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

作　　者：黄炳炎[1] 刘全印 余平[1] 刘清会 

机构地区：[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

出　　处：《压力容器》2016年第1期20-24,61,共6页Pressure Vessel Technology

摘　　要：核岛主设备承压边界一般采用锰镍钼低合金钢材料制造,与冷却剂接触的低合金钢内表面需要堆焊耐蚀奥氏体不锈钢。为研究不锈钢冷堆工艺(首层预热,后续堆焊层不预热)对低合金钢母材热影响区性能的影响,采用带极堆焊和手工电弧焊堆焊两种冷堆工艺在16MND5低合金钢试板上进行了不锈钢堆焊试验,对堆焊试板进行了硬度、弯曲、逐层金相和逐层磁粉检验等一系列试验和检验。试验结果表明,采用冷堆工艺在锰镍钼低合金钢上堆焊奥氏体不锈钢的质量是可靠的。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 austenitie 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 

分 类 号：TH142.2[一般工业技术—材料科学与工程] TL351[机械工程—机械制造及自动化]