摘要
通过监测反应堆压力容器钢服役过程中硬度的变化来表征其辐照损伤程度的方法日益引起研究界的关注。介绍了国内外在反应堆压力容器钢辐照脆化过程中硬度变化规律领域所开展的研究工作,并讨论了目前所取得的研究成果与存在的不足。最后提出了通过探索反应堆压力容器在服役时力学性能、硬度之间的潜在关联,以此为基础形成准无损评估技术,可为反应堆压力容器辐照监督提供一条新的思路。最后指出了对国产反应堆压力容器钢尽快开展辐照硬化研究工作的必要性与重要性。
To characterize the in-service reactor pressure vessel steels irradiation damage extent by monitoring its hardness properties′changes is provoking increasingly concern of researchers.The study on the hardness variation of reactor pressure vessel steels during its irradiation embrittlement procedure are introduced,the current research achievements and shortcomings are also discussed.Finally,the method of exploring the potential relevance between the mechanical properties and hardness properties of in-ser-vice reactor pressure vessel,developing the quasi-nondestructive evaluation techniques based on the above theories is pointed out.Finally,the necessity and importance of carrying out the research on the irradiation damage effects on the domestic reactor pressure vessel steels radiation hardening are pointed out.
作者
李承亮
陈骏
刘飞华
束国刚
LI Chengliang;CHEN Jun;LIU Feihua;SHU Guogang(Sate Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,China Nuclear Power Engineering Co.,Ltd,Shenzhen 518172)
出处
《材料导报》
EI
CAS
CSCD
北大核心
2017年第A01期184-187,197,共5页
Materials Reports
关键词
反应堆压力容器钢
辐照损伤
硬度
屈服强度
准无损评估技术
reactor pressure vessel steel
irradiation damage
hardness
yield strength
quasi-nondestructive evaluation techniques