Advanced Search
DENG Jing-shan~1, LIU Ping~2, REN Ning-li~3, LIU Ting-jin~2(1. Zhengzhou Fifth Research and Design Institute of Nuclear Industry, P. O. Box 253, Zhengzhou 450052, China;2. China Institute of Atomic Energy, P.O.Box 275-41, Beijing 102413, China;3. Fourth Research Institute of the Second Artillery, Th. Neutron Moderation Calculation for Nuclear Fuel Rod Scanner[J]. Atomic Energy Science and Technology, 2005, 39(3): 214-214. DOI: 10.7538/yzk.2005.39.03.0214
Citation: DENG Jing-shan~1, LIU Ping~2, REN Ning-li~3, LIU Ting-jin~2(1. Zhengzhou Fifth Research and Design Institute of Nuclear Industry, P. O. Box 253, Zhengzhou 450052, China;2. China Institute of Atomic Energy, P.O.Box 275-41, Beijing 102413, China;3. Fourth Research Institute of the Second Artillery, Th. Neutron Moderation Calculation for Nuclear Fuel Rod Scanner[J]. Atomic Energy Science and Technology, 2005, 39(3): 214-214. DOI: 10.7538/yzk.2005.39.03.0214
shu
    Graphical Abstract
    • Abstract
  • In order to use ~(252)Cf source effectively and improve testing sensitivity of the nuclear fuel scanner, appropriate moderation material should be selected carefully, and the process of neutron moderation should be optimized. In the paper, neutron fluence rate distributions in several moderation materials were calculated with Monte-Carlo method. The results of several materials and their combinations are given, the higher slowing-down neutron fluence rate and the higher ratio of ~(235)U to ~(238)U fission possibility simultaneously can be got.
    • FullText(HTML)
  • loading
    • References (5)
    • Related Articles

Catalog

    Turn off MathJax
    Article Contents

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return