Treatment of spent radioactive organic solvents from nuclear fuel reprocessing plant: Advances and perspectives

被引:5
|
作者
Wang, Chao [1 ]
Yu, Guoce [1 ,2 ]
Wang, Jianlong [1 ,2 ,3 ]
机构
[1] Tsinghua Univ, Lab Environm Technol, INET, Beijing 100084, Peoples R China
[2] Tsinghua Univ, Beijing Key Lab Radioact Waste Treatment, Beijing 100084, Peoples R China
[3] Tsinghua Univ, INET, Energy Sci Bldg, Beijing 100084, Peoples R China
关键词
Radioactive organic solvent; Volume reduction; Advanced oxidation process; Treatment and disposal; Reprocessing; OXIDATION; SOLIDIFICATION; RESINS; WASTE; WATER; TECHNOLOGY; MANAGEMENT;
D O I
10.1016/j.nucengdes.2024.113138
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The mixture of tributyl phosphate/odourless kerosene (TBP/OK) is employed in the plutonium uranium extraction (PUREX) process for nuclear fuel cycle. The radioactive spent organic solvent is produced during the operation of the nuclear fuel reprocessing plants. The treatment of the spent organic solvents containing tributyl phosphate in the reprocessing plants remains a difficult problem due to the complex chemical composition and radioactivity. In this paper, different treatment and disposal technologies of spent organic solvent were analyzed, summarized and compared, including advanced oxidation processes, such as dry oxidation (incineration and pyrolysis), wet oxidation (acid digestion and direct oxidation, plasma treatment, supercritical water oxidation, mediated electrochemical oxidation and Fenton oxidation), solidification, distillation, alkaline hydrolysis and absorption. The principles of the treatment and disposal technologies, their characteristics and applications were briefly introduced, and the future research directions were discussed. This is the first review article to systematically summarize and analyze the treatment of spent radioactive organic solvents from nuclear fuel reprocessing plant, which is helpful for readers to comprehensively understand the current status and development direction of the treatment of radioactive waste organic solvents.
引用
收藏
页数:11
相关论文
共 50 条
  • [41] An analysis of development and research on spent nuclear fuel reprocessing
    Silverio, Leticia Borges
    Lamas, Wendell de Queiroz
    ENERGY POLICY, 2011, 39 (01) : 281 - 289
  • [43] REPROCESSING OF SPENT NUCLEAR-FUEL - STATUS AND PROSPECTS
    EBERT, K
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1988, 27 (06): : 361 - 365
  • [44] Validation of analytical methods for nuclear spent fuel reprocessing
    Rivier, C.
    Roudil, D.
    Rigaux, C.
    Cames, B.
    Adnet, J. M.
    Eysseric, C.
    Tuffery, B.
    Ruas, A.
    Lamouroux, C.
    Casanova, F.
    Organista, M.
    Pochon, P.
    PROGRESS IN NUCLEAR ENERGY, 2014, 72 : 115 - 118
  • [45] REPROCESSING SPENT NUCLEAR-FUEL - THE FRENCH CONNECTION
    DICKSON, D
    AMBIO, 1983, 12 (02) : 127 - 129
  • [46] Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing
    Kozhokar, I. A.
    Kharitonov, V. V.
    ATOMIC ENERGY, 2024, 135 (5-6) : 264 - 274
  • [47] Reprocessing spent nuclear fuel with supercritical carbon dioxide
    Wai, Chien M.
    SEPARATIONS FOR THE NUCLEAR FUEL CYCLE IN THE 21ST CENTURY, 2006, 933 : 57 - 67
  • [48] Hydrophilic Chelators for Aqueous Reprocessing of Spent Nuclear Fuel
    Wang, Yufei
    Shield, Katherine M.
    Abergel, Rebecca J.
    SEPARATION AND PURIFICATION REVIEWS, 2024, 53 (02): : 119 - 137
  • [49] Simulation of Electrolyzer Processes for the Reprocessing of Spent Nuclear Fuel
    A. E. Galashev
    V. V. Stakhanov
    Yu. P. Zaikov
    High Temperature, 2020, 58 : 426 - 435
  • [50] Numerical simulations of nuclear fuel reprocessing plant subjected to the free drop impact of spent fuel cask and fuel assembly
    Yang, Y. H.
    Dai, W. Y.
    Huang, T.
    Wu, H.
    NUCLEAR ENGINEERING AND DESIGN, 2021, 385 (385)