|
|
|
| 堆芯结构材料辐照促进应力腐蚀开裂研究现状 |
邓平1,孙晨2,彭群家1( ),韩恩厚1,柯伟1 |
1. 中国科学院金属研究所 中国科学院核用结构材料与安全性评价重点实验室 沈阳 110016
2. 国核 (北京) 科学技术研究院有限公司 北京 102209 |
|
| Review of Irradiation Assisted Stress Corrosion Cracking of Core Structural Materials |
| Ping DENG1,Chen SUN2,Qunjia PENG1(),En-Hou HAN1,Wei KE1 |
1 Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2 State Nuclear Power Research Institute, Beijing 102209, China |
引用本文:
邓平,孙晨,彭群家,韩恩厚,柯伟. 堆芯结构材料辐照促进应力腐蚀开裂研究现状[J]. 中国腐蚀与防护学报, 2015, 35(6): 479-487.
Ping DENG,
Chen SUN,
Qunjia PENG,
En-Hou HAN,
Wei KE.
Review of Irradiation Assisted Stress Corrosion Cracking of Core Structural Materials. Journal of Chinese Society for Corrosion and protection, 2015, 35(6): 479-487.
链接本文:
https://www.jcscp.org/CN/10.11902/1005.4537.2015.024
或
https://www.jcscp.org/CN/Y2015/V35/I6/479
|
| [1] | Ge?rard R, Somville F. Situation of the baffle-former bolts in Belgian units [A]. 17th International Conference on Nuclear Engineering[C]. Brussels, 2009: 521 | | [2] | Banic M J, Bros J, Cizelj L.Assessment and management of ageing of major nuclear power plant components important to safety: Steamgenerators [A]. IAEA Safety Series, International Atomic Energy Agency[C]. Vienna, 1996: 996 | | [3] | Andresen P L, Ford F P, Murphy S M, et al.State of knowledge of radiation effects on environmental cracking in light water reactor core materials [A]. Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Houston, 1990, 1: 83 | | [4] | Was G S, Andresen P L.Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments[J]. Corrosion, 2007, 63(1): 19 | | [5] | Simonen E P, Bruemmer S M.Radiation effects on environmental cracking of stainless steels[J]. JOM, 1998, 50(12) : 52-55 | | [6] | Zhang H K, Yao Z, Morin G, et al.TEM characterization of in-reactor neutron irradiated CANDU spacer material Inconel X-750[J]. J. Nucl. Mater., 2014, 451(1): 88 | | [7] | Was G S.Recent developments in understanding irradiation assisted stress corrosion cracking [A]. Proc. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Washington, 2003: 965 | | [8] | Was G S, Andresen P L.Irradiation-assisted stress-corrosion cracking in austenitic alloys[J]. JOM, 1992, 44(4): 8 | | [9] | Zhou R, West E A, Jiao Z, et al.Irradiation-assisted stress corrosion cracking of austenitic alloys in supercritical water[J]. J. Nucl. Mater., 2009, 395(1): 11 | | [10] | Ioka I, Ishijima Y, Usami K, et al.Radiation hardening and IASCC susceptibility of extra high purity austenitic stainless steel[J]. J. Nucl. Mater., 2011, 417(1): 887 | | [11] | Was G S, Bruemmer S M.Effects of irradiation on intergranular stress corrosion cracking[J]. J. Nucl. Mater., 1994, 216: 326 | | [12] | Stephenson K J, Was G S.Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons[J]. J. Nucl. Mater., 2015, 456: 85 | | [13] | Wan F R.Radiation Damage of Metal Materials [M]. Beijing: Science Press, 1993 | | [13] | (万发荣. 金属材料的辐射损伤 [M]. 北京: 科学出版社, 1993) | | [14] | Xu C, Was G S.In situ proton irradiation creep of ferritic-martensitic steel T91[J]. J. Nucl. Mater., 2013, 441(1): 681 | | [15] | Okamoto P R, Wiedersich H.Segregation of alloying elements to free surfaces during irradiation[J]. J. Nucl. Mater., 1974, 53: 336 | | [16] | Was G S, Allen T.Radiation-induced segregation in multicomponent alloys: Effect of particle type[J]. Mater. Charact., 1994, 32(4): 239 | | [17] | Allen T, Busby J T, Was G S, et al.On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Fe alloys[J]. J. Nucl. Mater., 1998, 255(1): 44 | | [18] | Maziasz P J.Overview of microstructural evolution in neutron-irradiated austenitic stainless steels[J]. J. Nucl. Mater., 1993, 205: 118 | | [19] | Maziasz P J, McHargue C J. Microstructural evolution in annealed austenitic steels during neutron irradiation[J]. Int. Mater. Rev., 1987, 32(1): 190 | | [20] | Garner F A.Evolution of microstructure in face-centered cubic metals during irradiation[J]. J. Nucl. Mater., 1993, 205: 98 | | [21] | Zinkle S J, Maziasz P J, Stoller R E.Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel[J]. J. Nucl. Mater., 1993, 206(2): 266 | | [22] | Edwards D J, Simonen E P, Bruemmer S M.Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 ℃[J]. J. Nucl. Mater., 2003, 317(1): 13 | | [23] | Edwards D J, Oliver B A, Garner F A, et al.Microstructural evaluation of a cold-worked 316SS baffle bolt irradiated in a commercial PWR [A]. Proc. 10th Int. Conf. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Houston, 2002: 1 | | [24] | Bruemmer S M, Simonen E P, Scott P M, et al.Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals[J]. J. Nucl. Mater., 1999, 274(3): 299 | | [25] | Bergenlid U, Haag Y, Pettersson K. The Studsvik MAT 1 experiment, R2 irradiations and post-irradiation tensile test [R]. Studsvik: Studsvik Nuclear-Report No.Studsvik/NS-90/13, 1990 | | [26] | Farrell K, Byun T S, Hashimoto N.Mapping Flow Localization Processes in Deformation of Irradiated Reactor Structural Alloys[M]. Washington D C: United States Department of Energy, 2003 | | [27] | Kodama M, Suzuki S, Nakata K, et al.Mechanical properties of various kinds of irradiated austenitic stainless steels [A]. Proc. 8th Int. Symp. on Environment Degradation of Materials in Nuclear Power System-Water Reactor[C]. La Grange Park, American Nuclear Society, 1997: 831 | | [28] | Odette G R, Lucas G E.The effects of intermediate temperature irradiation on the mechanical behavior of 300-series austenitic stainless steels[J]. J. Nucl. Mater., 1991, 179: 572 | | [29] | Garner F A, Flinn J E, Hall M M.Anisotropic swelling observed during stress-free reirradiation of AISI 304 tubes previously irradiated under stress[J]. J. Nucl. Mater., 2009, 386: 249 | | [30] | Seeger A K.On the theory of radiation damage and radiation hardening [R]. Stuttgart: Max-Planck-Inst, 1959 | | [31] | Singh B N, Foreman A J E, Trinkaus H. Radiation hardening revisited: role of intracascade clustering[J]. J. Nucl. Mater., 1997, 249(2): 103 | | [32] | Busby J T, Hash M C, Was G S.The relationship between hardness and yield stress in irradiated austenitic and ferritic steels[J]. J. Nucl. Mater., 2005, 336(2): 267 | | [33] | Was G S.Fundamentals of Radiation Materials Science[M]. Berlin Heidelberg: Springer Science & Business Media, 2007 | | [34] | Bruemmer S M, Cole J I, Brimhall J L, et al.Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels [A]. Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Richland, 1993: 537 | | [35] | Robertson I M, Robach J, Wirth B, et al.Dislocation behavior during deformation-combining experiments, simulation and modeling [A]. Symposium on Multiscale Phenomena in Materials-Experiments and Modeling Related to Mechanical Behavior[C]. San Francisco, 2003: 15 | | [36] | Esquivel E V, Murr L E.Grain boundary contributions to deformation and solid-state flow in severe plastic deformation[J]. Mater. Sci. Eng., 2005, A409(1): 13 | | [37] | Bloom E E.Irradiation Strengthening and Embrittlement[M]. Berlin Heidelberg: Springer Science & Business Media, 1976 | | [38] | Jiao Z J, Was G S, Miura T.Aspects of ion irradiations to study localized deformation in austenitic stainless steels[J]. J. Nucl. Mater., 2014, 452(1-3): 328 | | [39] | Heald P T, Speight M V.Steady-state irradiation creep[J]. Philos. Mag., 1974, 29(5): 1075 | | [40] | Brailsford A D, Bullough R.Irradiation creep due to the growth of interstitial loops[J]. Philos. Mag., 1973, 27(1): 49 | | [41] | Taylor R, Jeffs A T.The effect of irradiation on stress relaxation in Nimonic 80A[J]. J. Nucl. Mater., 1966, 19(2): 142 | | [42] | Garner F A.Materials Science and Technology: A Comprehensive Treatment[M]. Weinheim: VCH Publishers, 1994: 419 | | [43] | Garner F A.Understanding and Mitigating Aging in Nuclear Power Plants: Materials and Operational Aspects of Plant Life Management (PLiM)[M]. Amsterdam: Elsevier, 2010: 308 | | [44] | Ma C, Peng Q J, Han E-H, et al.Review of stress corrosion cracking of structural materials in nuclear power plants[J]. J. Chin. Soc. Corros. Prot., 2014, 34: 37 | | [44] | (马成, 彭群家, 韩恩厚等. 核电结构材料的应力腐蚀开裂研究现状与进展[J]. 中国腐蚀与防护学报, 2014, 34: 37) | | [45] | Chopra O K, Rao A S.A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rates of austenitic stainless steels[J]. J. Nucl. Mater., 2011, 409(3): 235 | | [46] | Chopra O K, Alexandreanu B, Gruber E E, et al.Crack Growth Rates of Irradiated Austenitic Stainless Steel Weld Heat Affected Zone in BWR Environments[M]. North Bethesda: Division of Engineering Technology, Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission, 2006 | | [47] | Chopra O K, Shack W J.Crack Growth Rates and Fracture Toughness of Irradiated Austenitic Stainless Steels in BWR Environments[M]. North Bethesda: US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2008 | | [48] | Brown K S, Gordon G M.Effects of BWR coolant chemistry on the propensity for IGSCC initiation and growth in creviced reactor internals components [A]. Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Michigan, 1988: 243 | | [49] | Gordon G M, Brown K S.Dependence of creviced BWR component IGSCC behavior on coolant chemistry [A]. Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Houston, 1990: 14 | | [50] | Was G S, Allen T R, Busby J T, et al.Microchemistry and microstructure of proton-irradiated austenitic alloys: Toward an understanding of irradiation effects in LWR core components[J]. J. Nucl. Mater., 1999, 270(1): 96 | | [51] | Scott P.A review of irradiation assisted stress corrosion cracking[J]. J. Nucl. Mater., 1994, 211(2): 101 | | [52] | Bruemmer S M, Was G S.Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems[J]. J. Nucl. Mater., 1994, 216: 348 | | [53] | Pardo A, Merino M C, Coy A E.Pitting corrosion behaviour of austenitic stainless steels-combining effects of Mn and Mo additions[J]. Corros. Sci., 2008, 50(6): 1796 | | [54] | Stephenson K J, Was G S.Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water[J]. J. Nucl. Mater., 2014, 444(1): 331 | | [55] | Yonezawa T, Fujimoto K, Kanasaki H, et al.Investigation of irradiation-induced intergranular stress corrosion cracking susceptibility of austenitic stainless steels for PWR by simulated radiation-induced segregation materials[J]. Corros. Eng., 2000, 49(7): 49 | | [56] | Koji F, Yonezawa T, Iwamura T, et al.Simulation of Radiation Induced Segregation of PWSCC Susceptibility for Austenitic Stainless Steels[J]. Corros. Eng., 2000, 49(8): 472 | | [57] | Yonezawa T, Iwamura T, Fujimoto K, et al.Optimized chemical composition and heat treatment conditions of 316 CW and high -chromium austenitic stainless steels for PWR baffle former bolts [A]. Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. California, 1999: 1015 | | [58] | Li G F, Kaneshima Y, Shoji T.Effects of impurities on environmentally assisted crack growth of solution-annealed austenitic steels in primary water at 325 ℃[J]. Corrosion, 2000, 56(5): 460 | | [59] | 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 | | [60] | Zinkle S J, Was G S.Materials challenges in nuclear energy[J]. Acta Mater., 2013, 61(3): 735 | | [61] | Jacobs A J, Wozadlo G P, Gordon G M.Low-temperature annealing: A process to mitigate irradiation-assisted stress corrosion crac-king[J]. Corrosion, 1995, 51(10): 731 | | [62] | Katsura R, Ishiyama Y, Yokota N, et al.Post-irradiation annealing effects of austenitic stainless steel in IASCC [A]. Proc. Corrosion 98 Conference, NACE International[C], Houston, 1998 | | [63] | Edwards D J, Simonen E P, Garner F A, et al.Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS[J]. J. Nucl. Mater., 2003, 317(1): 32 | | [64] | Hash M C, Busby J T, Was G S.The effect of hardening source in proton irradiation-assisted stress corrosion cracking of cold workedtype 304 stainless steel [A]. 21st International Symposium on Effects of Radiation on Materials[C]. Arizona, 2004: 92 | | [65] | Manahan M P, Kohli R, Santucci J, et al.A phenomenological investigation of in-reactor cracking of type 304 stainless steel control rod cladding[J]. Nucl. Eng. Des., 1989, 113(3): 297 | | [66] | Hide K, Onchi T, Mayuzumi M, et al.Intergranular cracking of irradiated thermally sensitized type 304 stainless steel in high-temperature water and inert gas[J]. Corrosion, 1995, 51(10): 757 | | [67] | Thomas L E, Bruemmer S M.Insights into environmental degradation mechanisms from analytical transmission electron microscopy of SCC cracks [A]. Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. California, 1999: 41 | | [68] | Andresen P L, Chou P.Effects of hydrogen on SCC growth rate of Ni alloys in BWR water [A]. Proc. 15th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Colorado, Springs, 2011: 2039 | | [69] | Indig M E, Wozadlo G P, Nelson J L.Investigation of the protection potential against IASCC [A]. Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. California, 1991: 671 | | [70] | Kodama M, Nishimura S, Morisawa J, et al.Effects of fluence and dissolved oxygen on IASCC in austenitic stainless steels [A]. Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. California, 1991:948 | | [71] | Ashida Y, Flick A, Andresen P L, et al.The key factors affecting crack growth behavior of neutron-irradiated austenitic alloys [A]. Proc. 15th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Colorado, Springs, 2011: 1241 | | [72] | Shi J, Wang J, Macdonald D D.Prediction of crack growth rate in type 304 stainless steel using artificial neural networks and the coupled environment fracture model[J]. Corros. Sci., 2014, 89: 69 | | [73] | Zhang L, Wang J.Effect of temperature and loading mode on environmentally assisted crack growth of a forged 316L SS in oxygenated high-temperature water[J]. Corros. Sci., 2014, 87: 278 | | [74] | Andresen P L.Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600[J]. Corrosion, 1993, 49(9): 714 | | [75] | Swann P R.Dislocation substructure vs transgranular stress corrosion susceptibility of single phase alloys[J]. Corrosion, 1963, 19(3): 102 | | [76] | Stroh A N.The cleavage of metal single crystals[J]. Philos. Mag., 1958, 3(30): 597 | | [77] | Alexandreanu B, Was G S.Grain boundary deformation-induced intergranular stress corrosion cracking of Ni-16Cr-9Fe in 360 ℃ water[J]. Corrosion, 2003, 59(8): 705 | | [78] | Jiao Z, Was G S.Localized deformation and IASCC initiation in austenitic stainless steels[J]. J. Nucl. Mater., 2008, 382(2): 203 | | [79] | Fukuya K, Nakano M, Fujii K, et al.IASCC susceptibility and slow tensile properties of highly-irradiated 316 stainless steels[J]. J. Nucl. Sci. Technol., 2004, 41(6): 673 | | [80] | Fukuya K, Fujii K, Nishioka H, et al.Evolution of microstructure and microchemistry in cold-worked 316 stainless steels under PWRirradiation[J]. J. Nucl. Sci. Technol., 2006, 43(2): 159 | | [81] | Das E S P, Marcinkowski M J. Accommodation of the stress field at a grain boundary under heterogeneous shear by initiation of microcracks[J]. J. Appl. Phys., 1972, 43(11): 4425 | | [82] | Busby J T, Was G S.Irradiation-assisted stress corrosion cracking in model austenitic alloys with solute additions [A]. Proc. 11th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Washington, 2003: 995 | | [83] | Pathania R S, Nelson J L.The use of proton irradiation to understand IASCC in LWR cores [R]. Palo Alto: EPRI, 2001 | | [84] | Wang G H.Particle Interaction on Solid Physics [M]. Beijing: Science Press, 1988 | | [84] | (王广厚. 粒子同固体相互作用物理学 [M]. 北京: 科学出版社, 1988) | | [85] | Xu C L, Wang R S, Huang P, et al.Charged-particles irradiation simulation of neutron irradiation assisted strain corrosion cracking in stainless steel[J]. Mater. Rev., 2012, 26(2): 150 | | [85] | (徐超亮, 王荣山, 黄平等. 不锈钢中子辐照加速应力腐蚀开裂的带电粒子辐照模拟[J]. 材料导报, 2012, 26(2): 150) |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|
