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Featured researches published by Eisaku Hayashi.


Nuclear Engineering and Design | 1993

Welding residual stresses at the intersection of a small diameter pipe penetrating a thick plate

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

Guideline of Weld Overlay Repair Method for Primary Piping of Japanese Boiling Water Reactors

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

Generation of welding residual stress when a pipe penetrates a thick plate

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

Underwater laser processing device including chamber with partitioning wall

Keiichi Uraki; Toshitaka Satsuta; Akira Onuma; Mitsuo Nakamura; Tsutomu Onuma; Toshimi Matsumoto; Yasumasa Tamai; Hiroshi Yamauchi; Eisaku Hayashi; Ren Morinaka


Archive | 1996

Fluid jet nozzle and stress improving treatment method using the nozzle

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

X-Ray Study on Deformation and Fracture of Solid. Effects of Water Jet Peening on Corrosion Resistance and Fatigue Strength of Type 304 Stainless Steel.

Katsuhiko Hirano; Kunio Enomoto; Eisaku Hayashi; Koichi Kurosawa


Archive | 1999

Preventive maintenance apparatus for structural members in a nuclear pressure vessel

Koichi Kurosawa; Eisaku Hayashi; Sadato Shimizu; Minoru Ootaka; Fujio Yoshikubo; Ren Morinaka; Masayuki Nishino; Noboru Chiba; Kunio Enomoto; Kazunori Sato


Archive | 2002

Water jet peening apparatus

Katsuhiko Hirano; Kunio Enomoto; Eisaku Hayashi; Sadato Shimizu; Ren Morinaka; Tetsuya Ishikawa; Shigeru Tanaka; Noboru Chiba


Archive | 2013

Preventive maintenance method and apparatus of a structural member in a reactor pressure vessel

Kunio Enomoto; Katsuhiko Hirano; Eisaku Hayashi; Ren Morinaka; Sadato Shimizu; Satoshi Kanno; Shigeru Tanaka; Tetsuya Ishikawa


Nuclear Engineering and Design | 2009

Stress corrosion cracking countermeasure observed on Ni-based alloy welds of BWR core support structure

Wataru Sagawa; Takayuki Aoki; Takashi Itou; Kunio Enomoto; Eisaku Hayashi; Tetsuya Ishikawa

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