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碳酸铵反萃TRPO流程中Np,Pu的工艺研究

碳酸铵反萃TRPO流程中Np,Pu的工艺研究[J]. 核化学与放射化学, 2003, 25(2): 106-106.
引用本文: 碳酸铵反萃TRPO流程中Np,Pu的工艺研究[J]. 核化学与放射化学, 2003, 25(2): 106-106.
STUDY ON STRIPPING PLUTONIUM AND NEPTUNIUM BY (NH_4)_2CO_3 IN TRPO PROCESS[J]. Journal of Nuclear and Radiochemistry, 2003, 25(2): 106-106.
Citation: STUDY ON STRIPPING PLUTONIUM AND NEPTUNIUM BY (NH_4)_2CO_3 IN TRPO PROCESS[J]. Journal of Nuclear and Radiochemistry, 2003, 25(2): 106-106.

碳酸铵反萃TRPO流程中Np,Pu的工艺研究

详细信息
  • 中图分类号: O614352;;O614353

STUDY ON STRIPPING PLUTONIUM AND NEPTUNIUM BY (NH_4)_2CO_3 IN TRPO PROCESS

  • 摘要: 探讨了使用碳酸铵反萃TRPO中Np和Pu的工艺条件。测定了反萃平衡时间、(NH4)2CO3质量浓度、反萃温度和有机相中U质量浓度对反萃率的影响。进行了模拟动力堆高放废液的串级实验。结果表明,(NH4)2CO3可以在反萃U的同时反萃Np,Pu,并且反萃过程无沉淀和界面污物生成。实验给出了高放废液中其它核素在流程物流中的分布。
    Abstract: Technological conditions of stripping Pu(Ⅳ) and Np(Ⅳ) by (NH4)2CO3 in TRPO process are discussed.The influence of (NH4)2CO3 mass concentraction,temperature and U mass concentration in organic phase on the stripping rate is investigated.The countercurrent tube experiment using simulated high level liquid waste from power reactor is also carried out.In these experiments,Pu(Ⅳ) and Np(Ⅳ) can be stripped off from TRPO organic phase along with U by (NH4)2CO3 and no precipitation or interface filth occurs during stripping process.The distribution of other nuclides in HLLW is presented.
  • [1] 宋崇立,GLATZJP,KOCHL 从高放废液中去除超铀元素的TRPO流程热实验[J] 清华大学学报,1996,36(6):102
    [2] BUSHRP,MILLSAL,STEARNML.ComparisonofthePlantRequirements,ProcessPerformanceandWasteArisingforPotentialProcessesforthePartitioningofHighLevelWaste[A].In:Global′95,InternationalConferenceonEvaluationofEmergingNuclearFuelCycleSystems[C].Versailles,France:TheFrenchSectionofANSandtheFuelCycleandWasteManagementDivision,1995.232~239.
    [3] 郭一飞,焦荣洲,梁俊福,等 TRPO流程中U的反萃Ⅱ (NH4)2CO3对U的反萃[J].核化学与放射化学,1999,21(2):115~117
    [4] 贾瑞和,刘秉仁,梁俊福,等 电沉积法制备镅、钚和镎的α源[J] 同位素,2000,13(3):135~141
    [5] 郭一飞,梁俊福,焦荣洲,等 分光光度法测定高放废液处理工艺中的U[J] 原子能科学技术,2000,34(3):252~258
    [6] 郭一飞,刘秀琴,梁俊福,等 237Np与233Pa的分离和测定[J].核化学与放射化学,2001,23(1):59~64
    [7] 姜圣阶,任凤仪,马瑞华,等 核燃料后处理工学[M] 北京:原子能出版社,1995 435
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出版历程
  • 收稿日期:  2002-09-02
  • 刊出日期:  2003-05-19

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