A TEST PROGRAM ON THERMOMECHANICAL AND THERMAL-HYDRAULIC ASPECTS OF NUCLEAR SYSTEMS FOR MAGNETICALLY CONFINED FUSION POWER-REACTORS

被引：0
|
作者：
NYGREN, RE
HERMAN, H
BAKER, CC
机构：
来源：
NUCLEAR ENGINEERING AND DESIGN | 1982年 / 68卷 / 03期
关键词：
D O I：
10.1016/0029-5493(82)90250-3
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：311 / 321
页数：11
相关论文
共 16 条
  • [1] THERMAL-HYDRAULIC CONSIDERATIONS IN MAGNETICALLY CONFINED FUSION REACTORS.
    Kearney, D.W.
    Transactions of the International Conference on Structural Mechanics in Reactor Technology, 1979, N
  • [2] SAFETY SYSTEMS AND STRUCTURAL ASPECTS OF SUPERCONDUCTING MAGNETS FOR FUSION POWER-REACTORS
    POWELL, J
    LEHNER, J
    DANBY, G
    HSIEH, D
    REICH, M
    PRODELL, A
    IEEE TRANSACTIONS ON MAGNETICS, 1977, 13 (01) : 628 - 631
  • [3] Open thermal-hydraulic research issues in Western Nuclear Power Reactors
    Hicken, EF
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2004, 49 (05): : 342 - +
  • [4] MODCIR - A 3-DIMENSIONAL TRANSIENT CODE USED IN THERMAL-HYDRAULIC ANALYSES OF CANDU POWER-REACTORS
    AUSTMAN, G
    SZYMANSKI, J
    MIDVIDY, WI
    MATHEMATICS AND COMPUTERS IN SIMULATION, 1983, 25 (06) : 493 - 496
  • [5] Thermal-hydraulic and safety aspects of UO2 fuel for low-power reactors
    Albarhoum, M.
    PROGRESS IN NUCLEAR ENERGY, 2011, 53 (04) : 354 - 360
  • [6] Status and trends of thermal-hydraulic system codes for nuclear power plants with pressurized water reactors
    State Nuclear Power Technology Corporation Ltd., Beijing 100140, China
    不详
    Yuanzineng Kexue Jishu, 2009, 11 (966-972):
  • [7] Transient thermal-hydraulic characteristics analysis software for pwr nuclear power systems
    Wu, Ying-Wei
    Zhuang, Cheng-Jun
    Su, Guang-Hui
    Qiu, Sui-Zheng
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (02): : 47 - 49
  • [8] ANALYSIS OF THE THERMAL-HYDRAULIC AND MECHANICAL PERFORMANCE OF INTERMEDIATE HEAT EXCHANGERS USED IN SYSTEMS WITH VERY HIGH TEMPERATURE NUCLEAR REACTORS
    de la Torre Valdes, Raciel
    Francois Lacouture, Juan Luis
    PROCEEDINGS OF THE ASME NUCLEAR FORUM, 2018, 2018,
  • [9] Experimental investigations of thermal-hydraulic processes arising during operation of the passive safety systems used in new projects of nuclear power plants equipped with VVER reactors
    Morozov A.V.
    Remizov O.V.
    Kalyakin D.S.
    Thermal Engineering, 2014, 61 (5) : 357 - 363
  • [10] Transient test of a NSSS thermal-hydraulic module for the nuclear power plant simulator using a best-estimate code, RETRAN
    Lee, MS
    Seo, IY
    Kim, YH
    Lee, YK
    Suh, JS
    SYSTEMS MODELING AND SIMULATION: THEORY AND APPLICATIONS, 2005, 3398 : 529 - 535
12