核电厂焊接OVERALY技术标准分析
Study and Discussion on Weld OVERALY Technical Standards for Nuclear Power Plants
- 2022年52卷第2期 页码:57-62
DOI: 10.7512/j.issn.1001-2303.2022.02.08
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王宇欣,郭城湘,李 华,等.核电厂焊接OVERALY技术标准分析[J].电焊机,2022,52(2):57-62.
WANG Yuxin, GUO Chengxiang, LI Hua, et al.Study and Discussion on Weld OVERALY Technical Standards for Nuclear Power Plants[J].Electric Welding Machine, 2022, 52(2): 57-62.
焊接OVERLAY技术是通过在原设计壁厚基础上增加耐蚀材料,改变原壁厚内表面的应力状态,从而抑制裂纹的产生或扩展,可用于在役维修或预防性维修。该技术在国外有着广泛的应用,在国内反应堆控制棒驱动机构(CRDM)修复上也有局部应用案例,但国内对此技术缺乏系统、完整的研究,制约了该技术的推广。文中通过ASME标准和文献研究,系统地梳理了焊接OVERLAY技术的分类,比较分析了几种技术的适用范围和特点。介绍了ASME-Ⅺ卷(2005年补遗)非强制性附录Q“1、2、3级奥氏体不锈钢管道焊接件的堆焊修复”,总结了标准演化过程,并对其关键标准条款进行了探讨,为焊接OVERLAY技术的国内推广和标准规范的制定提供了技术支撑。
Weld OVERLAY technology is to add corrosion-resistant materials on the basis of the original design wall thickness to change the stress state of the original inner surface, thereby inhibiting the generation or expansion of cracks. It can be used for in-service maintenance or preventive maintenance. The technology is widely used abroad, and has some application cases of CRDM repairing in China. However, the lack of systematic and complete technical research restricts the popularization of the technology. This article systematically sorts out the classification and standard evolution of Weld OVERLAY technology, compares and analyzes the application scope and characteristics by ASME standards and literature studying. This article introduces the Non mandatory Appendix Q of ASME BPVC.XI-2005, Weld Overlay Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping Weldments, summarizes the evolution process, analyzes the key standard clauses, and provides technical support for the promotion of this technology and the formulation of standards.
核电厂OVERLAYASME-Ⅺ卷标准研究
nuclear power plantweld OVERLAYASME-Ⅺstandard study
郑晓敏. 岭澳核电厂L1号机组控制棒驱动机构泄露问题[J]. 核安全, 2007(02), 25-29,45.
Zheng Xiaomin. The Leakage Problem of CRDM in Ling’ao Station Unit 1[J]. Nuclear Safety, 2007(02), 25-29,45.
鲁治诚, 徐晓, 王大胜, 等. 控制棒驱动机构上部Ω焊缝堆焊修复结构完整性分析[J]. 核动力工程, 2018, 39(05):75-79.
Lu Zhicheng, Xu Xiao, Wang Dasheng, et al. Integrity Analysis of Weld Overlay Repair Structure of Upper Ω Seal Weld of Control Rod Drive Mechanism[J]. Nuclear Power Engineering, 2018, 39(05):75-79.
卢丽莉, 王建, 罗绪珍, 等. CRDM上端Ω焊缝返修堆焊残余应力分析[J]. 东方电气评论, 2011, 25 (02):42-48.
Lu Lili, Wang Jian, Luo Xuzhen, et al. Residual Stress Analysis of Overlay Repair Technology Applied on Upper Ω Seal Weld of CRDM[J]. Dongfang Electric Review, 2011, 25 (02):42-48.
罗家成, 张勇, 李朋洲, 等. CRDM中部Ω密封环堆焊修复裂纹扩展分析[J]. 核动力工程, 2016, 37(S2):11-13.
Luo Jiacheng, Zhang Yong, Li Pengzhou, et al. Crack Growth Analysis of Ω Seal Overlay Weld Repair for CRDM[J]. Nuclear Power Engineering, 2016, 37(S2):11-13.
孙海涛, 盛朝阳, 高晨, 等. OVERLAY堆焊技术在核电设备维修中的应用[J]. 焊接, 2015(09):53-56,75.
Sun Haitao, Sheng Chaoyang, Gao Chen, et al. Application of OVERLAY welding technique to nuclear equipment maintenance and repairment[J]. Welding & Joining, 2015(09):53-56,75.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-740-2, Full Structural Dissimilar Metal Weld Overlay for Repair or Mitigation of Class 1, 2, and 3 Items Section XI, Division 1[S]. New York: ASME, 2008.
Electric Power Research Institute. Materials Reliability Program: Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs (MRP-169) Revision 1. EPRI, Palo Alto, CA: 2008. 1021014.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-754-1, Optimized Structural Dissimilar Metal Weld Overlay for Mitigation of PWR Class 1 Items Section XI, Division 1[S]. New York: ASME, 2013.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-847, Partial Excavation and Deposition of Weld Metal for Mitigation of Class 1 Items Section XI, Division 1[S]. New York: ASME, 2016.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-766-3, Nickel Alloy Reactor Coolant Inlay and Onlay for Mitigation of PWR Full Penetration Circumferential Nickel Alloy Dissimilar Metal Welds in Class 1 Items Section XI, Division 1[S]. New York: ASME, 2017.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-729-7, Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure- Retaining Partial-Penetration Welds Section XI, Division 1[S]. New York: ASME, 2019.
Electric Power Research Institute. Materials Reliability Program: Mechanical Stress Improvement Process (MSIP) Implementation and Performance Experience for PWR Applications (MRP-121). EPRI, Palo Alto, CA: 2004. 1009503.
Electric Power Research Institute. Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335). EPRI, Palo Alto, CA: 2016. 3002007392.
American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Code Case N-770-5, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities Section XI, Division 1[S]. New York: ASME, 2019. ☞ Page 108
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