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Kaji, Yoshiyuki
Proceedings of KNS-AESJ Joint Summer School 2005 for Students and Young Researchers, 2, p.221 - 228, 2005/08
For core internals, the main research items are intergranular stress corrosion cracking (IGSCC) of low carbon stainless steel in core shrouds and primary loop recirculation pipes in boiling water reactor (BWR), and irradiation assisted stress corrosion cracking (IASCC) which is caused by the synergistic effects of neutron and gamma-ray radiation, corrosion by high temperature water, and the residual and/or applied stresses. This paper describes the current status and typical results of fundamental study for mechanistic understanding of IGSCC and IASCC, development of IASCC evaluation technology for BWR plants based on post-irradiation IASCC test data as a part of METI's national project, in-pile IASCC tests.
Nakano, Junichi; Koya, Toshio; Endo, Shinya; Ugachi, Hirokazu; Tsuji, Hirokazu; Tsukada, Takashi
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), P. 56, 2003/00
Irradiation assisted stress corrosion cracking (IASCC) is one of the key issues for the life management of light water reactor (LWR) core components. For understanding IASCC phenomenon, a slow stain rate testing (SSRT) facility with a capability for in-situ observation in high temperature water for irradiated materials was developed. The SSRT facility has an autoclave with a window for in-situ observation and has been designed for SSRT under boiling water reactor (BWR) condition. To simulate normal water chemistry (NWC) and hydrogen water chemistry (HWC) of BWR environment, dissolved oxygen and hydrogen concentrations (DO and DH) can be controlled within the range of 10 ppb to 32 ppm and 10 ppb to 2.8 ppm, respectively. Hydrogen peroxide can be injected into the autoclave to simulate the radiolysis of water in the reactor core. As a trial run, in-situ observation for an unirradiated material during tensile test in water at 561K was performed and it was confirmed that the load-elongation curve and images could be obtained successfully.
HTTR Utilization Research Committee
JAERI-Review 2001-016, 232 Pages, 2001/05
JAERI-Review-2001-016.pdf:12.01MB
no abstracts in English
Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi
JAERI-Research 2001-009, 21 Pages, 2001/03
JAERI-Research-2001-009.pdf:2.93MB
no abstracts in English
Nagase, Fumihisa; Uetsuka, Hiroshi;
JAERI-Research 95-085, 48 Pages, 1995/11
JAERI-Research-95-085.pdf:2.67MB
no abstracts in English
