|
|
核电异种金属焊接接头的应力腐蚀裂纹扩展行为研究进展 |
朱若林,张志明,王俭秋( ),韩恩厚 |
|
Review on SCC Crack Growth Behavior of Dissimilar Metal Welds for Nuclear Power Reactors |
Ruolin ZHU,Zhiming ZHANG,Jianqiu WANG( ),En-Hou HAN |
Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China |
引用本文:
朱若林,张志明,王俭秋,韩恩厚. 核电异种金属焊接接头的应力腐蚀裂纹扩展行为研究进展[J]. 中国腐蚀与防护学报, 2015, 35(3): 189-198.
Ruolin ZHU,
Zhiming ZHANG,
Jianqiu WANG,
En-Hou HAN.
Review on SCC Crack Growth Behavior of Dissimilar Metal Welds for Nuclear Power Reactors. Journal of Chinese Society for Corrosion and protection, 2015, 35(3): 189-198.
链接本文:
https://www.jcscp.org/CN/10.11902/1005.4537.2014.101
或
https://www.jcscp.org/CN/Y2015/V35/I3/189
|
[1] | Rebak R B. 2012 Research topical symposium proceedings "Corrosion degradation of materials in nuclear power reactors-lessons lear-ned future challenges" introduction[J]. Corrosion, 2013, 69(10):951 | [2] | Kerr M, Hill M R, Olson M D. Study of residual stresses in compact tension specimens fabricated from weld metal[J]. Corrosion, 2013, 69(10): 975 | [3] | Celin R,Tehovnik F.Degradation of a Ni-Cr-Fe alloy in a pressurised-water nuclear power plant [J]. Mater. Technol, 2011, 45(2): 151 | [4] | Tsuruta T,Sato K,Asada S,et al. PWSCC of nickel base alloys in vapor phase environment of pressurizer [A]. Icone16: Proceeding of the 16th International Conference on Nuclear Engineering [C]. Orlando: ASME, 2008: 571 | [5] | Chung W C, Huang J Y, Tsay L W, et al. Microstructure and stress corrosion cracking behavior of the weld metal in alloy 52-A508 dissimilar welds[J]. Mater. Trans. JIM, 2011, 52(1): 12 | [6] | 0 Li G F, Congleton J. Stress corrosion cracking of a low alloy steel to stainless steel transition weld in PWR primary waters at 292 ℃[J]. Corros. Sci., 2000, 42(6): 1005 | [7] | Muransky O, Smith M C, Bendeich P J, et al. Validated numerical analysis of residual stresses in Safety Relief Valve (SRV) nozzle mock-ups[J]. Comput. Mater. Sci., 2011, 50(7): 2203 | [8] | Andresen P L.Emerging issues and fundamental processes in environmental cracking in hot water (Reprinted from proceedings of the CORROSION/2007 research topical symposium"Advances in environmentally assisted cracking", 2007)[J]. Corrosion, 2008, 64(5): 439 | [9] | Cattant F, Crusset D, Feron D. Corrosion issues in nuclear industry today[J]. Mater. Today, 2008, 11(10): 32 | [10] | Andresen P L, Morra M M. Stress corrosion cracking of stainless steels and nickel alloys in high-temperature water[J]. Corrosion, 2008, 64(1): 15 | [11] | Paraventi D J, Moshier W C.The effect of cold work and dissolved hydrogen in the stress corrosion cracking of Alloy 82 and Alloy 182 weld metal [A]. Proc. 12th Int. Symp. Environmental Degradation of Materials in Nuclear Power System [C]. Warrendale: TMS, 2005: 543 | [12] | Alexandreanu B,Chen Y,Natesan K,et al. SCC behavior of Alloy 690 HAZ in a PWR environment [A]. Proceedings of the Asme Pressure Vessels and Piping Conference [C]. Baltimore: ASME, 2012: 385 | [13] | Amzallag C,Boursier J,Pages C,et al. Stress corrosion life experience of 182 and 82 welds in French PWRs [A]. 5th Fontevraud Conf. Contribution of Material Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors [C]. Fontevraud, 2002: 22 | [14] | Scott P M.An overview of materials degradation by stress corrosion in PWRs [A]. European Corrosion Conference: Long Term Prediction and Modelling of Corrosion, EUROCORR 2004 [C]. Nice: Cefracor, 2004: 3 | [15] | Bamford W, Hall J.A review of alloy 600 cracking in operating nuclear plants including alloy 82 and 182 weld behavior [A]. 12th International Conference on Nuclear Engineering (ICONE12) [C]. Arlington: ASME, 2004: 131 | [16] | Gorman J, Hunt S, Riccardella P. PWR Reactor Vessel Alloy 600 Issues [M]. New York: ASME, 2009: 63 | [17] | Yvon P, Carre F.Structural materials challenges for advanced reactor systems[J]. J. Nucl. Mater., 2009, 385(2): 217 | [18] | Young G A, Etien R A, Hackett M J, et al. Physical metallurgy, weldability, and in-service performance of nickel-chromium filler metals used in nuclear power systems [A]. Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors [C]. Colorado Sprin-gs: Wiley Online Library, 2009: 2431 | [19] | Szklarskasmialowska S, Cragnolino G. Stress-corrosion cracking of sensitized type-304 stainless-steel in oxygenated pure water at elevated-temperatures (review)[J]. Corrosion, 1980, 36(12): 653 | [20] | Huang J Y, Liu R F, Chiang M F, et al. Corrosion fatigue behavior of dissimilar metal weldments under nominal constant Delta K loading mode in a simulated BWR coolant environment[J]. Corros. Sci., 2011, 53(6): 2289 | [21] | Huang J Y, Chiang M F, Jeng S L, et al. Environmentally assisted cracking behavior of dissimilar metal weldments in simulated BWR coolant environments[J]. J. Nucl. Mater., 2013, 432(1-3): 189 | [22] | Huang J Y, Yung T Y, Huang J S, et al. Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments[J]. Corros. Sci., 2013, 75: 386 | [23] | Ozawa M, Yamamoto Y, Nakata K, et al. Evaluation of SCC crack growth rate in alloy 600 and its weld metals in simulated BWR environments [A]. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors [C]. Salt Lake City: TMS, 2006: 651 | [24] | Lee H T, Wu J L. Intergranular corrosion resistance of nickel-based alloy 690 weldments[J]. Corros. Sci., 2010, 52(5): 1545 | [25] | Hou J, Peng Q, Takeda Y, et al. Microstructure and stress corrosion cracking of the fusion boundary region in an alloy 182-A533B low alloy steel dissimilar weld joint[J]. Corros. Sci., 2010, 52(12): 3949 | [26] | Peng Q, Xue H, Hou J, et al. Role of water chemistry and microstructure in stress corrosion cracking in the fusion boundary region of an Alloy 182-A533B low alloy steel dissimilar weld joint in high temperature water[J]. Corros. Sci., 2011, 53(12): 4309 | [27] | White G A, Nordmann N S, Hickling J, et al. Development of crack growth rate disposition curves for primary water stress corrosion cracking (PWSCC) of alloy 82, 182, and 132 weldments [A]. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors [C]. Salt Lake City: TMS, 2006: 511 | [28] | Bruemmer S M, Charlot L A, Henager C H. Microstructure and microdeformation effects on IGSCC of alloy-600 steam-generator tubing[J]. Corrosion, 1988, 44(11): 782 | [29] | Guerre C, Chaumun E, Crepin J, et al. Stress corrosion cracking of nickel base alloys in PWR primary water [A]. 1st International Workshop on Materials Innovation for Nuclear Optimized Systems[C].CEA Saclay: EPJ Web of Conferences, 2013 | null | | [30] | Yeh T K, huang G R, Wang M Y, et al. Stress corrosion cracking in dissimilar metal welds with 304L stainless steel and Alloy 82 in high temperature water[J]. Prog. Nucl. Energy, 2013, 63: 7 | [31] | Huang J Y, Chiang M F, Kuo R C, et al. Stress corrosion cracking behavior of dissimilar metal weldments in high temperature water environments [A]. Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]. Colorado Springs: TMS, 2011: 1105 | [32] | Saito N, Tanaka S, Sakamoto H. Effect of corrosion potential and microstructure on the stress corrosion cracking susceptibility of nickel-base alloys in high-temperature water[J]. Corrosion, 2003, 59(12): 1064 | [33] | Alexandreanu B,Chopra O K,Shack W J. The stress corrosion cracking behavior of alloys 690 and 152 weld in a PWR environment [A]. Pressure Vessel and Piping Division of the American Society of Mechanical Engineers [C]. Chicago: ASME, 2009: 153 | [34] | Alexandreanu B,Chopra O K,Shack W J. Crack growth rates of nickel alloy welds in a PWR environment [A]. ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference [C]. Vancouver: ASME, 2006: 153 | [35] | Seifert H P, Ritter S, Shoji T, et al. Environmentally-assisted cracking behaviour in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment[J]. J. Nucl. Mater., 2008, 378(2): 197 | [36] | Kim S W, Kim H P, Jeong J U, et al. Effect of residual stress of dissimilar metal welding on stress corrosion cracking of bottom-mounted instrumentation penetration mock-up[J]. Corrosion, 2010 66(10): 106001 | [37] | Zhang T,Brust F W,Wilkowski G,et al. Welding residual stress in a large diameter nuclear reactor pressure vessel nozzle [J]. J. Press Vess-T ASME, 2013, 135(2): 021208 | [38] | Liu R F, Huang C C. Welding residual stress analysis for weld overlay on a BWR feedwater nozzle[J]. Nucl. Eng. Des., 2013, 256: 291 | [39] | Lu Z, Shoji T, Takeda Y, et al. The dependency of the crack growth rate on the loading pattern and temperature in stress corrosion cracking of strain-hardened 316L stainless steels in a simulated BWR environment[J]. Corros. Sci., 2008, 50(3): 698 | [40] | Andresen P L, Young L M, Emigh P W, et al. Stress corrosion crack growth rate behavior of ni alloys 182 and 600 in high temperature water [A]. Corrosion/2002 [C]. Denver: NACE, 2002: 1 | [41] | Zhang L T,Wang J Q. Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment [J]. J. Nucl. Mater.., 2014, 446(1-3): 15 | [42] | Toloczko M B, Olszta M J, Bruemmer S M. Stress corrosion crack growth of alloy 52m in simulated PWR primary water [A]. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors [C]. Colorado Sprin-gs: TMS, 2011: 225 | [43] | Lu Z, Shoji T, Xue H, et al. Synergistic effects of local strain-hardening and dissolved oxygen on stress corrosion cracking of 316NG weld heat-affected zones in simulated BWR environments[J]. J. Nucl. Mater., 2012, 423(1-3): 28 | [44] | Lu Z, Shoji T, Meng F, et al. Characterization of microstructure and local deformation in 316NG weld heat-affected zone and stress corrosion cracking in high temperature water[J]. Corros. Sci., 2011, 53(5): 1916 | [45] | Alexandreanu B,Chen Y,Natesan K,et al. Cyclic and SCC behavior of alloy 152 weld in a PWR environment [A]. Proceedings of the ASME Pressure Vessels and Piping Conference [C]. Baltimore: AMSE, 2012: 639 | [46] | Terachi T, Yamada T, Miyamoto T, et al. SCC growth behaviors of austenitic stainless steels in simulated PWR primary water[J]. J. Nucl. Mater., 2012, 426(1-3): 59 | [47] | Zhanpeng L, Shoji T, Takeda Y, et al. Transient and steady state crack growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in oxygenated pure water at different temperatures[J]. Corros. Sci., 2008, 50(2): 561 | [48] | Andresen P L. Stress corrosion cracking of current structural materials in commercial nuclear power plants[J]. Corrosion, 2013, 69(10): 1024 | [49] | Stjarnsater J, Jenssen A, Jansson C, et al. The effect of temperature on the crack growth rate of stainless steel and ni-alloys in simulated BWR environment [A]. 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]. Colorado Springs: TMS, 2011: 827 | [50] | Hoang P H, Gangadharan A, Ramalingam S C. Primary water stress corrosion cracking inspection ranking scheme for alloy 600 components[J]. Nucl. Eng. Des., 1998, 181(1-3): 209 | [51] | Kim Y J, Andresen P L, Moran E, et al. Modification of surface property for controlling the Type 304 stainless steel electrochemical corrosion potential in 288 ℃ water[J]. Corrosion, 2005, 61(7): 648 | [52] | Lima L I L,Schvartzman M M A M,Figueiredo C A,et al. Stress corrosion cracking behavior of alloy 182 weld in pressurized water reactor primary water environment at 325 ℃ [J]. Corrosion, 2011, 67(8): 085004 | [53] | Andresen P L, Hickling J, Ahluwalia A, et al. Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water[J]. Corrosion, 2008, 64(9): 707 | [54] | Andresen P L, Young L M. Crack-tip microsampling and growth-rate measurements in low-alloy steel in high-temperature water[J]. Corrosion, 1995, 51(3): 223 | [55] | Andresen P L, Emigh P W, Morra M M, et al. Effects of PWR primary water chemistry and deaerated water on SCC [A]. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-water Reactors [C]. Salt Lake City : TMS, 2006: 989 | [56] | Korb J, Stellwag B. Thermodynamics of zinc chemistry in PWRs: effects and alternatives to zinc[J]. Nucl. Energ-J. Br. Nucl., 1997, 36(5): 377 | [57] | Liu X H, Wu X Q, Han E-H.Influence of Zn injection on characteristics of oxide film on 304 stainless steel in borated and lithiated high temperature water[J]. Corros. Sci., 2011, 53(10): 3337 | [58] | Liu X H, Han E H, Wu X Q.Effect of Zn injection on established surface oxide films on 316 L stainless steel in borated and lithiated high temperature water[J]. Corros. Sci., 2012, 65: 136 |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
|
Shared |
|
|
|
|
|
Discussed |
|
|
|
|