ASSESSMENT OF TRITIUM INVENTORY IN WASTE BY OUTGASSING MEASUREMENTS

被引:4
|
作者
ANTONIAZZI, AB
SHMAYDA, WT
机构
来源
FUSION TECHNOLOGY | 1995年 / 28卷 / 03期
关键词
D O I
10.13182/FST95-A30617
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 production of large volumes of low specific activity waste is a byproduct of working with tritium. Reliable, labour minimized techniques for assessing the tritium bound in the waste is essential for an effective waste management program. This work examines the use of tritium outgassing rates from waste as a means of determining the bound inventory. A simple and inexpensive technique has been developed which, when combined with a sampling methodology, leads to accurate measurements of tritium outgassing rates. These outgassing rates when used in conjuction with the appropriate database will yield the inventory bound in the waste. The results of this study support the viability of the proposed approach.
引用
收藏
页码:1457 / 1462
页数:6
相关论文
共 50 条
  • [1] LIMITATION OF TRITIUM OUTGASSING FROM TRITIATED SOLID WASTE DRUMS
    Liger, K.
    Trabuc, P.
    Lefebvre, X.
    Troulay, M.
    Perrais, C.
    FUSION SCIENCE AND TECHNOLOGY, 2015, 67 (02) : 455 - 458
  • [2] TRITIUM INVENTORY MEASUREMENTS USING CALORIMETRY
    KAPULLA, H
    KRAEMER, R
    HEINE, R
    FUSION TECHNOLOGY, 1992, 21 (02): : 412 - 418
  • [3] Reducing the tritium inventory in waste produced by fusion devices
    Pamela, J.
    Decanis, C.
    Canas, D.
    Liger, K.
    Gaune, F.
    FUSION ENGINEERING AND DESIGN, 2015, 93 : 51 - 56
  • [4] Tritium inventory assessment for ITER using TRIMO
    Cristescu, IR
    Cristescu, I
    Murdoch, D
    Dörr, L
    Glugla, M
    FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) : 763 - 769
  • [5] Tritium inventory measurements by ''in-bed'' gas flowing calorimetry
    Hayashi, T
    Suzuki, T
    Yamada, M
    Okuno, K
    FUSION TECHNOLOGY, 1996, 30 (03): : 931 - 935
  • [6] Tritium inventory measurements by 'in-bed' gas flowing calorimetry
    Japan Atomic Energy Research Inst, Ibaraki-ken, Japan
    Fusion Technol, 3 (931-935):
  • [7] Limitation of tritium outgassing from fusion reactors waste drums: Theoretical aspects of hydrogen oxidation
    Lefebvre, X.
    Liger, K.
    Troulay, M.
    Ghirelli, N.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 2398 - 2402
  • [8] Physical inventory by use of modeling for the tritium aqueous waste recovery system
    Sienkiewicz, Charles
    Lentz, James E.
    Wiggins, Donald V.
    Fusion Technology, 1988, 14 (2 pt 2B): : 1096 - 1101
  • [9] Assessment of erosion and surface tritium inventory issues for the ITER divertor
    Brooks, JN
    Causey, R
    Federici, G
    Ruzic, DN
    JOURNAL OF NUCLEAR MATERIALS, 1997, 241 : 294 - 298
  • [10] Assessment of erosion and surface tritium inventory issues for the ITER divertor
    Argonne Natl Lab, Argonne, United States
    Journal of Nuclear Materials, 241-243 : 294 - 298