快堆破损组件铅清洗阱功能验证试验研究  被引量:1

Study of Lead Cleaning Trap Function Verification Test of Fast Reactor Failed Fuel Assembly

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作  者:李君瑜[1] 俞晓琛[1] 李凌霄[1] 刘绩伟[1] 

机构地区:[1]中国原子能科学研究院,北京102413

出  处:《核科学与工程》2017年第5期721-726,共6页Nuclear Science and Engineering

摘  要:快堆采用钠作为冷却剂,破损组件由于粘附大量的钠必须经过清洗除钠后才可以放置于乏燃料水池中保存。铅清洗是快堆破损组件除钠的一种工艺。本文主要对铅清洗工艺中的关键设备——铅清洗阱的结构进行了研究,并通过试验的方法对其结构进行了验证;还对影响清洗效果的因素进行了试验和分析。通过此功能验证试验,证明了铅清洗阱结构设计合理,为后续快堆电站组件铅清洗阱的设计和运行提供有益的参考。Sodium is used as the coolant of the fast reactor, and the failed fuel assembly should be cleaned before being placed in the spent fuel pool because of the large amount of sodium that is adhered. Lead cleaning is a process used for fast reactor failed fuel assembly cleaning. This paper mainly studied the function of lead cleaning trap that was the key equipment in lead cleaning process and the structure of lead cleaning trap was verified by this test. Then the factors influencing cleaning effect were tested and analyzed. Through this test, it is proved that the structure of lead cleaning trap is reasonable, which can provide a useful reference for the follow-up design and operation of lead cleaning trap of fast reactor plant failed fuel assembly.

关 键 词:块堆  清洗 模拟组件 

分 类 号:TL43[核科学技术—核技术及应用]

 

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