Zobrazeno 1 - 10 of 25 pro vyhledávání: '"Kimihiko Yano"'
1
Chemical forms of uranium evaluated by thermodynamic calculation associated with distribution of core materials in the damaged reactor pressure vessel
Autor: Hirotomo Ikeuchi, Tadahiro Washiya, Kimihiko Yano
Publikováno v: Journal of Nuclear Science and Technology. 57:704-718
To suggest efficient process of the fuel debris treatment after the retrieval from the Fukushima Daiichi Nuclear Power Plant (1F), thorough investigation is indispensable on potential source of U in the fuel debris. The present study aims to estimate
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a0ecfb21253d9558455fac581c59f283
https://doi.org/10.1080/00223131.2020.1720844
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2
急冷による溶融燃料とコンクリートの反応生成物への影響評価
Autor: Hirotomo Ikeuchi, Julien Roger, Toru Kitagaki, Brigitte Tormos, Renaud Domenger, Laurent Brissonneau, Kimihiko Yano, Tadahiro Washiya
Publikováno v: Journal of Nuclear Science and Technology. 56(9-10):902-914
Characterization of fuel debris is required to develop fuel debris removal tools. Especially, knowledge pertaining to the characteristics of molten core-concrete interaction (MCCI) product is needed because of the limited information available at pre
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::26fa2fdc469a7234d9ca144aa9703be5
https://jopss.jaea.go.jp/search/servlet/search?5064018
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3
Microparticles with diverse sizes and morphologies from mechanical and laser cutting of fuel debris simulants and geopolymer as a covering material
Autor: Seiya Suzuki, Shunichi Suzuki, Kimihiko Yano, Qian Zhou, Takumi Saito
During the decommissioning of Fukushima Daiichi nuclear power plant, the dismantling of massive fuel debris is important for the defueling process. The production and dispersion of radioactive microparticles highly depends on the cutting technique im
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::796895f029062cfc83fc1e145566e32d
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6
福島第一原子力発電所の推定条件における溶融炉心-コンクリート凝固相の熱力学評価
Autor: Tadahiro Washiya, Hideki Ogino, Toru Kitagaki, Kimihiko Yano
Publikováno v: Journal of Nuclear Materials. 486:206-215
The solidification phases of molten core–concrete under the estimated molten core–concrete interaction (MCCI) conditions in the Fukushima Daiichi Nuclear Power Plant Unit 1 were predicted using the thermodynamic equilibrium calculation tool, Fact
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e9a30f5659f5f7fba44aafd4ff57f547
https://jopss.jaea.go.jp/search/servlet/search?5057304
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7
Mechanical Properties of Cubic (U,Zr)O2
Autor: Tetsuo Fukasawa, Toru Kitagaki, Nobuo Okamura, Kenji Koizumi, Kimihiko Yano, Hiroshi Ohara, Takanori Hoshino
Publikováno v: Journal of Nuclear Engineering and Radiation Science. 4
Evaluation of fuel debris properties in the Fukushima Daiichi nuclear power plant (1F) is required to develop fuel debris removal tools. In the removal of debris resulting from the Three Mile Island unit 2 (TMI-2) accident, a core-boring system playe
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e19b61a294212b82ada9cfef348c9d56
https://doi.org/10.1115/1.4039847
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8
Purification of uranium products in crystallization system for nuclear fuel reprocessing
Autor: Yuji Sanbonmatsu, Atsuhiro Shibata, Kimihiko Yano, Izumi Hirasawa, Takahiro Chikazawa, Kazuhito Nakamura, Masayuki Takeuchi
Publikováno v: Journal of Nuclear Science and Technology. 53:521-528
Uranium crystallization system has been developed to establish an advanced aqueous reprocessing for fast breeder reactor (FBR) fuel cycle. In the crystallization system, most part of uranium in dissolved solution of spent FBR-MOX fuels is separated a
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2a5c47598aa04897557c6102ea4f6aed
https://doi.org/10.1080/00223131.2015.1060907
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9
Dissolution behavior of (U,Zr)O2-based simulated fuel debris in nitric acid
Autor: Yasuo Nakajima, Naoya Kaji, Miho Ishihara, Kimihiko Yano, Tadahiro Washiya, Hirotomo Ikeuchi
Publikováno v: Journal of Nuclear Science and Technology. 51:996-1005
To explore the possibility of dissolving fuel debris into nitric acid as a potential pre-treatment for waste treatment in which the U and Pu are removed from the inventory, dissolution tests of U1−...
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1052bdd0772b13a46a742ba8a837d203
https://doi.org/10.1080/00223131.2014.924445
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