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Journal Articles

Stress corrosion cracking of copper in swollen bentonite simulating nuclear waste disposal environment

Fujimoto, Shinji*; Tsuchiya, Hiroaki*; Ogawa, Soma*; Iida, Yoshihisa; Taniguchi, Naoki

Materials and Corrosion, 72(1-2), p.333 - 338, 2021/01

 Times Cited Count:2 Percentile:13.1(Materials Science, Multidisciplinary)

The stress corrosion cracking (SCC) of pure copper in bentonite was examined by a slow strain rate test (SSRT). The bentonite was swollen with pure water or aqueous solutions containing NH$$_{3}$$ of 0.05 M and 0.1 M. The thick corrosion films and particulate deposits were formed on copper surface after SSRT. Typical tarnish rupture type SCC occurred on pure copper in swollen bentonite with and without NH$$_{3}$$. Crack propagation rate was enhanced by NH$$_{3}$$. It is confirmed thick oxide layer is formed on copper during plastic deformation which resulting in the tarnish crack type SCC. The many particulate deposits observed on the surface might be formed as a results of rapid dissolution of Cu$$^{2+}$$ to form porous CuO at locallized deformed sites.

JAEA Reports

Feasibility Study on Commercialization of Fast Breeder Reactor Cycle Systems Interim Report of Phase II; Technical Study Report for Reactor Plant Systems

Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.

JNC TN9400 2004-035, 2071 Pages, 2004/06

JNC-TN9400-2004-035.pdf:76.42MB

The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.

Oral presentation

Stress corrosion cracking of Cu via turnish rupture in wet bentonite

Nishioka, Tsuyoshi*; Ogawa, Soma*; Tsuchiya, Hiroaki*; Fujimoto, Shinji*; Taniguchi, Naoki; Dobashi, Ryuta*

no journal, , 

no abstracts in English

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