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Effects of temperature on stress corrosion cracking behavior of stainless steel and outer oxide distribution in cracks due to exposure to high-temperature water containing hydrogen peroxide

過酸化水素を含む高温水に曝したことによるステンレス鋼の応力腐食割れ及びき裂の外層酸化物分布に及ぼす温度の影響

中野 純一; 佐藤 智徳; 加藤 千明; 山本 正弘; 塚田 隆; 加治 芳行

Nakano, Junichi; Sato, Tomonori; Kato, Chiaki; Yamamoto, Masahiro; Tsukada, Takashi; Kaji, Yoshiyuki

沸騰水型原子炉(BWR)の運転温度よりも低い温度において、ステンレス鋼(SS)の応力腐食割れ(SCC)に及ぼす過酸化水素(H$$_{2}$$O$$_{2}$$)の影響を評価するため、H$$_{2}$$O$$_{2}$$を含む561$$sim$$423Kの高温水中でき裂進展試験を行った。小型コンパクト・テンション(CT)試験片を熱鋭敏化304SSから作製した。100ppbのH$$_{2}$$O$$_{2}$$を含む561Kの高温水中での試験では、CT試験片のサイドグルーブ近傍に粒界型SCC(IGSCC)の小さな領域が認められたにもかかわらず、423及び453KではCT試験片の中央部までIGSCC領域が拡大した。SCCに及ぼすH$$_{2}$$O$$_{2}$$の影響はBWR運転温度よりも低い温度で著しく現れた。き裂中の環境を評価するため、破面及び疲労予き裂上の外層酸化物分布をレーザーラマン分析により調べるとともに熱平衡計算を行った。

Cracking growth tests were conducted in high-temperature water containing hydrogen peroxide (H$$_{2}$$O$$_{2}$$) at 561 to 423 K to evaluate the effects of H$$_{2}$$O$$_{2}$$ on stress corrosion cracking (SCC) of stainless steel (SS) at temperature lower than the boiling water reactor (BWR) operating temperature. Small compact tension (CT) specimens were prepared from thermally sensitized type 304 SS. Despite the observation of only a small portion intergranular SCC (IGSCC) near the side groove of the CT specimen at 561 K in high-temperature water containing 100 ppb of H$$_{2}$$O$$_{2}$$, the IGSCC area expanded to the central region of the CT specimens at 423 and 453 K. Effects of H$$_{2}$$O$$_{2}$$ on SCC appeared intensely at temperature lower than the BWR operating temperature. To estimate the environment in the cracks, outer oxide distribution on the fracture surface and fatigue pre-crack were examined by laser Raman spectroscopy and thermal equilibrium calculation was performed.

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パーセンタイル:100

分野:Materials Science, Multidisciplinary

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