摘要
为了有效评价经辐照后的反应堆压力容器的结构完整性,人们提出了多种表征反应堆压力容器用钢断裂韧性与温度之间的经验表达式。基于美国橡树岭国家实验室的断裂韧性测试数据,对目前常用的经验关系式进行了对比研究。结果表明,经修正后的ASME KⅠC曲线有最高保守性,未经修正的ASME KⅠC曲线在T-Tref低于-60℃时不够保守,主曲线5%下限具有足够的保守性,ASME Code Case N631提供的方法具有与ASME KⅠC曲线相似的保守性。
To assess the integrity of Reactor Pressure Vesse(RPV) after irradiation,several experiential expressions between RPV steel fracture toughness and temperature were suggested.Basing on the fracture toughness testing data of ORNL,these experiential expressions were compared and analyzed.It showed that adjusted ASME KⅠC curve is the most conservative one.The ASME KⅠCcurve has enough conservative in high T-Tref region,but less conservative in low T-Tref region.5% lower bound of master curve is conservative enough.ASME Code Case N631 is as conservative as ASME KⅠC curve.
出处
《压力容器》
北大核心
2011年第3期16-21,共6页
Pressure Vessel Technology
基金
国家863高技术研究发展计划资助项目(核电站承压设备检测与安全评价技术研究
编号:2009AA04Z421)
关键词
反应堆压力容器
断裂韧性
经验关系
温度
reactor pressure vesse(RPV)
fracture toughness
experiential expression
temperature