核电站金属堆内构件设备用12Cr2Mo1合金钢锻件落锤试验  

RTNDT drop weight test of no ductility transition temperature for 12Cr2Mo1 alloy steel forgings used for the reactor internals in nuclear power station

作　　者：韩建成[1] 王毅[1] 吴志军[1] 石长仁 

机构地区：[1]华能山东石岛湾核电有限公司,山东荣成264312

出　　处：《中国电力》2011年第4期67-70,共4页Electric Power

摘　　要：12Cr2Mo1合金钢锻件是高温气冷堆核电站示范工程金属堆内构件设备所用主体材质,为保证该材质在反应堆整个寿命期内的性能不发生失效,在制造时要求进行无延性转变温度RTNDT小于等于-25℃的落锤试验,而国内锻件生产企业以往从无此技术要求的铬钼合金钢锻件制造经验和实践活动,为实现在高温堆核岛主设备上的成功应用通过试验和科研攻关掌握了其核心制造技术。介绍了12Cr2Mo1材质锻件在制造过程中所出现的质量问题、原因分析、采取的改进措施及取得成效等,将对今后GW级高温堆核电设备的国产化用材提供借鉴。12Cr2Mol alloy steel forging material is widely used for reactor internals in the demonstrate project of high temperature gas-cooled reactor nuclear power plant. In order to avoid the failure of properties of the material during the service life cycle of the reactor, drop weight test under the condition of R TNDT 〈-25 ℃ was required for the material manufacturing. Chinese manufacturers have less experience in the manufacturing before the project. To master the key manufacturing technique, experiments and research were carried on. The quality problems occurred in the manufacturing of the material, the cause analysis, improvement approach, and the achieved effects were introduced, which will provide a good experience for the domestic material application in 1000 MW high temperature gas-cooled reactor nuclear power plant.

关 键 词：高温气冷堆 金属堆内构件 12Cr2Mo1合金钢锻件 落锤试验 

分 类 号：TG115.5[金属学及工艺—物理冶金]