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Yamamoto, Masahiro; Kato, Chiaki; Sato, Tomonori; Nakano, Junichi; Ugachi, Hirokazu; Tsukada, Takashi; Kaji, Yoshiyuki; Tsujikawa, Shigeo*; Hattori, Shigeo*; Yoshii, Tsuguyasu*; et al.
JAEA-Review 2012-007, 404 Pages, 2012/03
There are many LWRs which have been operated for more than 20 years in Japan and it is expected that technique corresponding to aging plants are necessary established for safety operation in LWRs. A lot of troubles related to SCC are reported and many investigations are concerned with SCC mechanism and technical evaluation. In this paper, those research data were collected as possible widely and reviewed systematically. Current circumstances concerned with SCC in LWRs were reviewed specifically as follows: SCC incidents, SCC evaluation methods for crack initiation and propagation, the investigations concerned with SCC mechanism and monitoring technique for corrosive environment. Influences with reactor types (BWR, PWR), materials (stainless steels, Ni alloys) and SCC evaluating methods (laboratories and actual plants) were summarized as graphs and tables easy to understand in common/difference points concerned with SCC. From these arranged results, future themes were considered and remarked SCC phenomenon was summarized in actual plants. As for SCC evaluations under the accelerate conditions in the laboratory test, it was suggested that a computational prediction and modeling including statistical technique and microscopic analysis in crack initiation were important. Furthermore it was suggested that monitoring techniques predicting SCC initiation and grasping plant circumstance in operation and feasibility in actual plants were important.
Tsujikawa, Shigeo*; *; *; Tsuru, Toru*; Shibata, Toshio*; *
PNC TJ1560 98-001, 164 Pages, 1998/02
None
Tsujikawa, Shigeo*; *; *; Tsuru, Toru*; Shibata, Toshio*; *
PNC TJ1560 97-001, 210 Pages, 1997/03
None
Kato, Chiaki; Yamamoto, Masahiro; Tsujikawa, Shigeo*; Hattori, Shigeo*; Yoshii, Tsuguyasu*; Kudo, Takeo*; Nemoto, Rikio*; Akashi, Masatsune*
no journal, ,
There are many LWRs which have been operated for more than 20 years in Japan and it is expected that technique corresponding to aging plants are necessary established for safety operation in LWRs. A lot of troubles related to SCC are reported and many investigations are concerned with SCC mechanism and technical evaluation. In this paper, those research data were collected as possible widely and reviewed systematically. Current circumstances concerned with SCC in LWRs were reviewed specifically as follows: SCC incidents, SCC evaluation methods for crack initiation and propagation, the investigations concerned with SCC mechanism and monitoring technique for corrosive environment. Influences with reactor types (BWR, PWR), materials (stainless steels, Ni alloys) and SCC evaluating methods (laboratories and actual plants) were summarized as graphs and tables easy to understand in common/difference points concerned with SCC. From these arranged results, future themes were considered and remarked SCC phenomenon was summarized in actual plants.
Sato, Tomonori; Yamamoto, Masahiro; Omori, Chihiro*; Nomura, Masahiro; Tsujikawa, Shigeo*; Ogawa, Hiroyuki*; Nakajima, Hiroshi*
no journal, ,
The RF cavities used in J-PARC are heated by the applied current, and they are cooled by the circulating water. The RF cavities were made by a magnetic alloy. The corrosion of the RF cavities was observed. The analyses of the corrosion was performed. As a result, the contribution of the copper ions to the corrosion of RF cavity was confirmed. And the 40 m/year of corrosion rate was estimated in copper ion free condition.