Koreyuki Shiba

发表

Studies of Ceramic Fuels with Use of Fission Gas Release Loop, (IV): Fission Gas Release from Uranium Carbide in the Presence of Trace Amounts of Water Vapor

Shigeru Yamagishi, Muneo Handa, Takaaki Tanifuji, 1974 .

Methods and Devices for Small Specimen Testing at the Japan Atomic Energy Research Institute

Shiro Jitsukawa, S. Jitsukawa, A. Hishinuma, 1993 .

Evaluation of irradiation assisted stress corrosion cracking (IASCC) of type 316 stainless steel irradiated in FBR

Hajime Nakajima, Takashi Tsukada, I. Shibahara, 1993 .

Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication

Mikio Enoeda, Takanori Hirose, Masato Akiba, 2006 .

Studies of Ceramic Fuels with Use of Fission Gas Release Loop, (IV)

Shigeru Yamagishi, Muneo Handa, Takaaki Tanifuji, 2012 .

Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H

Akira Kohyama, Ronald L. Klueh, G. R. Odette, 2002 .

Transient fuel behavior of preirradiated PWR fuels under reactivity initiated accident conditions

Kazuaki Yanagisawa, Toshio Fujishiro, Kiyomi Ishijima, 1992 .

Effects of heat treatment process for blanket fabrication on mechanical properties of F82H

Masato Akiba, Shiro Jitsukawa, S. Jitsukawa, 2004 .

Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effects studies

Mikhail A. Sokolov, Naoyuki Hashimoto, Ronald L. Klueh, 2006 .

Reduced activation martensitic steels as a structural material for ITER test blanket

Mikio Enoeda, Shiro Jitsukawa, S. Jitsukawa, 2004 .