无机盐工业
主管:中海油天津化工研究设计院有限公司
主办:中海油天津化工研究设计院有限公司
   中海油炼油化工科学研究院(北京)有限公司
   中国化工学会无机酸碱盐专业委员会
ISSN 1006-4990 CN 12-1069/TQ
环境·健康·安全

放射性废盐的真空蒸馏净化技术研究

  • 李迅 ,
  • 贾艳虹 ,
  • 窦强 ,
  • 杨洋
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  • 1.中国原子能科学研究院放射化学研究所,北京 102413
    2.中国科学院上海应用物理研究所,上海 201800
李迅(1980— ),男,高级工程师,博士,主要从事高温熔盐化学冶金应用研究;E-mail:lix404@126.com

收稿日期: 2022-09-23

  网络出版日期: 2023-07-13

Study on vacuum distillation purification technology for radioactive waste salt

  • LI Xun ,
  • JIA Yanhong ,
  • DOU Qiang ,
  • YANG Yang
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  • 1. China Institute of Atomic Energy,Beijing 102413,China
    2. Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China

Received date: 2022-09-23

  Online published: 2023-07-13

摘要

为了降低钚熔盐电解过程中产生的放射性废盐量,减轻后续放射性废物处理处置过程中的压力,采用NaCl-KCl-CeO2混合熔盐作为非放模拟料,对真空蒸馏技术进行了研究。考察了CeO2浓度、温度和压力对蒸馏结果的影响。研究结果表明:在CeO2质量分数为5%~15%、温度为825~925 ℃、压力为0.1~66 Pa条件下,Ce的净化系数均可达到103以上,获得的馏分盐和残余物CeO2的纯度与混熔前相当,熔盐和CeO2的回收率均稳定在98%以上。蒸馏后NaCl-KCl熔盐组分配比不变,可以在熔盐电解中重复利用。真空蒸馏净化技术在模拟料实验中体现出的良好效果,为后续放射性废盐处理提供了备选路线。

本文引用格式

李迅 , 贾艳虹 , 窦强 , 杨洋 . 放射性废盐的真空蒸馏净化技术研究[J]. 无机盐工业, 2023 , 55(7) : 97 -102 . DOI: 10.19964/j.issn.1006-4990.2022-0573

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.

参考文献

1 林如山,何辉,唐洪彬,等.我国乏燃料干法后处理技术研究现状与发展[J].原子能科学技术202054(S1):115-125.
  LIN Rushan, HE Hui, TANG Hongbin,et al.Progress and development of dry reprocessing technology of spent fuel in China[J].Atomic Energy Science and Technology202054(S1):115-125.
2 张磊,林如山,陈辉,等.NaCl-KCl熔盐体系电解制备金属铈工艺研究[J].原子能科学技术202054(12):2306-2313.
  ZHANG Lei, LIN Rushan, CHEN Hui,et al.Electrolytic extraction of Ce from NaCl-KCl molten salt[J].Atomic Energy Science and Technology202054(12):2306-2313.
3 张磊,王有群,谢书宝,等.LiCl-KCl、NaCl-KCl和KCl熔盐体系中Ce(Ⅲ)的电化学行为[J].核化学与放射化学202143(5):379-386.
  ZHANG Lei, WANG Youqun, XIE Shubao,et al.Electrochemical behavior of Ce(Ⅲ) in LiCl-KCl,NaCl-KCl and KCl molten salt[J].Journal of Nuclear and Radiochemistry202143(5):379-386.
4 GARCIA E.High-temperature vacuum distillation separation of plutonium waste salts[C]∥Gaithersburg,MD:Efficient Separations and Processing Crosscuting Program 1996 Technical Exchange Meeting,1996:21-23.
5 REICHLEY-YINGER L, VANDEGRIFT G F.Recovery of plutonium and americium from chloride salt wastes by solvent extraction[J].Separation Science and Technology198823(12/13):1409-1421.
6 MUSCATELLO A C, NAVRATIL J D.Chloride anion exchange process for DOR and ER residue salts[R].Pittsburgh,PA:Rockwell International Corp.,1986.
7 SMITH W H, WEDMA D E.Electrodialysis reduces waste in the treatment of pyrochemical salt residues[J].The Actinide Research Quarterly19963:4-5.
8 CHRISTENSEN D C, WILLIAMS J D, MCNEESE J A,et al.Plutonium metal preparation and purification at Los Alamos-1984[R].
  Los Alamos,NM:Los Alamos National Laboratory,1984.
9 FIFE K W, WEST M H.Pyrochemical investigations into recovering plutonium from americium extraction salt residues[R].Los Alamos,NM:Los Alamos National Laboratory,1987.
10 BOURGèS G, FAURE S, FIERS B,et al.Vacuum distillation of plutonium pyrochemical salts[J].Procedia Chemistry20127:731-739.
11 CHO Y J, YANG H C, EUN H C,et al.Characteristics of oxidation reaction of rare-earth chlorides for precipitation in LiCl-KCl molten salt by oxygen sparging[J].Journal of Nuclear Science and Technology200643(10):1280-1286.
12 EUN H C, YANG H C, CHO Y J,et al.Separation of pure LiCl-KCl eutectic salt from a mixture of LiCl-KCl eutectic salt and rare-earth precipitates by vacuum distillation[J].Journal of Nu-
  clear Science and Technology,200744(10):1295-1300.
13 耿俊霞,窦强,王子豪,等.钍基熔盐堆核能系统中熔盐的蒸馏纯化与分离[J].核化学与放射化学201739(1):36-42.
  GENG Junxia, DOU Qiang, WANG Zihao,et al.Purification and separation of fluoride molten salt in thorium molten salt reactors system by low pressure distillation[J].Journal of Nuclear and Radiochemistry201739(1):36-42.
14 郑小强,窦强,程明,等.减压蒸馏法对熔盐堆载体盐中氧的去除研究[J].核技术202245(4):46-52.
  ZHENG Xiaoqiang, DOU Qiang, CHENG Ming,et al.Study on removal of oxide from carrier salt in molten salt reactor by vacuum distillation[J].Nuclear Techniques202245(4):46-52.
15 杨甜宏,罗艳,付海英,等.氟化物对LiCl-KCl熔盐蒸馏行为的影响[J].核技术201841(12):35-40.
  YANG Tianhong, LUO Yan, FU Haiying,et al.The influence of fluorides on the distillation behaviors of molten LiCl-KCl[J].Nuclear Techniques201841(12):35-40.
16 付海英,耿俊霞,杨洋,等.乏燃料干法后处理中的熔盐减压蒸馏技术[J].核技术201841(4):5-12.
  FU Haiying, GENG Junxia, YANG Yang,et al.Low pressure distillation technology of molten salt in spent fuel pyroprocessing field[J].Nuclear Techniques201841(4):5-12.
17 GENG Junxia, LUO Yan, FU Haiying,et al.Temperature and pressure effect on evaporation behavior of chloride salts using low pressure distillation[J].Progress in Nuclear Energy2022147:104212.
18 赖耀斌,徐建兵,李忠岐,等.真空蒸馏法综合回收稀土熔盐电解渣工艺研究[J].真空科学与技术学报202141(4):332-335.
  LAI Yaobin, XU Jianbing, LI Zhongqi,et al.Research on comprehensive recovery of rare earth electrolytic molten salt slag by vacuum distillation[J].Chinese Journal of Vacuum Science and Technology202141(4):332-335.
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