Processing simulated oxalated high-level waste through a vitrification feed preparation flowsheet

被引：0
|
作者：
Patello, GK [1 ]
Russell, RL [1 ]
Golcar, GR [1 ]
Smith, HD [1 ]
Smith, GL [1 ]
Elliott, ML [1 ]
机构：
[1] Battelle Mem Inst, Pacific NW Labs, Richland, WA 99352 USA
来源：
ENVIRONMENTAL ISSUES AND WASTE MANAGEMENT TECHNOLOGIES IN THE CERAMIC AND NUCLEAR INDUSTRIES IV | 1999年 / 93卷
关键词：
D O I：
暂无
中图分类号：
X [环境科学、安全科学];
学科分类号：
08 ; 0830 ;
摘要：
Following an initial vitrification phase at the West Valley Demonstration Project (WVDP), residual tank waste, consisting of cesium-loaded zeolite in Tank 8D-1 and a mixture of neutralized plutonium-uranium extraction (PUREX) sludge and thorium extraction (THOREX) waste in Tank 8D-2, may require additional processing. A proposed treatment process involves adding oxalic acid to Tanks 8D-1 and 8D-2 to remove the residual activity. The oxalic acid will dissolve solids and increase the mobility of the radioactivity components. One option is to process the oxalated waste directly through the vitrification process. Laboratory-scale tests at the Pacific Northwest National Laboratory (PNNL) with simulated oxalated waste have evaluated the effect of oxalated waste in the melter feed flowsheet, for comparison to the baseline WVDP flowsheet. Comparisons were made on the basis of rheology, pH, and glass redox potential.
引用
收藏
页码：163 / 170
页数：8
相关论文
共 50 条
  • [21] NMR Insights into Wasteforms for the Vitrification of High-Level Nuclear Waste
    D. Holland
    B. G. Parkinson
    M. M. Islam
    A. Duddridge
    J. M. Roderick
    A. P. Howes
    C. R. Scales
    Applied Magnetic Resonance, 2007, 32 : 483 - 497
  • [22] VITRIFICATION OF ACTUAL HIGH-LEVEL WASTE FROM LWR FUEL
    BJORKLUND, WJ
    HANSON, MS
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 943 - 944
  • [23] NMR insights into wasteforms for the vitrification of high-level nuclear waste
    Holland, D.
    Parkinson, B. G.
    Islam, M. M.
    Duddridge, A.
    Roderick, J. M.
    Howes, A. P.
    Scales, C. R.
    APPLIED MAGNETIC RESONANCE, 2007, 32 (04) : 483 - 497
  • [24] VITRIFICATION OF SIMULATED HIGH-LEVEL WASTE USING DIRECT LIQUID FEEDING INTO A JOULE-HEATED CERAMIC MELTER
    WEISENBURGER, S
    GRUNEWALD, W
    KOSCHORKE, H
    AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 320 - 320
  • [25] DIFFUSION OF NEPTUNIUM IN SIMULATED HIGH-LEVEL WASTE GLASS
    INOUE, T
    TSUKAMOTO, M
    FUKUSHIMA, M
    KINOSHITA, M
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1986, 23 (11) : 992 - 1000
  • [26] IMMOBILIZATION OF SIMULATED HIGH-LEVEL WASTE IN SINTERED GLASSES
    AUDERO, MA
    BEVILACQUA, AM
    DEBERNASCONI, NBM
    RUSSO, DO
    STERBA, ME
    JOURNAL OF NUCLEAR MATERIALS, 1995, 223 (02) : 151 - 156
  • [27] FRACTURING OF SIMULATED HIGH-LEVEL WASTE GLASS IN CANISTERS
    PETERS, RD
    SLATE, SC
    NUCLEAR ENGINEERING AND DESIGN, 1982, 67 (03) : 425 - 445
  • [28] Progress in Study on Radiation Effect of Vitrification for High-level Radioactive Waste
    Wang T.-S.
    Peng H.-B.
    Liu F.-F.
    Sun M.-L.
    Yuan W.
    Duan B.-H.
    Guan X.-C.
    Chen L.
    Du X.
    Yang D.
    Chen H.
    Yuanzineng Kexue Jishu, 6 (967-974): : 967 - 974
  • [29] Influence of Radioactive Sludge Content on Vitrification of High-Level Liquid Waste
    Tan, Shengheng
    Chang, Jiong
    Liu, Xiao
    Sun, Shikuan
    Xian, Liang
    Zhang, Shengdong
    SUSTAINABILITY, 2023, 15 (06)
  • [30] Precipitation behaviour of simulated high-level liquid waste during the denitration process based on two-step vitrification
    Wang, Changfu
    Liu, Xu
    Shao, Bobo
    Xu, Zhiyi
    Liu, Yan
    Wang, Yun
    Tan, Shengheng
    Liu, Zhirong
    Zhang, Shengdong
    NUCLEAR ENGINEERING AND DESIGN, 2023, 415
12345