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作 者:林天龙 苏志勇[2] 王用超[2] 姜圣翰[2] Lin Tianlong;Su Zhiyong;Wang Yongchao;Jiang Shenghan(Navy Part,Beijing 100841,China;Nuclear Power Institute of China,Chengdu 610014,China)
机构地区:[1]海军某部,北京100841 [2]中国核动力研究设计院,成都610014
出 处:《核安全》2020年第2期29-32,共4页Nuclear Safety
摘 要:为了解决减少反应堆压力容器内活化腐蚀产物进入保存水池的问题,本文给出了活化腐蚀产物移除和收集的基本研究思路。打开压力容器端盖前,借助高速水流使活化腐蚀产物松动,并采用机械过滤的方式去除部分腐蚀产物,随后将取出的堆内构件放入内置活化产物去除装置的过渡水池,待出水悬浮物指标达到预设数值后,将堆内构件转移至堆内构件暂存保存水池中。该研究方案基于工程需求,已成功应用于反应堆退役工作中。In order to solve the problem of reducing the entry of activated corrosion products in the reactor pressure vessel into the storage tank, the basic research ideas of removal and collection of activated corrosion products are given. Before opening the end cover of the pressure vessel, the high-speed water flow is used to loosen and activate the corrosion products and part of the corrosion products are removed by mechanical filtration.Subsequently, the removed internals are put into a transition pool with an activated product removal device built in, and after the effluent suspended substance index reaches a preset value, the internals are transferred to the internals temporary storage pool. Based on engineering requirements, the research scheme has been successfully applied to decommissioning of reactors.
分 类 号:TL353[核科学技术—核技术及应用]
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