|
|
质子辐照对AL-6XN在高温高压水中的腐蚀行为影响 |
乔岩欣1,2,任爱1,刘飞华1,郑玉贵2,唐睿3,靳硕学4,郭立平4 |
1. 苏州热工研究院有限公司 苏州 215004
2. 中国科学院金属研究所 金属腐蚀与防护国家重点实验室 沈阳 110016
3. 中国核动力研究设计院 成都 610041
4. 武汉大学物理科学与技术学院 武汉 430072 |
|
EFFECT OF PROTON IRRADIATION ON CORROSION BEHAVIOR OF AUSTENITE STAINLESS STEEL AL-6XN IN HIGH TEMPRATURE HIGH PRESSURE WATER |
QIAO Yanxin1,2, REN Ai1, LIU Feihua1, ZHENG Yugui2, TANG Rui3, JIN Shuoxue4, GUO Liping4 |
1. Suzhou Nuclear Power Research Institute, Suzhou 215004
2. State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
3. Nuclear Power Institute of China, Chengdu 610041
4. School of Physics and Technology, Wuhan University, Wuhan 430072 |
引用本文:
乔岩欣,任爱,刘飞华,郑玉贵,唐睿,靳硕学,郭立平. 质子辐照对AL-6XN在高温高压水中的腐蚀行为影响[J]. 中国腐蚀与防护学报, 2012, 32(5): 381-387.
QIAO Yanxin,
REN Ai,
LIU Feihua,
ZHENG Yugui,
TANG Rui,
JIN Shuoxue,
GUO Liping.
EFFECT OF PROTON IRRADIATION ON CORROSION BEHAVIOR OF AUSTENITE STAINLESS STEEL AL-6XN IN HIGH TEMPRATURE HIGH PRESSURE WATER. Journal of Chinese Society for Corrosion and protection, 2012, 32(5): 381-387.
链接本文:
https://www.jcscp.org/CN/
或
https://www.jcscp.org/CN/Y2012/V32/I5/381
|
[1] Allen T R, Sridharan K, Tan L, et al. Materials challenges for generation IV nuclear energy systems [J]. Nucl. Technol., 2008, 162: 342-457[2] Zhou R S, West E A, Jiao Z J, et al. Irradiation-assisted stress corrosion cracking of austenitic alloys in supercritical water [J]. J. Nucl. Mater., 2009, 395: 11-22[3] Was G S, Ampornrat P, Gupta G, et al. Corrosion and stress corrosion cracking in supercritical water [J]. J. Nucl. Mater., 2007, 371: 176-201[4] Yin K J, Qiu S Y, Tang R, et al. Corrosion behavior of ferritic/martensitic steel P92 in supercritical water [J]. J. Super. Flu., 2009, 50: 235-239[5] Zhu F W, Zhang L F, Tang R, et al. Corrosion behavior of austenitic 304NG stainless steel in supercritical water at 550℃/25MPa [J]. Atom. Energ. Sci. Tech., 2009, 46: 518-522 (朱发文, 张乐福, 唐睿等. 奥氏体304NG不锈钢在550℃/25 MPa超临界水中的腐蚀行为[J]. 原子能科学技术, 2009, 46: 518-522)[6] Jiang E, Wen Y, Liu R C, et al. Research on general corrosion property of 304NG stainless steel [J]. Nucl. Power Eng., 2007, 26: 390-392 (姜峨, 文燕, 刘然超等. 304NG不锈钢均匀腐蚀性能研究[J]. 核动力工程, 2007, 26: 390-392)[7] Bai X D, Chen X W, Xu J, et al. Corrosion resistance and microstructure of zircaloy-4 subjected to ion irradiation [J]. Nucl. Ins. Meth. Phy. Res. B, 2005, 217: 293-299[8] Wan Q, Bai X D, Zhang X Y. Impact of high dose krypton ion irradiation on corrosion behavior of laser beam welded zircaloy-4 [J]. Mater. Res. Bull., 2006, 41: 387-395[9] Teysseyre S, Was G S. Stress corrosion cracking of austenitic alloys in supercritical water [J]. Corrosion, 2006, 62: 1100-1116[10] Was G S, Teysseyre S, Jiao Z. Corrosion of austenitic alloys in supercritical water [J]. Corrosion, 2006, 62: 989-1005[11] MacDonald D D. Effect of pressure on the rate of corrosion of metals in high subcritical and supercritical aqueous systems [J]. J. Super. Flu., 2004, 30: 375-382[12] Yi Y S, Lee B H, Kim S H, et al. Corrosion and corrosion fatigue behaviors of 9Cr steel in a supercritical water condition [J]. Mater. Sci. Eng.,2006, A429: 161-168[13] Ehlers J, Young D J, Smaardijk E J, et al. Enhanced oxidation of the 9%Cr steel P91 in water vapor containing environments [J]. Corros. Sci., 2006, 48: 3428-3454[14] Essuman E, Meier G H, Zurek J, et al. The effect of water vapor on selective oxidation of Fe-Cr alloys [J]. Oxid. Met., 2008, 69:143-162[15] Jin S X, Guo L P, Yang Z, et al. Microstructural evolution in nickel alloy C-276 after Ar+ ion irradiation [J]. Nucl. Ins. Meth. Phy. Res. B, 2011, 269: 209-215[16] Characterization of Neutron-Irradiated 300-Series Stainless Steels to Assess Mechanisms of Irradiation-Assisted Stress Corrosion Cracking: Volume 1: LWR-Irradiated Type 304 and 316SS Heats with Established IASCC Susceptibility [M]. Palo Alto: EPRI, 2001[17] Panter J, Viguier B, Cloue J M, et al. Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [J]. J. Nucl. Mater., 2006, 348: 213-221[18] Yin K J. Corrosion behavior of candidate material for supercritical water reactor [D]. Beijing: Nuclear Power Institute of China, 2011 (尹开锯. 超临界水堆(SCWR)候选材料腐蚀行为研究[D]. 北京: 中国核动力研究设计院, 2011) |
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
|
Shared |
|
|
|
|
|
Discussed |
|
|
|
|