大型SA508.Gr3低合金钢锻件夹杂物断裂行为分析

吴义党; 张斌; 杨志鹏; 乔木; 张茂龙

doi:10.12073/j.hjxb.2019400127

大型SA508.Gr3低合金钢锻件夹杂物断裂行为分析

1.
中广核工程有限公司深圳 518124
2.
上海电气核电设备有限公司上海 201306

基金项目: 国家能源核电工程建设技术研发（实验）重点资助项目

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- 收稿日期: 2017-12-12

Fracture behavior analysis of inclusions in large forgings of SA508.Gr3 low alloy steel

1.
China Nuclear Power Engineering Co., Ltd., Shenzhen 518124, China
2.
Shanghai Electric Nuclear Power Equipment Co., Ltd., Shanghai 201306, China

摘要

摘要: 通过模拟拉伸试验，研究焊接热循环条件下大型SA508.Gr3低合金钢锻件夹杂物断裂行为，结果表明，大型SA508.Gr3低合金钢锻件在焊接热循环条件下，当锻件母材中微小冶金为近似圆形或孔洞时，母材在存在有圆形缺口的条件下，仍有较好的塑性变形能力，断后伸长率达到20%以上，高温拉伸中不易产生裂纹；锻件母材中微小冶金存在尖锐角度且夹杂物超过临界尺寸时，母材在热循环作用下会产生0.2%应变损失，在锐角处容易诱发裂纹. 在实际生产中需要对母材中超过临界尺寸的尖锐角度的缺欠应进行消缺处理.
- 核岛主设备 /
- 锻件 /
- 冶金缺欠 /
- 临界尺寸 /
- 裂纹
Abstract: The fracture behavior of inclusions in large SA508.Gr3 low alloy steel forgings under welding thermal cycling was studied by simulating tensile test. The results show that the large SA508.Gr3 low alloy steel forgings with circular notches still have good plastic deformation ability under welding thermal cycling conditions, and more than 20% elongation is obtained. Cracks are not easy to occur in high temperature tension. When the micro-metallurgy in the forging base metal has sharp angle and the inclusions exceed the critical size, the base metal will have 0.2% strain loss under thermal cycling, and the cracks are easy to induce at the sharp angle area. In actual production, it is necessary to eliminate the deficiency of sharp angle exceeding critical size in base metal.
- nuclear island main equipment /
- forging /
- metallurgical defect /
- critical size /
- crack

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参考文献(10)

[1]	Corner A, Venables D, Spenec A, et al. Nuclear power, climate change and energy security:exploring British public attitudes[J]. Energy Policy, 2011, 39(9):4823-4833.
[2]	欧阳予,汪达升.国际核能应用及其前景展望与我国核电的发展[J].华北电力大学学报, 2007, 34(5):1-10 Ou Yangyu, Wang Dasheng. International nuclear power application and its prospect forecast and our country nuclear electricity development[J]. Journal of North Electric Power University, 2007, 34(5):1-10
[3]	Toth F L, Rogner H H. Oil and nuclear power:Past, present, and future[J]. Energy Economics, 2006, 28(1):1-25.
[4]	van der Zwaan B.C.C Nuclear energy:tenfold expansion or phase-out?[J]. Technological Forecasting and Social Change, 2002, 69(3):287-307.
[5]	陈剑辉,杨军,杨巨文,等.焊后热处理时间对奥氏体不锈钢焊缝熔敷金属力学性能的影响[J].焊接, 2014(11):39-44 Chen Jianhui, Yang Jun, Yang Juwen, et al. Influence of PWHT time on mechanical properties of austenitic stainless steel weld metal[J]. Welding&Joining, 2014(11):39-44
[6]	雷中黎,吴义党,乔木,等.核电厂核岛主设备制造焊接质量及其控制[M].北京:中国电力出版社, 2014.
[7]	中国机械工程学会焊接学会.焊接手册(焊接方法及设备)第3版[M].机械工业出版社, 2008.
[8]	王志锋,陈佩寅,吴伟,等.厚板带极埋弧堆焊温度场的有限元模拟[J].焊接学报, 2009, 30(1):89-92 Wang Zhifeng, Chen Peiyin, Wu Wei, et al. Finite element simulation of temperature field for submerged arc strip overlaying on thick plate[J]. Transactions of the China Welding Institution, 2009, 30(1):89-92
[9]	Jinya K, Hiroyuki N, Makoto D, et al. Assessments of residual stress due to weld-overlay cladding and structural integrity of reactor pressure vessel[C]//Proceeding of the ASME 2010 pressure vessels&piping division. K-PVP confenence, 2010, Bellevue, Washington, USA. 1-7.
[10]	吴义党,杨志鹏,刘鸣宇,等.核岛主设备带极埋弧堆焊层残余应力研究[J].南昌航空大学学报,自然科学版, 2016, 30(2):103-108 Wu Yidang, Yang Zhipeng, Liu Mingyu, et al. Study on residual stress of submerge arc strip cladding layer of nuclear island main equipment[J]. Journal of Nanchang Hangkong University,Natural Sciences, 2016, 30(2):103-108

施引文献(5)

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文章访问数: 310
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大型SA508.Gr3低合金钢锻件夹杂物断裂行为分析

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出版历程

Fracture behavior analysis of inclusions in large forgings of SA508.Gr3 low alloy steel

期刊类型引用(3)

其他类型引用(2)

计量

出版历程

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