摘要
介绍了以岭澳核电站一期控制棒驱动机构为技术基础的百万千瓦级压水堆核电站用控制棒驱动机构的改进设计,及样机制造过程中的材料替代和技术简化,解决了顶部Ω密封焊缝带来的泄漏问题,以及因钩爪组件中的弹簧与运动件接触摩擦可能造成的机械动作延迟问题;介绍了样机的冷态性能试验,对冷态性能试验过程中出现的滑步现象进行分析并阐述了解决方案。
At Ling＇ao Nuclear Power Plant phase I, a 1000 MWe PWR, the control rod drive mechanism （CRDM） has been improved in the design, with some material substitutions and simplification of the manufacturing technology The new design solved the problem of Ω-type weld leakage in upper part of the CRDM, and mechanical movement delay problem caused probably by friction between the spring and movable components. Step loss occurred during a fimction test of the prototype CRDM under atmospheric pressure and ambient temperature. This was analyzed and a further solution was employed.
出处
《核技术》
CAS
CSCD
北大核心
2011年第11期860-865,共6页
Nuclear Techniques
关键词
控制棒驱动机构
样机研制
冷态性能试验
滑步
Control rod drive mechanism, Prototype research and development, Function test, Step-loss
