Studies of sorbent/ion-exchange materials for the removal of radioactive strontium from liquid radioactive waste and high hardness groundwaters

被引:134
|
作者
Marinin, DV [1 ]
Brown, GN
机构
[1] Russian Acad Sci, Inst Chem, Far E Dept, Vladivostok 690022, Russia
[2] Pacific NW Natl Lab, Richland, WA 99352 USA
关键词
low-level liquid radioactive waste; radioactive strontium; sorbent/ion-exchange materials;
D O I
10.1016/S0956-053X(00)00017-9
中图分类号
X [环境科学、安全科学];
学科分类号
08 ; 0830 ;
摘要
Different sorbents were studied in terms of their full-scale applicability for radioactive strontium removal in low-level liquid radioactive waste (LLRW) management. The following types of sorbent/ion-exchange materials were investigated: natural zeolite-clinoptilolite, modified natural clinoptilolite, synthetic zeolites, new synthetic crystalline materials selective to strontium, ion-exchange resins, and modified fiber sorbents. Simulated solutions for experimental tests were prepared according to the composition of one of the facilities at the Hanford nuclear site (Richland, WA, USA). The following experiments were performed at different concentrations of strontium and competing elements (calcium, on the first hand): batch tests for determination of strontium distribution coefficients, sorbent/ion-exchanger selectivity to strontium in time presence of calcium, and kinetic measurements of strontium uptake. Modifications of Amberlite and Duolite ion-exchange resins (Rohm and Haas, USA) and new synthetic crystalline materials - silicotitanate IE-911 (UOP, USA) and sodium titanate (Allied Signal, USA) - showed the highest distribution coefficients of strontium (K(d)similar to 2x10(4)-4x10(5) ml/g). For all materials, the K-d decreased significantly with increased calcium concentration. On the other hand, each of these sorbents showed poor selectivity to strontium in the presence of calcium. Newly developed sorbents (Institute of Chemistry, Vladivostok, Russia) based on a fiber matrix (FM and FP) showed the best relative selectivity to strontium followed by the natural zeolite (clinoptilolite extracted and produced in the USA). Synthetic zeolites (IE-96, TIE-96) had moderate values of both parameters (distribution coefficient and selectivity). Fiber sorption materials were also absolute leaders in kinetic measurements removing 40% to 60% of the strontium from solution within a few minutes. (C) 2000 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:545 / 553
页数:9
相关论文
共 50 条
  • [1] Modeling Ion-Exchange for Cesium Removal from Alkaline Radioactive Waste Solutions
    Smith, F. G., III
    Hamm, L. L.
    Aleman, S. E.
    Johnson, M. E.
    SEPARATION SCIENCE AND TECHNOLOGY, 2009, 44 (13) : 2983 - 3012
  • [2] ION-EXCHANGE AND ELECTRODIALYSIS IN LIQUID RADIOACTIVE-WASTE DECONTAMINATION
    RAUZEN, FV
    KULESHOV, NF
    TRUSHKOV, NP
    DUDNIK, SN
    SOVIET ATOMIC ENERGY, 1978, 45 (01): : 705 - 709
  • [3] Inorganic ion exchangers for strontium removal from radioactive waste : a review
    Inan, Suleyman
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2022, 331 (03) : 1137 - 1154
  • [4] Inorganic ion exchangers for strontium removal from radioactive waste : a review
    Süleyman İnan
    Journal of Radioanalytical and Nuclear Chemistry, 2022, 331 : 1137 - 1154
  • [5] DECONTAMINATION OF ALKALINE RADIOACTIVE-WASTE BY ION-EXCHANGE
    WILEY, JR
    INDUSTRIAL & ENGINEERING CHEMISTRY PROCESS DESIGN AND DEVELOPMENT, 1978, 17 (01): : 67 - 71
  • [6] Geocement immobilization of radioactive waste ion-exchange resins
    Li, Shaobin
    Cao, Hailin
    Krivenko, Pavle
    Petropavlovskii, Oleg
    Weng, Luqian
    PROCEEDINGS OF THE 2017 3RD INTERNATIONAL FORUM ON ENERGY, ENVIRONMENT SCIENCE AND MATERIALS (IFEESM 2017), 2017, 120 : 576 - 580
  • [7] Removal of iodide ion from simulated radioactive liquid waste
    Kodama, H
    CZECHOSLOVAK JOURNAL OF PHYSICS, 1999, 49 : 971 - 977
  • [8] PURIFICATION OF LIQUID RADIOACTIVE EFFLUENTS BY CONTINUOUS ION-EXCHANGE
    RYABCHIKOV, BE
    TROFIMOV, DI
    ZAKHAROV, EI
    DUDIN, AS
    MIKHEEV, LK
    SOVIET ATOMIC ENERGY, 1975, 38 (04): : 284 - 287
  • [9] Mechanisms of strontium and uranium removal from high-level radioactive waste simulant solutions by the sorbent monosodium titanate
    Duff, MC
    Hunter, DB
    Hobbs, DT
    Fink, SD
    Dai, Z
    Bradley, JP
    ENVIRONMENTAL SCIENCE & TECHNOLOGY, 2004, 38 (19) : 5201 - 5207
  • [10] Ion exchange characteristics of rhodium from a simulated radioactive liquid waste
    Lee, SH
    Kim, KR
    Shon, JS
    Yoo, JH
    Chung, H
    JOURNAL OF INDUSTRIAL AND ENGINEERING CHEMISTRY, 1999, 5 (04) : 296 - 301