Eisaku Hayashi
Hitachi
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Featured researches published by Eisaku Hayashi.
Nuclear Engineering and Design | 1993
Masahito Mochizuki; Kunio Enomoto; Noriaki Okamoto; Hideyo Saito; Eisaku Hayashi
Abstract This paper investigates welding residual stresses at the juncture of a small diameter pipe penetrating a thick plate. The pipe is welded to the plate, and TIG cladding is melted on the inner surface of the pipe to protect it from stress corrosion cracking due to environmentally-induced changes in nuclear power plant components. Welding residual stresses are calculated by heat conduction and thermal elastoplastic analyses using an assumption of “simplified pass” to save the computing time, and are also measured by the strain-relief technique. Welding residual stresses after TIG cladding are shown to have no corrosive influence on the inner pipe surface, and the residual stresses are compressive enough to protect the pipe against stress corrosion cracking on the outer surface.
ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference | 2006
Haruo Fujimori; Eisaku Hayashi; Yuichi Motora; Hitoshi Ohata; Hideo Sakurai
A private guideline of a weld overlay (WOL) repair method for SCC cracked Boiling Water Rector (BWR) primary piping was provided by Thermal and Nuclear Power Engineering Society of Japan. In the WOL method, the overlaid structure of SCC resistant 308L weld metal substitutes for cracked existing piping weldments as pressure boundary. The guideline prescribes the applicability, welding conditions and essential variables, weld overlay structural design, evaluation of welding effects to the piping system, in-process control, post-process examination, and procedures of pre-service and in-service inspection.Copyright
Welding International | 1995
Masahito Mochizuki; Kunio Enomoto; Noriaki Okamoto; Hideyo Saito; Eisaku Hayashi
Summary This paper describes a study of the welding residual stress at the intersection of a small‐diameter pipe penetrating a thick plate. The pipe is welded to the plate, and TIG cladding is deposited on its inside surface to protect it from stress corrosion cracking due to prolonged operation in a nuclear power plant. The residual stress is calculated by a heat conduction analysis and tensile elastic‐plastic analysis and also measured by strain gauges. The welding residual stress is shown to have no corrosive effect on the pipe inside surface, and the stress is sufficiently compressive to protect the pipe from stress corrosion cracking on its outside surface. The mechanism of residual stress generation during welding is also investigated.
Archive | 1995
Keiichi Uraki; Toshitaka Satsuta; Akira Onuma; Mitsuo Nakamura; Tsutomu Onuma; Toshimi Matsumoto; Yasumasa Tamai; Hiroshi Yamauchi; Eisaku Hayashi; Ren Morinaka
Archive | 1996
Kunio Enomoto; Katsuhiko Hirano; Masahiro Otaka; Kazuo Amano; Eisaku Hayashi; Sadato Shimizu; Ren Morinaka; Kazunori Sato
Journal of The Society of Materials Science, Japan | 1996
Katsuhiko Hirano; Kunio Enomoto; Eisaku Hayashi; Koichi Kurosawa
Archive | 1999
Koichi Kurosawa; Eisaku Hayashi; Sadato Shimizu; Minoru Ootaka; Fujio Yoshikubo; Ren Morinaka; Masayuki Nishino; Noboru Chiba; Kunio Enomoto; Kazunori Sato
Archive | 2002
Katsuhiko Hirano; Kunio Enomoto; Eisaku Hayashi; Sadato Shimizu; Ren Morinaka; Tetsuya Ishikawa; Shigeru Tanaka; Noboru Chiba
Archive | 2013
Kunio Enomoto; Katsuhiko Hirano; Eisaku Hayashi; Ren Morinaka; Sadato Shimizu; Satoshi Kanno; Shigeru Tanaka; Tetsuya Ishikawa
Nuclear Engineering and Design | 2009
Wataru Sagawa; Takayuki Aoki; Takashi Itou; Kunio Enomoto; Eisaku Hayashi; Tetsuya Ishikawa