脉冲电流作用下核反应堆压力容器修复延寿技术
Performance Regeneration of Aged Nuclear Reactor Pressure Vessel under Pulsed Electric Current
张新房 1李弼谦 2周梦程 3张雅婷 2李澍2
作者信息
- 1. 北京科技大学冶金与生态工程学院,北京 100083;内蒙古科技大学轻稀土资源绿色提取与高效利用教育部重点实验室,内蒙古包头 014010;内蒙古科技大学稀土产业学院,内蒙古包头 014010
- 2. 北京科技大学冶金与生态工程学院,北京 100083
- 3. 内蒙古科技大学轻稀土资源绿色提取与高效利用教育部重点实验室,内蒙古包头 014010;内蒙古科技大学稀土产业学院,内蒙古包头 014010
- 折叠
摘要
核反应堆压力容器钢的使用年限直接决定了核电站的服役寿命.压力容器钢在中子辐照环境下长期服役会逐渐产生大量位错环和纳米团簇缺陷,导致材料脆化甚至失效,严重威胁核反应堆的安全运行.传统退火处理可使材料性能部分恢复,但需对压力容器进行整体拆卸,导致反应堆长时间停堆,造成巨大经济损失.作为一项绿色高效的技术,脉冲电流"原位"修复处理为实现核反应堆压力容器服役延寿提供了新途径.简要综述了脉冲电流修复机理、服役寿命预测方程构建以及实用案例,对未来核反应堆关键构件延寿技术的发展具有重大意义.
Abstract
The service life of nuclear reactor pressure vessel steel directly determines the service life of nuclear power plant.The long-term service of pressure vessel steel under neutron irradiation will grad-ually produce many dislocation loops and nanoclusters,resulting in material embrittlement and threaten-ing the safe operation of nuclear reactors.The traditional annealing treatment can partially restore the material properties,but the pressure vessel needs to be disassembled as a whole,resulting in a long shut-down of the reactor and huge economic losses.As a green and efficient technology,"in-situ"pulsed elec-tric current processing provides a new pathway to prolong the service life of nuclear reactor pressure ves-sel.This study provides a brief overview of the repair mechanism of pulse current,the construction of service life prediction equation and practical cases,which is of great significance for the development of life extension technology for key components of nuclear reactors in the future.
关键词
脉冲电流/核反应堆压力容器/辐照缺陷/性能修复/寿命预测Key words
pulsed electric current/nuclear reactor pressure vessel/irradiation-induced defects/per-formance repair/life prediction引用本文复制引用
出版年
2024
NETL
NSTL
万方数据