Weld Heat Input and Stress Corrosion Cracking of Alloy 182 Filler in a Pressurized Water Reactor Nuclear Reactor Coolant Environment

被引:1
|
作者
Silva, G. M. [1 ]
Bracarense, A. Q. [2 ]
Schvartzman, M. M. A. M. [3 ]
机构
[1] Ctr Fed Educacao Tecnol Minas Gerais CEFETMG, BR-30421169 Belo Hoizonte, MG, Brazil
[2] Univ Fed Minas Gerais UFMG, BR-31270901 Belo Horizonte, MG, Brazil
[3] Ctr Desenvolvimento Tecnol Nucl CDTN, BR-CEP31270 Belo Horizonte, MG, Brazil
关键词
Alloy; 182; corrosion; dissimilar welding; heat input; stress corrosion cracking;
D O I
10.5006/1.3613644
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In pressurized water reactors (PWR), dissimilar metal welds are made to join the pressure vessels of low-alloy steel to pipes of stainless steel using Alloy 182 (UNS W86182) as a filler metal. However, it has been found that Alloy 182 is susceptible to intergranular environmentally assisted cracking (IGEAC) at high temperatures, and this has been one of the major concerns in the management and prediction of plant life. Variation within welds and welders are expected; for design and integrity assessment of the dissimilar welds, these variations should be evaluated. In this study, three dissimilar welds blocks of ASTM A508 steel were prepared using gas tungsten arc welding (GTAW; buttering) and shield metal arc welding (SMAW) processes using Alloys 82/182 (UNS N06082/UNS W86182) as filler metal. Three different welding conditions or heat inputs were used: normal or conventional for the procedure, higher, and normal but cooled. Samples were taken from the three blocks and tested with slow strain rate testing (SSRT). All specimens were taken from the region filled by Alloy 182 within the dissimilar welded blocks and tested under the PWR environment. Microstructures were observed under optical and electron microscopes. Typical dendrite structures were observed in Alloys 82/182 welds. Microhardness tests were conducted to measure the variation in hardness of the weld. It was discovered that a higher heat input increases the ASTM G129 ratios that shall be utilized in evaluating SSRT.
引用
收藏
页数:10
相关论文
共 50 条
  • [41] A case study of environmental assisted cracking in a low alloy steel under simulated environment of pressurized water reactor
    Shahzad, M.
    Qureshi, A. H.
    Waqas, H.
    Hussain, N.
    MATERIALS & DESIGN, 2011, 32 (10): : 5154 - 5158
  • [42] Stress Corrosion Cracking of Ferritic-Martensitic Steels in Simulated Boiling Water Reactor Environment
    Ahmedabadi, Parag M.
    Was, Gary S.
    CORROSION, 2016, 72 (01) : 66 - 77
  • [43] Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment
    Lijin Dong
    Cheng Ma
    Qunjia Peng
    En-Hou Han
    Wei Ke
    JournalofMaterialsScience&Technology, 2020, 40 (05) : 1 - 14
  • [44] Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment
    Dong, Lijin
    Ma, Cheng
    Peng, Qunjia
    Han, En-Hou
    Ke, Wei
    JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2020, 40 : 1 - 14
  • [45] 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
  • [46] Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environment
    Que, Zaiqing
    Zajec, Bojan
    Ritter, Stefan
    Seppanen, Tommi
    Saario, Timo
    Toivonen, Aki
    Treichel, Aleksandra
    Lautaru, Valentin
    Scenini, Fabio
    CORROSION ENGINEERING SCIENCE AND TECHNOLOGY, 2022, 57 (05) : 474 - 485
  • [47] Effects of crack tip plastic zone on corrosion fatigue cracking of alloy 690(TT) in pressurized water reactor environments
    Xiao, J.
    Qiu, S. Y.
    Chen, Y.
    Fu, Z. H.
    Lin, Z. X.
    Xu, Q.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 456 : 120 - 124
  • [48] Environmentally influenced fatigue cracking of Alloy A-286 in nuclear reactor coolant pump bolting
    Poehler, JC
    Hardies, RO
    PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 290 - 298
  • [49] Intergranular Stress Corrosion Cracking Growth Behavior of Ni-Cr-Fe Alloys in Pressurized Water Reactor Primary Water
    Arioka, Koji
    Yamada, Takuyo
    Miyamoto, Tomoki
    Aoki, Masanori
    CORROSION, 2014, 70 (07) : 695 - 707
  • [50] The mitigation of stress corrosion cracking of boiling water reactor structural components
    Cowan, RL
    CHEMISTRY AND ELECTROCHEMISTRY OF CORROSION AND STRESS CORROSION CRACKING: A SYMPOSIUM HONORING THE CONTRIBUTIONS OF R.W. STAEHLE, 2001, : 467 - 484