核电接管安全端308L/309L异种金属焊接接头拉伸断裂行为Tensile fracture behavior of nuclear safe-end 308L/309L dissimilar metal welded joints
罗炯,张十庆,王宏,刘洋
摘要(Abstract):
对核电接管安全端异种金属焊接接头(SA508-3-308L/309L-316L)进行拉伸、硬度试验及显微组织观察,确定接头拉伸断裂位置并研究断裂位置产生原因。结果表明:焊缝在接头具有最低强度及塑性,断裂位置为焊缝隔离层;隔离层中铁素体大部分呈板条状,因此隔离层裂纹扩展穿透两相界面相对较少,裂纹扩展阻力更小;隔离层相对于对接焊缝硬度更高,隔离层具有高的位错密度,因此残余应力大,导致硬度升高,降低隔离层临界塑性变形能力;焊缝与SA508-3钢为低强度匹配,高的三轴应力及塑性应变主要分布在隔离层内,裂纹更易萌生。
关键词(KeyWords): 异种金属焊接;拉伸;断裂位置;核电接管安全端;308L/309L
基金项目(Foundation): 工业转型升级强基工程(TC150B5C0/20);; 重庆市重点产业共性关键技术创新专项(cstc2015zdcy-ztzx50002)
作者(Author): 罗炯,张十庆,王宏,刘洋
DOI: 10.13289/j.issn.1009-6264.2017-0462
参考文献(References):
- [1]李光福.压水堆压力容器接管-主管安全端焊接件在高温水中失效案例和相关研究[J].核技术,2013,36(4):232-237.LI Guang-fu.Failure cases of welds between pressure vessel nozzle and main pipe safe-end in high temperature water environments and relevant research[J].Nuclear Techniques,2013,36(4):232-237.
- [2]Jang C,Lee J,Kim J S,et al.Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel[J].International Journal of Pressure Vessels&Piping,2008,85(9):635-646.
- [3]Jin W K,Lee K,Kim J S,et al.Local mechanical properties of Alloy 82/182 dissimilar weld joint between SA508 Gr.1a and F316SS at RT and 320℃[J].Journal of Nuclear Materials,2009,384(3):212-221.
- [4]Fang K W,Li G J,Li G F,et al.Microstructures and mechanical properties of dissimilar metal weld A508/52M/316L used in nuclear power plants[J].Key Engineering Materials,2011,479:40-47.
- [5]Wang H T,Wang G Z,Xuan F Z,et al.Fracture mechanism of a dissimilar metal welded joint in nuclear power plant[J].Engineering Failure Analysis,2013,28(2):134-148.
- [6]Qin R,Duan Z,He G.Microstructure and ductility-dip cracking susceptibility of circumferential multipass dissimilar weld between20MND5 and Z2CND18-12NS with Ni-base filler metal 52[J].Metallurgical&Materials Transactions A,2013,44(10):4661-4670.
- [7]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].Journal of Nuclear Materials,2008,378(2):197-210.
- [8]Weichih C,Huang J Y,Leuwen T.Microstructure and stress corrosion cracking behavior of the weld metal in alloy 52-A508dissimilar welds[J].Materials Transactions,2011,52(1):12-19.
- [9]Ming H,Zhang Z,Wang J,et al.Microstructural characterization of an SA508-309L/308L-316L domestic dissimilar metal welded safe-end joint[J].Materials Characterization,2014,97:101-115.
- [10]Li G F,Yuan Y F,Lu X.Microstructure and stress corrosion cracking of dissimilar metal weld 16MND5/309L/308L/Z2CND18-12N used for connecting reactor pressure vessel to piping in nuclear power plants[J].Procedia Engineering,2015,130:1572-1579.
- [11]Dong L,Peng Q,Han E H,et al.Stress corrosion cracking in the heat affected zone of a stainless steel 308L-316L weld joint in primary water[J].Corrosion Science,2016,107:172-181.
- [12]孙晓娜,雷毅,张鹰.厚板奥氏体不锈钢焊缝显微组织分析[J].金属热处理,2006,31(10):21-23.SUN Xiao-na,LEI Yi,ZHANG Ying.Microstructure analysis of weld joint for austenitic stainless steel thick plate[J].Heat Treatment of Metals,2006,31(10):21-23.
- [13]Dehmolaei R,Shamanian M,Kermanpur A.Microstructural characterization of dissimilar welds between alloy 800 and HP heatresistant steel[J].Materials Characterization,2008,59(10):1447-1454.
- [14]杨敏,李长香,罗英,等.核岛主设备接管与安全端对接焊缝焊接材料选择对焊缝质量的影响[C]//中国机械工程学会,第十五次全国焊接学术会议论文集,西宁,2010:227-231.
- [15]Deng D,Ogawa K,Kiyoshima S,et al.Prediction of residual stresses in a dissimilar metal welded pipe with considering cladding,buttering and post weld heat treatment[J].Computational Materials Science,2009,47(2):398-408.
- [16]荆洪阳,朱政强,霍立兴,等.强度匹配对核容器用钢A508-Ⅲ焊接接头断裂行为的影响[J].焊接学报,2002,23(5):35-37.JING Hong-yang,ZHU Zheng-qiang,HUO Li-xing,et al.Effect of strength mis-matching on fracture behavior for nuclear pressure vessel steel A508-Ⅲwelded joints[J].Transactions of The China Welding Institution,2002,23(5):35-37.
文章评论(Comment):
|
||||||||||||||||||
|
||||||||||||||||||