Inorganic Chemicals Industry ›› 2023, Vol. 55 ›› Issue (7): 97-102.doi: 10.19964/j.issn.1006-4990.2022-0573

• Environment·Health·Safety • Previous Articles     Next Articles

Study on vacuum distillation purification technology for radioactive waste salt

LI Xun1(), JIA Yanhong1, DOU Qiang2, YANG Yang2   

  1. 1. China Institute of Atomic Energy,Beijing 102413,China
    2. Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China
  • Received:2022-09-23 Online:2023-07-10 Published:2023-07-13

Abstract:

In order to reduce the amount of radioactive waste salt generated in the process of molten salt electrolysis of plutonium and relieve the stress in the subsequent process of treatment and disposal of radioactive waste,the vacuum distillation technology was studied by using NaCl-KCl-CeO2 mixed molten salt as simulative material.The effects of CeO2 concentration,temperature and pressure on the experiment results were investigated.The results showed that in the range of CeO2 mass fraction of 5%~15%,temperature of 825~925 ℃ and pressure of 0.1~66 Pa,the purification coefficient of Ce could reach above 103,the purity of distillate salt and residual CeO2 was equal to that before the mixed melting,and the recovery of molten salt and CeO2 was stable above 98%.After distillation,the distribution ratio of NaCl-KCl molten salt remained unchanged and could be reused in molten salt electrolysis.The good performance of vacuum distillation purification technology in simulated material experiments provided an alternative route for subsequent radioactive waste salt treatment.

Key words: plutonium, radioactive waste salts, molten salt electrolysis, vacuum distillation

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