钍基熔盐堆核能系统中熔盐的蒸馏纯化与分离

    Purification and Separation of Fluoride Molten Salt in Thorium Molten Salt Reactors System by Low Pressure Distillation

    • 摘要: 氟盐具有化学与辐射稳定性高、热容量大、传热性能好、运行温度高和蒸汽压低等优点,被用作熔盐堆的燃料载体和冷却剂。随着熔盐堆技术的发展,开发熔盐的净化、回收工艺非常必要。熔盐减压蒸馏技术基于物质挥发性差异进行组分分离,由于过程操作简单、不引入新的物质等特点,在燃料处理过程中有广泛应用。利用减压蒸馏技术对钍基熔盐堆核能系统的载体盐回收、电解产物纯化、模拟燃料球去除浸渗熔盐等方面进行了研究。研究结果表明,含CsF、SrF2、LaF3和ThF4的FLiNaK盐经减压蒸馏处理,可从FLiNaK中除去SrF2和LaF3,去污因子分别为4.4×103和1.9×103,Th的去污因子为94;通过蒸馏可去除电解产物表面夹带的氟盐,纯化电解产物;燃料球中浸渗熔盐在1085 ℃下处理37 h可去除石墨球中94%的浸渗熔盐。

       

      Abstract: Fluoride molten salt has many advantages such as high chemical and radiation stability, high thermal conductivity and heat capacity, low vapor pressure and so on, so it is used as one of the best fuel carrier salts and coolant for the molten salt reactor (MSR). With the development of MSR technique, it is necessary to develop the technique for the recovery and purification of molten salt. The low pressure distillation was studied on the carrier salt recovery, electrolysis product treatment, and graphite fuel ball cleaning. The results show that the decontamination factor for SrF2 and LaF3 is 4.4×103 and 1.9×103 respectively, and the value for ThF4 is 94 in FLiNaK salt system. The entrained salt with cathode product after electrolysis is removed by vacuum distillation, and the salt immerged in the graphite ball can also be removed and the removal rate ratio is up to 94%.

       

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