压力容器Issue(1)：20-24,61,6.DOI:10.3969/j.issn.1001-4837.2016.01.004
不锈钢冷堆工艺对锰镍钼低合金钢性能的影响研究
Impact Study of Stainless Steel Cold-cladding Process on Mn-Ni-Mo Low-alloy Steel Property
黄炳炎 1刘全印 2余平 1刘清会2
作者信息
- 1. 中国核动力研究设计院 核反应堆系统设计技术重点实验室，四川 成都 610213
- 2. 中核集团西安核设备有限公司，陕西 西安 710021
- 折叠
摘要
Abstract
The pressure boundary materials of nuclear islands main equipment generally used Mn-Ni-Mo low-alloy steel materials,and inner surface of low-alloy steels in contact with coolant fluid need to weld overlay cladding of austenitic stainless steel for corrosion resistance.In order to study the impact that cold-cladding process(the first layer preheating and the subsequent layers no preheating)append on property of low-alloy steel HAZ,the stainless steel cladding coupons are respectively executed with strip overlay welding and shielded metal-arc overlay welding on 16MND5 low-alloy steel,and undergo a series of tests and examinations,such as hardness measurements,bend tests,layer-by-layer metallographic examination and layer-by-layer magnetic particle examination.The test results show that the joints quality is reliable when overlay cladding of austenitic stainless steel on Mn-Ni-Mo low-alloy steel surface is welded with cold-cladding process.关键词
核岛主设备/锰镍钼低合金钢/预热/冷堆Key words
nuclear islands main components/Mn-Ni-Mo low-alloy steel/preheat/cold-cladding process分类
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黄炳炎,刘全印,余平,刘清会..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,(1):20-24,61,6.
