核动力装置回路水中氚监测用于传热管破损诊断的可行性分析

蒸汽发生器传热管易发生破损,对其破损进行监测是反应堆工艺监测的重要内容之一。分析了核动力装置回路水中氚的产生机理及事故情况下氚在回路水中的迁移过程,利用液体闪烁计数器测量了4个核动力装置一、二回路水中氚的放射性活度浓度。结果表明,一回路水净化后的氚放射性活度浓度与相应的二回路水相比高出2个数量级,分别为633,893,188和394倍,可见利用二回路水中氚的放射性活度浓度来监测蒸汽发生器传热管是否发生破损是可行的。后期,还需对氚的在线实时监测开展深入研究。

Feasibility on the Rupture-Diagnosing of Heat-Transfer Pipe by Tritium Monitoring in Loop Water of Nuclear Power Plant

Heat-transfer pipe rupture detection of steam generator is an important content of the reactor process monitoring.The producing mechanism of tritium in nuclear power plant loop water and the transi tion process of tritium in loop water under accident were discussed firstly.And then,the radioactive con centration of tritium in primary and secondary loop water from four nuclear power plants were measured re spectively by using liquid scintillation counter.Experimental results show that the activity concentration of tritium in the purified primary loop water is at least two orders of magnitude,namely 633,893,188 and 394 times higher than that of the secondary loop water respectively.This indicates that it would be feasible to diagnose the heat-transfer pipe rupture detection of steam generator by monitoring the radioactive con centration of tritium in secondary loop water,however,further research of on-line monitoring techniques of tritium is needed.