DEVELOPMENT OF A TRITIUM DISPERSION CODE

被引：0
|
作者：
BELL, R [1 ]
JOSEPH, S [1 ]
WONG, KY [1 ]
机构：
[1] CANADIAN FUS FUELS TECHNOL PROJECT,MISSISSAUGA,ONTARIO,CANADA
来源：
INTERNATIONAL JOURNAL OF APPLIED RADIATION AND ISOTOPES | 1985年 / 36卷 / 07期
关键词：
D O I：
10.1016/0020-708X(85)90202-9
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：
引用
收藏
页码：601 / 601
页数：1
相关论文
共 50 条
  • [1] DEVELOPMENT OF A TRITIUM DISPERSION CODE
    BELL, RP
    DAVIS, MW
    WONG, KY
    JOSEPH, S
    FUSION TECHNOLOGY, 1985, 8 (02): : 2582 - 2586
  • [2] MODELING ELEMENTAL TRITIUM DEPOSITION, CONVERSION AND REEMISSION USING ONTARIO HYDROS TRITIUM DISPERSION CODE
    RUSSELL, SB
    OGRAM, GL
    FUSION TECHNOLOGY, 1988, 14 (02): : 1193 - 1198
  • [3] Tritium atmospheric dispersion modelling code, ROPUCO, for A-FNS risk assessment
    Kenjo, Shunsuke
    Yokoyama, Sumi
    Ochiai, Kentaro
    Sato, Satoshi
    FUSION ENGINEERING AND DESIGN, 2024, 208
  • [4] Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR
    Huang, Kai
    Zhao, Xueli
    Ma, Xuebin
    Liu, Songlin
    FUSION ENGINEERING AND DESIGN, 2020, 153
  • [5] Study on the tritium behaviors in the VHTR system. Part 1. Development of tritium analysis code for VHTR and verification
    Kim, Eung S.
    Oh, Chang H.
    Patterson, Mike
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (07) : 1758 - 1767
  • [6] Development and validation of an atmospheric dispersion model for tritium using the IAEA BIOMASS scenario
    Yamamoto, K
    Sakashita, T
    Miyamoto, K
    FUSION SCIENCE AND TECHNOLOGY, 2005, 48 (01) : 500 - 503
  • [7] Development and preliminary verification of atmospheric dispersion code SDUG of radionuclide
    Cao, Bo
    Yang, Ye
    Chen, Yi-Xue
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (SUPPL.): : 472 - 476
  • [8] Tritium transport code development based on COMSOL and MATLAB and its application to the WCCB blanket
    Zhao, Xueli
    Chen, Lei
    Liu, Songlin
    Pan, Xin-Dong
    Li, Xiao-Chun
    FUSION ENGINEERING AND DESIGN, 2021, 173
  • [9] Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor
    Zeng, Youshi
    Wu, Shengwei
    Liu, Wei
    Wang, Guanghua
    Qian, Nan
    Wu, Xiaoling
    Liu, Wenguan
    Huang, Yu
    Qian, Yuan
    NUCLEAR TECHNOLOGY, 2018, 203 (01) : 48 - 57
  • [10] Model of tritium dispersion by ground water
    Golubev A.V.
    Mavrin S.V.
    Sten'gach A.V.
    Journal of Engineering Physics and Thermophysics, 2000, 73 (4) : 673 - 679
12345