検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

In-situ SCC observation of thermally-sensitized and cold-worked type 304 stainless steel irradiated to a neutron fluence of 1$$times$$10$$^{25}$$n/m$$^{2}$$

熱鋭敏化済及び冷間加工済で中性子照射量1$$times$$10$$^{25}$$n/m$$^{2}$$まで照射した304ステンレス鋼におけるその場SCC観察

中野 純一; 根本 義之; 三輪 幸夫; 宇佐美 浩二; 塚田 隆; 秀 耕一郎*

Nakano, Junichi; Nemoto, Yoshiyuki; Miwa, Yukio; Usami, Koji; Tsukada, Takashi; Hide, Koichiro*

照射誘起応力腐食割れにおけるき裂発生及び進展過程を酸素添加した561Kの高温水中での低ひずみ速度試験により調べた。同時に試験片表面のその場観察を行った。304ステンレス鋼の試験片に固溶体化,熱鋭敏化及び冷間加工を施し、材料試験炉(JMTR)の323Kの炉水中で1.0$$times$$10$$^{25}$$n/m$$^{2}$$(E$$>$$1MeV)まで照射した。照射量1.0$$times$$10$$^{26}$$n/m$$^{2}$$の冷間加工材では最大応力到達直後に割れの発生が見られたが、照射量1.0$$times$$10$$^{25}$$n/m$$^{2}$$の冷間加工材では最大応力に到達する前に割れの発生が観察された。破面観察では、熱鋭敏化材ではほぼ全面で粒界型応力腐食割れを示し、固溶体化材及び冷間加工材では粒内型応力腐食割れと延性を示すディンプルの混在する破面が認められた。

Crack initiation and crack growth processes of irradiation assisted stress corrosion cracking on stainless steels were studied by slow strain rate testing in oxygenated high temperature water at 561 K. In-situ observation was carried out during SSRT. Specimens of type 304 stainless steel were subjected to a solution annealing (SA), a thermally sensitization (TS), or a cold working (CW) and irradiated to 1.0$$times$$10$$^{25}$$ n/m$$^{2}$$ (E $$>$$ 1 MeV) at 323 K in the Japan Material Testing Reactor (JMTR). Crack initiations were observed before the maximum stress would be reached for the CW material in in-situ observation. In fracture surface examination, the TS material exhibited almost intergranular stress corrosion cracking while mixtures of transgranular stress corrosion cracking and ductile dimple fracture were observed for the SA and the CW materials.

Access

:

- Accesses

InCites™

:

パーセンタイル:72.57

分野:Materials Science, Multidisciplinary

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.