核电厂热泵蒸发系统分离效率试验研究  

Experimental Study on Separating Efficiency of Heat Pump Evaporating System in Nuclear Power Plant

作　　者：刘勇 霍明 兰立君 盛成 Liu Yong;Huo Ming;Lan Lijun;Sheng Cheng(China Nuclear Power Design Company,LTD,Shenzhen,Guangdong,518172,China)

机构地区：[1]深圳中广核工程设计有限公司,广东深圳518172

出　　处：《核动力工程》2018年第4期141-143,共3页Nuclear Power Engineering

摘　　要：按照核电厂热泵蒸发系统的工艺设计要求,设计研发了一套热泵蒸发试验装置,研究热泵蒸发系统的蒸发分离效率。模拟含硼料液的蒸发分离试验结果表明,回流比和浓缩液的硼浓度对试验装置的蒸发分离效率影响较小,冷凝液的硼浓度均小于0.2 mg/L,远低于国内最严格的地方排放标准2 mg/L。利用Mg SO4进行的放射性替代试验显示,该试验装置对不易挥发放射性核素的去污因子可达105。试验装置在硼酸分离和放射性去污方面的性能均优于目前的同类设备,优异的性能为内陆厂址的"近零排放"理念提供了可行性。According to the design requirements of heat pump evaporating system of nuclear power plant, a set of testing installation was built and corresponding performances and efficiencies of separating process were researched. The results show as follows： the reflux ratio of evaporation and concentration in concentrate has low impact on separating efficiencies of the testing installation. The boron concentration in distillate is less than 0.2 mg/L, which is much lower than the most strict limit value（2 mg/L） of releasing to the environment. The results of radioactive alternative test by using Mg SO4, show that the decontamination factor of the test installation reaches 105. Generally, the performance of separating and decontaminating of test installation is much better than similar devices as known, which provided the feasibility of near-zero releasing for inland nuclear plant.

关 键 词：热泵蒸发 含硼废液处理 去污因子 

分 类 号：TL942[核科学技术—辐射防护及环境保护]