试析氢致核电蒸汽发生器管板堆焊GH690耐蚀层裂纹影响
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- 英文论文题名：Effect analysis of hydrogen on cracks in GH690 corrosion-resistant cladding of nuclear steam generator tube-plate
- 论文作者：田洪志
- 英文论文作者：Tian Hong-zhi ; State Nuclear Power Engineering Company Co. ; Ltd.
- 年：2015
- 作者机构：国核工程有限公司;
- 论文关键词：GH690合金 ; 堆焊层裂纹 ; SA508Gr.3合金 ; 晶体结构
- 英文论文关键词：GH690 Alloy ; buttering cracks ; SA508 Gr.3 alloy ; crystal structure
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第5册（核材料分卷、辐射防护分卷）
- 语种：中文
- 分类号：TG455
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：7
- 文件大小：865k
- 原文格式：O
- 会议级别：全国
摘要
通过分析核电蒸汽发生器管板的镍基GH690合金堆焊层裂纹发生位置和堆焊母材中不同氢含量,考察管板锻件中氢含量及异种材料晶体结构对氢的溶解度和扩散行为不同对堆焊后裂纹发生的原因规律。结果表明:裂纹产生的倾向随着基体母材材料中的氢含量的增加而逐渐增大;实践表明把氢含量控制在1 ppm以下以及焊接时尽量控制氢的吸入可以有效避免裂纹的产生;由于堆焊金属GH690合金是奥氏体面心结构,母材SA508Gr.3是体心立方结构,氢在面心立方结构中的溶解度大于体心立方,而其扩散系数则在体心立方结构中远大于面心立方,所以裂纹基本发生在堆焊层下部,这是裂纹常在母材中分布的原因。
Analyzing the crack position on GH690 corrosion-resistant cladding and the difference of hydrogen content in base material of nuclear Steam Generator tube-plate,investigate the cause and regulation of crack after cladding by hydrogen solubility and diffusion caused by hydrogen content of tube-plate forging and crystal structure of heterogeneous material.The conclusion demonstrates that the tendency of crack is upward by the increase of hydrogen content of base material.The practice shows that cracks could be effectively avoided by controlling the hydrogen content lower than 1 ppm and absorption of H during welding.The cladding material GH690 alloy is austenitic face-center structure and base material SA508 Gr.3 is body-center cubical structure.As the solubility of hydrogen in face-center cubical structure is higher than that in body-center cubical structure while the diffusion coefficient in body-center cubical structure is much larger than that in face-center cubical structure,the cracks occur at the fusion area of base metal.
Analyzing the crack position on GH690 corrosion-resistant cladding and the difference of hydrogen content in base material of nuclear Steam Generator tube-plate,investigate the cause and regulation of crack after cladding by hydrogen solubility and diffusion caused by hydrogen content of tube-plate forging and crystal structure of heterogeneous material.The conclusion demonstrates that the tendency of crack is upward by the increase of hydrogen content of base material.The practice shows that cracks could be effectively avoided by controlling the hydrogen content lower than 1 ppm and absorption of H during welding.The cladding material GH690 alloy is austenitic face-center structure and base material SA508 Gr.3 is body-center cubical structure.As the solubility of hydrogen in face-center cubical structure is higher than that in body-center cubical structure while the diffusion coefficient in body-center cubical structure is much larger than that in face-center cubical structure,the cracks occur at the fusion area of base metal.
引文
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[2]上海交通大学核科学与工程学院编写组.反应堆材料学[M].上海:中电投核电培训教材,2009:121.
[3]王跃辉,朱伟青,李一清,等.无损检验概论及民用核安全设备基本知识[M].上海:民用核安全设备无损检验专业技术教材,2011:56.
[4]R R.Lowes,K.R Hutchinson,R.S.Chappo.Material Specification for SA-508/SA-508M Grade 3 class 2Forgings(sectionⅢ-NB)-Wstinghouse[A].USA:2009:4.
[5]JSW engineers group.The material analysis report about SA-508/SA-508M Grade 3 crack[A].Japan:2008:25.
[6]王章忠.材料科学基础[M].北京:机械工业出版社,2005:138-139.
[7]王章忠.反应堆材料学[M].北京:机械工业出版社,2005:140.
[8]褚武扬.断裂与环境断裂[M].北京:科学出版社,2000:85-89.
[9]冯端等.金属物理学[M].北京:科学出版社,2000:240-255.