KAJI Yoshiyuki | Japan Atomic Energy Research Institute
スポンサーリンク
概要
関連著者
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KAJI Yoshiyuki
Japan Atomic Energy Research Institute
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Kaji Yoshiyuki
Japan Atomic Energy Agency
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TSUJI Hirokazu
Japan Atomic Energy Research Institute
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TAKIGUCHI Hideki
Japan Atomic Power Co.
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TSUKADA Takashi
Japan Atomic Energy Agency
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Takiguchi Hideki
Japan Atomic Power Company
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Matsui Yoshinori
Japan Atomic Energy Agency
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Komori Yoshihiro
Japan Atomic Energy Agency
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Kaji Yoshiyuki
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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NAGATA Nobuaki
Japan Atomic Power Company
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DOZAKI Koji
Japan Atomic Power Company
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Tsukada Takashi
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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Schubert Florian
Forschungszentrum Juelich Gmbh
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Penkalla H‐j
Forschungszentrum Juelich Gmbh
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Nishi H
Japan Nuclear Cycle Dev. Inst. Fukui
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NISHI Hiroshi
Japan Atomic Energy Research Institute
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MUTO Yasushi
Japan Atomic Energy Research Institute
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Penkalla Heinz
Forschungszentrum Juelich Gmbh
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Penkalla Heinz-josef
Forschungszentrum Julich Gmbii. Fz
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UGACHI Hirokazu
Japan Atomic Energy Agency
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OHMI Masao
Japan Atomic Energy Agency
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Tsuji Hirokazu
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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Kikuchi Kenji
Japan Atomic Research Institute
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PENKALLA Heinz-Josef
Forschungszentrum Julich GmbH, KFA
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Shibata Akira
Japan Aerospace Exploration Agency (jaxa) Tsukuba‐shi Jpn
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PENKALLA Heinz
Forschungszentrum Juelich GmbH (J)
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Nakano Junichi
Japan Atomic Energy Agency
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Penkalla Heinz-josef
Forschungszentrum Juelich Gmbh
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KAWAMATA Kazuo
Japan Atomic Energy Agency
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KITA Satoshi
Japan Atomic Energy Research Institute (JAERI)
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Kikuchi Kenji
Japan Atomic Energy Agency
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Shibata Akira
Japan Atomic Energy Agency
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Tsukuda Takashi
Japan Atomic Energy Agency
著作論文
- Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures
- SB-02-2(075) Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures(Materials Performance in Nuclear Application 2)
- In-Core SCC Growth Behavior of Type 304 Stainless Steel in BWR Simulated High-Temperature Water at JMTR
- ICONE11-36136 Program of in-pile IASCC testing under the simulated actual plant condition : Development of Technique for In-pile IASCC Initiation Test in JMTR
- ICONE11-36119 PROGRAM OF IN-PILE IASCC TESTING UNDER THE SIMULATED ACTUAL PLANT CONDITION : Development of technique for in-pile IASCC growth test in JMTR
- SB-03-3(074) Inelastic Constitutive Equation in Alloy800H(Materials Performance in Nuclear Application 3)