THERMAL-HYDRAULIC STUDIES FOR THE POOL-TYPE LMFBR.

被引：0
|
作者：
Anon
机构：
来源：
Mitsubishi Genshiryoku Giho | 1983年 / 30期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
NUCLEAR REACTORS, BREEDER
引用
收藏
页码：16 / 20
相关论文
共 50 条
  • [21] AUTOMATIC-CONTROL SIMULATION OF REACTOR PRIMARY SODIUM TEMPERATURE IN A POOL-TYPE LMFBR
    MOHR, D
    FELDMAN, EE
    THOMPSON, VN
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1983, 44 : 460 - 461
  • [22] Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors
    Toti, A.
    Vierendeels, J.
    Belloni, F.
    ANNALS OF NUCLEAR ENERGY, 2017, 103 : 36 - 48
  • [23] SINGLE-ELEMENT MODEL OF THERMAL-HYDRAULIC BEHAVIOR FOR AN LMFBR SUBASSEMBLY
    MILES, KJ
    FAZZOLARE, RA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 424 - 425
  • [24] NUMERICAL THERMAL-HYDRAULIC SIMULATION OF AN LMFBR PIPE DURING A FLOW COASTDOWN
    CHEN, MJ
    DOMANUS, HM
    SHA, WT
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 673 - 674
  • [25] CORTRAN CODE FOR WHOLE-CORE LMFBR TRANSIENT THERMAL-HYDRAULIC ANALYSIS
    KHAN, EU
    HINDS, A
    CHEATHAM, RL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 537 - 539
  • [26] LMFBR CORE THERMAL-HYDRAULIC ANALYSIS ACCOUNTING FOR INTERASSEMBLY HEAT-TRANSFER
    CARELLI, MD
    BACH, CW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 560 - 562
  • [27] SIMPLE FORCED DIVERSION MODEL FOR STUDY OF THERMAL-HYDRAULIC TRANSIENTS IN LMFBR SUBASSEMBLY
    CHEN, WL
    GROLMES, MA
    ISHII, M
    NUCLEAR ENGINEERING AND DESIGN, 1978, 45 (01) : 53 - 66
  • [28] Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor
    Wang, Gongqing
    Yue, Zhiting
    Sun, Rulei
    Li, Dongyang
    Liu, Xingmin
    Wang, Bo
    Tian, Ruifeng
    Annals of Nuclear Energy, 2022, 170
  • [29] E-SCAPE: A scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations
    Van Tichelen, Katrien
    Mirelli, Fabio
    Greco, Matteo
    Viviani, Giorgia
    NUCLEAR ENGINEERING AND DESIGN, 2015, 290 : 65 - 77
  • [30] Numerical investigation on the core thermal hydraulic behavior of pool-type sodium-cooled fast reactor (SFR)
    Wang, X.A.
    Liang, Ximei
    Xu, RongShuan
    He, DongYu
    Wang, Ting
    Zhang, Dalin
    Frontiers in Energy Research, 2024, 12
12345