Glass-bonded iodosodalite waste form for immobilization of 129I

被引:56
|
作者
Chong, Saehwa [1 ]
Peterson, Jacob A. [3 ]
Riley, Brian J. [2 ,3 ]
Tabada, Diana [4 ]
Wall, Donald [4 ]
Corkhill, Claire L. [5 ]
McCloy, John S. [1 ,2 ,3 ]
机构
[1] Washington State Univ, Mat Sci & Engn Program, Pullman, WA 99164 USA
[2] Washington State Univ, Sch Mech & Mat Engn, POB 642920, Pullman, WA 99164 USA
[3] Pacific Northwest Natl Lab, Richland, WA 99354 USA
[4] Washington State Univ, Nucl Sci Ctr, Pullman, WA 99164 USA
[5] Univ Sheffield, Dept Mat Sci & Engn, NucleUS Immobilisat Sci Lab, Sheffield S1 3JD, S Yorkshire, England
基金
英国工程与自然科学研究理事会;
关键词
Iodosodalite; Sodalite; Glass ceramic waste form; Glass composite material; HYDROXY-SODALITE ZEOLITE; KAOLINITE; IODINE;
D O I
10.1016/j.jnucmat.2018.03.033
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Immobilization of radioiodine is an important requirement for current and future nuclear fuel cycles. Iodosodalite [Na-8(AlSiO4)(6)I-2] was synthesized hydrothermally from metakaolin, NaI, and NaOH. Dried unwashed sodalite powders were used to synthesize glass-bonded iodosodalite waste forms (glass composite materials) by heating pressed pellets at 650, 750, or 850 degrees C with two types of sodium borosilicate glass binders. These heat-treated specimens were characterized with X-ray diffraction, Fourier-transform infrared spectroscopy, scanning electron microscopy, energy dispersive spectroscopy, thermal analysis, porosity and density measurements, neutron activation analysis, and inductively-coupled plasma mass spectrometry. For the best waste form produced (pellets mixed with 10 mass% of glass binder and heat-treated at 750 degrees C), the maximum possible elemental iodine loading was 19.8 mass%, but only similar to 8-9 mass% waste loading of iodine was retained in the waste form after thermal processing. Other pellets with higher iodine retention either contained higher porosity or were incompletely sintered. ASTM C1308 and C1285 (product consistency test, PCT) experiments were performed to understand chemical durability under diffusive and static conditions. The C1308 test resulted in significantly higher normalized loss compared to the C1285 test, most likely because of the strong effect of neutral pH solution renewal and prevention of ion saturation in solution. Both experiments indicated that release rates of Na and Si were higher than for Al and I, probably due to a poorly durable Na-Si-O phase from the glass bonding matrix or from initial sodalite synthesis; however the C1308 test result indicated that congruent dissolution of iodosodalite occurred. The average release rates of iodine obtained from C1308 were 0.17 and 1.29 gm(-2) d(-1) for 80 or 8 m(-1), respectively, and the C1285 analysis gave a value of 2 x 10(-5) g m(-2) d(-1), which is comparable to or better than the durability of other iodine waste forms. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码:109 / 121
页数:13
相关论文
共 50 条
  • [41] Low-Temperature Sintering Bi-Si-Zn-Oxide Glasses for Use in Either Glass Composite Materials or Core/Shell 129I Waste Forms
    Garino, Terry J.
    Nenoff, Tina M.
    Krumhansl, James L.
    Rademacher, David X.
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2011, 94 (08) : 2412 - 2419
  • [42] Determination of 129I activities and interference in low level radioactive waste by alkaline fusion coupled with ICP-MS
    Chang, Feng-chih
    Chao, Jiunn-Hsing
    Tien, Neng-Chuan
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2022, 331 (05) : 2029 - 2036
  • [43] Development of new analytical procedures for determination of 129I and 99Tc in waste material produced by the Hungarian NPP
    Szucs, Z
    Hertelendi, E
    Svingor, E
    Gulyas, J
    Csongor, J
    INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 59, PT 1 AND 2, 1997, 59 : 1395 - 1397
  • [44] Determination of 129I activities and interference in low level radioactive waste by alkaline fusion coupled with ICP-MS
    Feng-chih Chang
    Jiunn-Hsing Chao
    Neng-Chuan Tien
    Journal of Radioanalytical and Nuclear Chemistry, 2022, 331 : 2029 - 2036
  • [45] Microwave heating for production of a glass bonded ceramic high-level waste form
    O'Holleran, TP
    ENVIRONMENTAL ISSUES AND WASTE MANAGEMENT TECHNOLOGIES IN THE CERAMIC AND NUCLEAR INDUSTRIES VIII, 2003, 143 : 363 - 370
  • [46] Comparison of thermal expansion and heat capacity properties of various borosilicate glass-bonded strontium chloroapatite composites loaded with simulated pyrochemical waste
    Maji, Binoy Kumar
    Jena, Hrudananda
    Krishnan, R. Venkata
    Asuvathraman, R.
    Ananthasivan, K.
    Kutty, K. V. Govindan
    JOURNAL OF THERMAL ANALYSIS AND CALORIMETRY, 2015, 119 (03) : 1825 - 1831
  • [47] Comparison of thermal expansion and heat capacity properties of various borosilicate glass-bonded strontium chloroapatite composites loaded with simulated pyrochemical waste
    Binoy Kumar Maji
    Hrudananda Jena
    R. Venkata Krishnan
    R. Asuvathraman
    K. Ananthasivan
    K. V. Govindan Kutty
    Journal of Thermal Analysis and Calorimetry, 2015, 119 : 1825 - 1831
  • [48] Synthesis and thermal characterization of glass bonded Ca-chloroapatite matrices for pyrochemical chloride waste immobilization
    Jena, Hrudananda
    Maji, Binoy Kumar
    Asuvathraman, R.
    Kutty, K. V. Govindan
    JOURNAL OF NON-CRYSTALLINE SOLIDS, 2012, 358 (14) : 1681 - 1686
  • [49] Use of CAP88 PC to infer differences in the chemical form of 129I emitted from a fuel reprocessing facility
    Fritz, Brad G.
    Phillips, Nathan R. J.
    JOURNAL OF ENVIRONMENTAL RADIOACTIVITY, 2013, 120 : 1 - 5
  • [50] DETERMINATION OF LONG-LIVED RADIONUCLIDE (10Be, 41Ca, 129I) CONCENTRATIONS IN NUCLEAR WASTE BY ACCELERATOR MASS SPECTROMETRY
    Nottoli, Emmanuelle
    Bienvenu, Philippe
    Bourles, Didier
    Labet, Alexandre
    Arnold, Maurice
    Bertaux, Maite
    ASME 2013 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL REMEDIATION AND RADIOACTIVE WASTE MANAGEMENT, VOL 1: LOW/INTERMEDIATE-LEVEL RADIOACTIVE WASTE MANAGEMENT; SPENT FUEL, FISSILE MATERIAL, TRANSURANIC AND HIGH-LEVEL RADIOACTIVE WASTE MANAGEMENT, 2013,