Analysis on Disbonding of Stainless Steel Overlay for Reactor Pressure Vessel

ZHU Kun; WU Yidang; ZOU Guowei

doi:10.7512/j.issn.1001-2303.2023.10.17

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Analysis on Disbonding of Stainless Steel Overlay for Reactor Pressure Vessel
Vol. 53, Issue 10, Pages: 109-114(2023)
DOI： 10.7512/j.issn.1001-2303.2023.10.17

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朱坤，吴义党，邹国伟.反应堆压力容器不锈钢堆焊层剥离问题分析及工艺控制［J］.电焊机，2023，53（10）：109-114.

ZHU Kun, WU Yidang, ZOU Guowei.Analysis on Disbonding of Stainless Steel Overlay for Reactor Pressure Vessel[J].Electric Welding Machine, 2023, 53(10): 109-114.
朱坤，吴义党，邹国伟.反应堆压力容器不锈钢堆焊层剥离问题分析及工艺控制［J］.电焊机，2023，53（10）：109-114. DOI： 10.7512/j.issn.1001-2303.2023.10.17.

ZHU Kun, WU Yidang, ZOU Guowei.Analysis on Disbonding of Stainless Steel Overlay for Reactor Pressure Vessel[J].Electric Welding Machine, 2023, 53(10): 109-114. DOI： 10.7512/j.issn.1001-2303.2023.10.17.

摘要

反应堆压力容器（简称RPV）属于核电厂的心脏设备，长期在高温、高压、强腐蚀和强辐射的环境下运行。不锈钢堆焊层剥离属于RPV制造中的重大问题，处理代价大。选取华龙一号RPV制造过程中发生的主螺栓孔堆焊和顶盖密封面堆焊层剥离案例，对不锈钢堆焊层剥离的影响因素进行分析研究，提出了预防不锈钢堆焊层剥离的工艺控制关键点，包括：焊接方法、焊接位置、焊接参数、搭接量、预热、焊接工位及操作规范，为后续华龙一号RPV的制造提供了技术积累和工程经验。

Abstract

The reactor pressure vessel (RPV) belongs to the heart equipment of nuclear power plants,which operates in the environment of high temperature, high pressure, strong corrosion and strong radiation for a long time.The stripping problem of stainless steel overlay is a major problem during RPV manufacturing process, and high cost to handle.In this paper, two stainless steel overlay stripping cases were selected to analyse, which appeared during main bolt holes and top cover sealing surface manufacturing process of “HPR1000” RPV. Through the analysis of influencing factors,the author summarizes 7 key points for welding process in the prevention of overlay stripping, including welding method, welding position, welding parameters, overlap amount, preheating, welding station and operation specifications. This provides a valuable accumulation and engineering experience for the subsequent manufacturing of “HPR1000” RPV.

关键词

反应堆压力容器堆焊层剥离工艺控制

Keywords

reactor pressure vesseloverlaydisbondingprocess control

references

张纪锋，崔凡，朱勃，等. 核反应堆压力容器主螺栓孔堆焊缺陷分析与质量控制［J］. 电焊机， 2021，51（11）：71-76.

ZHANG J F， CUI F， ZHU B， et al. Defect analysis and quality control of main bolt hole surfacing on nuclear reactor pressure vessel［J］.2021，51（11）：72-76.

张克静，陈耕耘，朱宇霆，等.核反应堆压力容器用焊条工艺量化评价研究［J］.电焊机，2022，52（9）：97-101.

ZHANG K J， CHEN G Y， ZHU Y T， et al. Study on Quantitative Evaluation of Welding Rod Process for Nuclear Reactor Pressure Vessel［J］. Electric Welding Machine， 2022， 52（9）： 97-101.

邓传印，熊建坤，徐健，等.堆焊方式对奥氏体不锈钢堆焊层组织和性能的影响［J］.电焊机，2022，52（8）：34-42.

DENG C Y， XIONG J K， XU J， et al. Effect of Different Welding Methods on Microstructure and Properties of Austenitic Stainless Steel Deposit Layer［J］. Electric Welding Machine， 2022， 52（8）： 34-42.

柳猛，刘飞，刘子寅，等. 核电站关键设备异种钢焊接接头16MND5/309L熔合线组织性能研究［J］. 电焊机， 2019， 49（7）：7-12.

LIU M， LIU F， LIU Z Y， et al. Research on microstructure and properties of 16MND5/309L bond line of dissimilar steel welded joints in key equipment of nuc-lear power plant［J］. Electric Welding Machine，2019， 49（7）：7-12.

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 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.

黄炳炎，刘全印，余平，等.不锈钢冷堆工艺对锰镍钼低合金钢性能的影响研究［J］.压力容器，2016，33（01）：20-24+61.

HUANG B Y，LIU Q Y，YU P，et al. Impact Study of Stainless Steel Cold-cladding Process on Mn-Ni-Mo Low-alloy Steel Property［J］. Pressure Vessel Technology，2016，33（01）：20-24+61.

左波，余燕，张茂龙.核电设备不锈钢堆焊层铁素体含量研究［J］. 焊接技术，2012（8）：10-12.

ZUO B，YU Y，ZHANG M L. Ferrite content in austenitic stainless steel cladding of nuclear power components［J］.Welding Technology，2012（8）：10-12.

高春华，邢芳，刘斌，等.不锈钢堆焊层裂纹的产生及解决措施［J］. 炼油与化工，2010（4）： 38-40.

GAO C H，XING F，LIU B，et al. Formation of cracks in stainless steel deposit welding layer and prevention measures［J］. Refining and Chemical Industry， 2010（4）： 38-40.

邹国伟，王伟波. “华龙一号”反应堆压力容器关键焊接技术［J］. 电焊机，2020，50（12）： 65-73.

ZOU G W，WANG W B. Key welding technology of HPR1000 reactor pre-ssure vessel［J］. Electric Welding Machine，2020，50（12）： 65-73.

刘鸣宇，吴义党，杨志鹏. CPR1000反应堆压力容器大面积不锈钢堆焊工艺探讨［J］. 热加工工艺，2021，41（05）：187-189.

LIU M Y，WU Y D，YANG Z P. Overview of Stainless Steel Cladding Technology on Reactor Pressure Vessel of CPR1000 Project［J］. Hot Working Technology，2021，41（05）：187-189.

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