PLOHS) in Fast Reactor, a whole core model which could simulate thermal hydraulics of each subassembly in a reactor was applied to Monju core. The Monju core model was validated by a test result of actual plant, MONJU. In addition, an analysis was conducted for PLOHS to investigate the applicability of this model.
