Investigation of neutron resonance absorption in uranium-thorium fuel in a high temperature gas-cooled reactor (HTGR)

被引:0
|
作者
机构
来源
| 1600年 / 68期
关键词
Neutrons;
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
相关论文
共 50 条
  • [1] INVESTIGATION OF NEUTRON RESONANCE-ABSORPTION IN URANIUM THORIUM FUEL IN A HIGH-TEMPERATURE GAS-COOLED REACTOR (HTGR)
    BUSHEV, AV
    BELOUSOV, NI
    DUVANOV, VM
    NAUMOV, VI
    POLUSHKIN, AY
    SOVIET ATOMIC ENERGY, 1990, 68 (05): : 404 - 409
  • [2] Development of high temperature gas-cooled reactor (HTGR) fuel in Japan
    Ueta, Shohei
    Aihara, Jun
    Sawa, Kazuhiro
    Yasuda, Atsushi
    Honda, Masaki
    Furihata, Noboru
    PROGRESS IN NUCLEAR ENERGY, 2011, 53 (07) : 788 - 793
  • [3] THE HIGH-TEMPERATURE GAS-COOLED REACTOR (HTGR) - PREFACE
    BONILLA, CF
    NUCLEAR ENGINEERING AND DESIGN, 1982, 72 (02) : 109 - 109
  • [4] Free uranium fraction of fuel element of high temperature gas-cooled reactor
    Institute of Nuclear Energy Technology, Tsinghua University, Beijing 102201, China
    Hedongli Gongcheng, 2007, SUPPL. (4-6+11): : 4 - 6
  • [5] RESONANCE-ABSORPTION IN HIGH-TEMPERATURE GAS-COOLED REACTOR-FUEL WITH DOUBLE HETEROGENEITY
    TSUCHIHASHI, K
    ISHIGURO, Y
    KANEKO, K
    NUCLEAR SCIENCE AND ENGINEERING, 1980, 73 (02) : 164 - 173
  • [6] Concept of the polish high temperature gas-cooled reactor HTGR-POLA
    Dabrowski, Mariusz P.
    Boettcher, Agnieszka
    Brudek, Wojciech
    Malesa, Janusz
    Muszynski, Dominik
    Potempski, Slawomir
    Skrzypek, Eleonora
    Skrzypek, Maciej
    Sierchula, Jakub
    NUCLEAR ENGINEERING AND DESIGN, 2024, 424
  • [7] PARAMETRIC INVESTIGATION OF SUPERCRITICAL CARBON DIOXIDE BRAYTON CYCLE FOR HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR)
    Zhao, Gang
    Ye, Ping
    Yang, Xiaoyong
    Wang, Jie
    PROCEEDINGS OF THE ASME POWER CONFERENCE, 2018, VOL 2, 2018,
  • [8] FUEL CYCLE IN GAS-COOLED HIGH-TEMPERATURE REACTOR
    MERZ, E
    CHEMIKER-ZEITUNG, 1977, 101 (02): : 81 - 91
  • [9] HIGH TEMPERATURE GAS-COOLED REACTORS (HTR OR HTGR)
    不详
    ENERGIE NUCLEAIRE PARIS, 1971, 13 (01): : 7 - &
  • [10] Simulation of spherical fuel element (SFF) motion in the high-temperature gas-cooled reactor (HTGR) core
    Mozovetskij, V.V.
    Atomnaya Energiya, 2001, 90 (02): : 100 - 115