Assessing the influence of welding-induced mechanics on oxidation and stress corrosion cracking in an Alloy 600-Alloy 152 M weldment under simulated PWR primary water

被引:0
|
作者
Xu, Xinhe [1 ,2 ]
Pan, Deng [1 ,2 ]
Li, Entong [1 ,2 ]
Lu, Zhanpeng [1 ,2 ]
Cui, Tongming [1 ,2 ]
Chen, Junjie [1 ,2 ]
Zheng, Hui [3 ]
Li, Kai [3 ]
Lozano-Perez, Sergio [4 ]
Shoji, Tetsuo [5 ]
机构
[1] Shanghai Univ, Inst Mat, Sch Mat Sci & Engn, Shanghai 200072, Peoples R China
[2] Shanghai Univ, State Key Lab Adv Special Steels, Shanghai 200072, Peoples R China
[3] State Nucl Power Plant Serv Co, 888 Tianlin Rd, Shanghai 200233, Peoples R China
[4] Univ Oxford, Dept Mat, Parks Rd, Oxford OX1 3PH, England
[5] Tohoku Univ, New Ind Creat Hatchery Ctr, Sendai 9808579, Japan
关键词
Pressurized water reactor; Alloy; 600; Heat-affected zone; Residual stress; Stress corrosion cracking; Oxidation; INTERGRANULAR OXIDATION; HIGH-TEMPERATURE; STAINLESS-STEEL; INTERNAL OXIDATION; MICROSTRUCTURE; DEFORMATION; DEPENDENCE; CARBIDES; BEHAVIOR; STRAIN;
D O I
10.1016/j.jnucmat.2024.155349
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The impact of welding-induced mechanics on the oxidation and stress corrosion cracking (SCC) behavior of Alloy 600 in a pressurized water reactor (PWR) primary water was investigated using an Alloy 600-Alloy 152 M weldment. The microstructural analysis found a 0.05 mm-wide composition transition zone from welding. The Alloy 600 heat-affected zone (HAZ) grain size matches the Alloy 600 base (600B). Deformation hardening initially decreases and stabilizes from the fusion boundary (FB) to the 600B Comparing the microstructural characteristics of the specimen from the HAZ at about 0.5 mm from the FB with specimen 600B shows identical composition, but the former exhibits higher Vickers hardness (HV), kernel average misorientation (KAM), dislocation density, and residual stresses. Results from both short- and long-term oxidation tests indicate that the specimen from the HAZ exhibits a greater thickness of the inner oxide film, a higher number of local oxidation sites, and an increased maximum depth of intergranular (IG) oxidation compared to the 600B specimen. Multiple sets of SCC test results demonstrate that the crack growth rate (CGR) in the specimens from the HAZ is higher than that in the base, with the former showing longer IG cracks and a greater proportion of IG cracking.
引用
收藏
页数:24
相关论文
共 50 条
  • [1] Dielectrostriction and Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Primary Water
    Devine, Thomas M.
    CORROSION, PASSIVITY, AND ENERGY: A SYMPOSIUM IN HONOR OF DIGBY D. MACDONALD, 2013, 50 (31): : 91 - 97
  • [2] Crack growth and cracking behavior of Alloy 600/182 and Alloy 690/152 welds in simulated PWR primary water
    Lim, Yun Soo
    Kim, Dong Jin
    Kim, Sung Woo
    Kim, Hong Pyo
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2019, 51 (01) : 228 - 237
  • [3] STRESS CORROSION CRACKING OF ALLOY 600 IN PWR PRIMARY WATER : INFLUENCE OF CHROMIUM, HYDROGEN AND OXYGEN DIFFUSION
    Guerre, C.
    Laghoutaris, P.
    Chene, J.
    Marchetti, L.
    Molins, R.
    Duhamel, C.
    Sennour, M.
    15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 1477 - 1488
  • [4] Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam and PWR primary side water
    Sui, G
    Heys, GB
    Congleton, J
    PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 274 - 281
  • [5] Effect of material chemical composition on oxidation and stress corrosion cracking of the submerged arc welding Alloy 52M overlay in a simulated PWR primary water
    Xu, Xinhe
    Jia, Yibo
    Pan, Deng
    Cui, Tongming
    Lu, Zhanpeng
    Lozano-Perez, Sergio
    Chen, Junjie
    Li, Shuangyan
    Shoji, Tetsuo
    JOURNAL OF NUCLEAR MATERIALS, 2024, 588
  • [6] Microstructural characterization on intergranular stress corrosion cracking of Alloy 600 in PWR primary water environment
    Lim, Yun Soo
    Kim, Hong Pyo
    Hwang, Seong Sik
    JOURNAL OF NUCLEAR MATERIALS, 2013, 440 (1-3) : 46 - 54
  • [7] Combined effects of lead and magnetite on the stress corrosion cracking of alloy 600 in simulated PWR secondary water
    Song, Geun Dong
    Choi, Won-Ik
    Jeon, Soon-Hyeok
    Kim, Jung Gu
    Hur, Do Haeng
    JOURNAL OF NUCLEAR MATERIALS, 2018, 512 : 8 - 14
  • [8] Stress corrosion crack initiation of alloy 600 in PWR primary water
    Zhai, Ziqing
    Toloczko, Mychailo B.
    Olszta, Matthew J.
    Bruemmer, Stephen M.
    CORROSION SCIENCE, 2017, 123 : 76 - 87
  • [9] Influence of surface condition on primary water stress corrosion cracking initiation of alloy 600
    Le Hong, S
    CORROSION, 2001, 57 (04) : 323 - 333
  • [10] Influence of δ phase precipitation on the stress corrosion cracking resistance of alloy 718 in PWR primary water
    Deleume, Julien
    Cloue, Jean-Marc
    Andrieu, Eric
    JOURNAL OF NUCLEAR MATERIALS, 2008, 382 (01) : 70 - 75