Factors affecting the crack growth rates of reactor pressure vessel steels under simulated boiling water reactor conditions (vol 62, pg 403, 2006)

被引：0

作者：

Chen, YY ^{[1
]}

Shih, HC

Wang, LH

Oung, JC

机构：

[1] Natl Tsing Hua Univ, Dept Mat Sci & Engn, Hsinchu 300, Taiwan

[2] Ind Technol Res Inst, Mat Res Labs, Hsinchu 310, Taiwan

来源：

CORROSION | 2006年 / 62卷 / 06期

关键词：

D O I：

暂无

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

页码：552 / 552

页数：1

共 26 条

[1] Factors affecting the crack growth rates of reactor pressure vessel steels under simulated boiling water reactor conditions
Chen, Y. Y.
Shih, H. C.
Wang, L. H.
Oung, J. C.
CORROSION, 2006, 62 (05) : 403 - 418
[2] Corrosion fatigue crack growth behaviour of low-alloy reactor pressure vessel steels under boiling water reactor conditions
Seifert, H. P.
Ritter, S.
CORROSION SCIENCE, 2008, 50 (07) : 1884 - 1899
[3] Stress corrosion cracking of reactor pressure vessel steels under boiling water reactor conditions
Heldt, J
Seifert, HP
PROCEEDINGS OF THE NINTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 1999, : 901 - 909
[4] Stress corrosion cracking of low-alloy reactor pressure vessel steels under boiling water reactor conditions
Seifert, H. P.
Ritter, S.
JOURNAL OF NUCLEAR MATERIALS, 2008, 372 (01) : 114 - 131
[5] The role of water chemistry for environmentally assisted cracking in low-alloy reactor pressure vessel and piping steels under boiling water reactor conditions
Seifert, HP
Ritter, S
CHIMIA, 2005, 59 (12) : 944 - 949
[6] FATIGUE CRACK-GROWTH OF IRRADIATED PRESSURE-VESSEL STEELS IN SIMULATED, REACTOR-GRADE WATER ENVIRONMENT
CULLEN, WH
WATSON, HE
PROVENZANO, V
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 182 - 183
[7] CYCLIC CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEELS IN LIGHT WATER-REACTOR ENVIRONMENTS
VANDERSLUYS, WA
EMANUELSON, RH
JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1986, 108 (01): : 26 - 30
[8] INVESTIGATION ON CYCLIC CRACK-GROWTH BEHAVIOR OF REACTOR PRESSURE-VESSEL STEELS PLACED AND LOADED IN THE CORE REGION OF AN OPERATING BOILING WATER-REACTOR
ANDERS, D
FOHL, J
NUCLEAR ENGINEERING AND DESIGN, 1992, 136 (03) : 265 - 276
[9] The influence of ppb levels of chloride impurities on the stress corrosion crack growth behaviour of low-alloy steels under simulated boiling water reactor conditions
Seifert, H. P.
Ritter, S.
CORROSION SCIENCE, 2016, 108 : 134 - 147
[10] Modeling for ductile-to-brittle transition under ductile crack growth for reactor pressure vessel steels
Margolin, BZ
Kostylev, VI
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1999, 76 (05) : 309 - 317

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