核电机组Overlay堆焊修复技术的典型应用分析
Analysis of Typical Applications of Weld Overlay for Nuclear Power Units
- 2022年52卷第11期 页码:43-51
收稿:2022-03-25,
修回:2022-05-10,
纸质出版:2022-11-25
DOI: 10.7512/j.issn.1001-2303.2022.11.07
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收稿:2022-03-25,
修回:2022-05-10,
纸质出版:2022-11-25
移动端阅览
随着核电机组运行时间的延长,核电材料性能劣化和部件失效的几率随之增加。Overlay堆焊修复技术作为一种可实现无需去除缺陷金属的在线维修方法,已广泛应用于国内外核电设备及管道的纠正性维修和预防性维修。针对Overlay堆焊修复技术,分析技术原理并进行残余应力有限元模拟验证,研究了Overlay堆焊修复应用于核领域的标准规范要求,提出了基于失效模式及工况条件进行堆焊材料和堆焊方法的选择原则,梳理了Overlay堆焊修复技术在CRDM Ω焊缝和接管安全端异种金属焊缝维修中的应用情况,分析了堆焊结构和堆焊工艺的关键技术要求,研究了残余应力和结构完整性分析的相关结论,提出了后续Overlay堆焊修复技术的研究建议。研究表明,Overlay堆焊修复可实现结构补强和薄弱区域残余应力状态及分布的改善,堆焊后结构可满足长寿期服役安全要求。
With the extension of operation time of nuclear power units
the probability of degradation of nuclear materials and failures of nuclear components increase. As an on-line repair technology without removing defects
Weld Overlay (WOL) has been widely used in corrective maintenance or mitigation maintenance of nuclear equipments and pipelines at home and abroad. Technical principle was analyzed and residual stress was verified by finite element simulation to study the standard specifications of WOL applied in nuclear field
and the key principles for the selection of welding materials and welding methods of WOL were put forward. The typical applications of WOL on CRDM Ω welds and dissimilar metal welds were summarized
the key technical requirements of welding structure and process parameters of WOL were analyzed
the conclusions of residual stress and structural integrity evaluation were studied
and some research suggestions on WOL were proposed. The results show that WOL can strengthen the structure and improve the state and distribution of residual stress
and the structure after WOL can meet the requirements of service safety in a long operating period.
吴江涛 . 控制棒驱动机构密封焊缝缺陷修复技术研究 [D]. 上海 : 上海交通大学 , 2008 .
WU J T . Study of overlay technology for the repair of control rod drive mechanism canopy seal weld [D]. Shanghai : Shanghai Jiao Tong University , 2008 .
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 ( 9 ): 53 - 56 .
SUN H T , SHENG C Y , GAO C , et al . Application of OVERLAY technology in nuclear power equipment maintenance [J]. Welding & Joining , 2015 ( 9 ): 53 - 56 .
王宇欣 , 郭城湘 , 李华 , 等 . 核电厂焊接OVERLAY技术标准分析 [J]. 电焊机 , 2022 , 52 ( 2 ): 57 - 62 .
WANG Y X , GUO C X , LI H , et al . Study and Discussion on Weld OVERALY Technical Standards for Nuclear Power Plants [J]. Electric Welding Machine , 2022 , 52 ( 2 ): 57 - 62 .
French Association for Design , Construction and In-service inspection Rules for Nuclear Island Components . Design andConstruction Rules for Mechanical Components of PWR Nuclear Islands [S]. France : RCC-M , 2007 .
American Society of Mechanical Engineers . Boiler and Pressure Vessel Code [S]. New York : ASME , 2015 .
American Society of Mechanical Engineers . Boiler and Pressure Vessel Code,Code CaseN-504-4,Alternative Rules for Repair of Class 1,2,and 3 Austenitic Stainless Steel Piping [S]. New York : ASME , 2006 .
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 [S]. New York : ASME , 2008 .
American Society of Mechanical Engineers . Boiler and Pressure Vessel Code,Code Case N-666-1,Weld Overlay of Class 1,2,and 3 Socket Welded Connections [S]. New York : ASME , 2012 .
American Society of Mechanical Engineers . Boiler and Pressure Vessel Code,Code Case N-561-2,Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping [S]. New York : ASME , 2007 .
Control rod drive mechanism lower omega seal weld overlay repair for Qinshan unit l [R]. California : Structural Integrity Associates,Inc. , 2013 .
郑晓敏 . 岭澳核电厂L1号机组控制棒驱动机构泄漏问题 [J]. 核安全 , 2007 ( 2 ): 25 - 29 .
ZHENG X M . The Leakage Problem of CRDM in Lin-g'ao Station Unit 1 [J]. Nudear Safety , 2007 ( 2 ): 25 - 29 .
李建春 . 秦山核电站控制棒驱动机构泄漏分析及修复 [J]. 中国核电 , 2015 , 8 ( 3 ): 231 - 238 .
LI J C . Leakage Analysis and Repair Method for CRDM in Qinshan Nuclear Power Plant [J]. China Nuclear Power , 2015 , 8 ( 3 ): 231 - 238 .
Design and Analysis of a Weld Overlay Repair for CRDM Lower Canopy Seal Welds of Watts Bar Nuclear Plant [R]. California : Structural Integrity Associates,Inc. , 1997 .
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 ( 5 ): 75 - 79 .
LU Z C , XU X , WANG D S , 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 ( 5 ): 75 - 79 .
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 J C , ZHANG Y , LI P Z , et al . Crack Growth Analysis of Ω Seal Overlay Weld Repair for CRDM [J]. Nuclear Power Engineering , 2016 , 37 ( S2 ): 11 - 13 .
芦丽莉 , 林方强 , 伍建文 , 等 . 核电厂控制棒驱动机构上部Ω密封焊缝堆焊维修工艺 [J]. 电焊机 , 2019 , 49 ( 7 ): 19 - 26 .
LU L L , LIN F Q , WU J W , et al . Overlaying repair technology for the upper Ω seal weld of control rod drive mechanism in nuclear power plant [J]. Electric Welding Machine , 2019 , 49 ( 7 ): 19 - 26 .
文忠 , 俞照辉 , 闫国华 , 等 . 核电控制棒驱动机构密封焊缝激光堆焊修复工艺研究 [J]. 热加工工艺 , 2017 , 46 ( 23 ): 176 - 179 .
WEN Z , YU Z H , YAN G H , et al . Study on Laser Cladding Repair of Canopy Weld of Nuclear Power Control Rod Drive Mechanism [J]. Hot Working Technology , 2017 , 46 ( 23 ): 176 - 179 .
Bamford W , Newton B , Seeger D . Recent Experience with Weld Overlay Repair of Indications in Alloy 182 Butt Welds in Two Operating PWRs [R]. ASME Pressure Vessels & Piping/icpvt-11 Conference , 2006 .
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-A [R]. EPRI,Palo Alto,CA : 2010 .1021014.
Doug Killian . EPRI-NRC Welding Residual Stress Model Validation Program-Phase Ⅳ-Cold Leg Nozzle Optimized Weld Overlay [R]. NRC/Industry WRS FEA Validation Meeting , 2011 .
张世伟 , 陈学德 , 张勇 , 等 . 秦山核电厂稳压器管嘴DMW焊缝堆焊修复残余应力分析 [J]. 核动力工程 , 2016 , 37 ( S2 ): 4 - 6 .
ZHANG S W , CHEN X D , ZHANG Y , et al . Analysis of Weld Overlay Residual Stress for Dissimilar Metal Welds in Qinshan Nuclear Power Plant [J]. Nuclear Po-wer Engineering , 2016 , 37 ( S2 ): 4 - 6 .
林方强 , 王建 , 罗绪珍 , 等 . 核电管道安全端异种金属焊接接头表面堆焊的有限元分析 [J]. 电焊机 , 2016 , 46 ( 7 ): 129 - 133 .
LIN F Q , WANG J , LUO X Z , et al . Finite element analysis of the overlay welding on a nuclear nozzle safe-end dissimilar metal weld joint [J]. Electric Welding Machine , 2016 , 46 ( 7 ): 129 - 133 .
DuPont J N , Lippold J C , Kiser S D . Welding Metallurgy and Weldability of Nickel Base Alloys [M]. Wi-ley and Sons Inc. Hoboken , 2009 .
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 Di-ssimilar Metal Welds in Class 1 Items [S]. New York : ASME , 2017 .
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