EXPLICIT METHOD FOR PREDICTING THERMAL PERFORMANCE OF FBR WIRE-WRAPPED FUEL ROD ASSEMBLIES

被引:0
|
作者
GRAVES, AW
CATTON, I
机构
[1] ATOM INT,CANOGA PK,CA 91304
[2] UNIV CALIF,LOS ANGELES,CA 90024
来源
关键词
D O I
暂无
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:404 / &
相关论文
共 50 条
  • [31] MODELING OF FLOW SWEEPING EFFECTS IN WIRE-WRAPPED ROD BUNDLES
    MAGEE, PM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 406 - &
  • [32] DISTRIBUTED RESISTANCE MODELING OF WIRE-WRAPPED ROD BUNDLES.
    Ninokata, Hisashi
    Efthimiadis, Apostolos
    Todreas, Neil E.
    1600, (104):
  • [33] Multiobjective optimization of a wire-wrapped LMR fuel assembly
    Raza, Wasim
    Kim, Kwang-Yong
    NUCLEAR TECHNOLOGY, 2008, 162 (01) : 45 - 52
  • [34] STATIC PRESSURE DISTRIBUTION IN A 7 WIRE-WRAPPED ROD BUNDLE
    FERNANDEZYFERNANDEZ, E
    CARAJILESCOV, P
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 33 (NOV): : 633 - 634
  • [35] A novel friction factor model for wire-wrapped rod bundles
    Dix, Adam
    Kim, Seungjin
    NUCLEAR ENGINEERING AND DESIGN, 2023, 401
  • [36] THERMAL-HYDRAULIC ANALYSIS OF A WIRE-WRAPPED 19-ROD BUNDLE WITH EDGE BLOCKAGE
    LIN, EIH
    SHA, WT
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 28 (JUN): : 539 - 540
  • [37] Multi-objective optimization of wire-wrapped reactor fuel assemblies using CFD and genetic algorithms
    Qiu, Hanrui
    Liu, Zhenglong
    Wang, Mingjun
    Tian, Wenxi
    Su, Guanghui
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2024, 159
  • [38] EXPERIMENTAL CORRELATION OF CROSS-FLOW PRESSURE DROP FOR TRIANGULAR ARRAY WIRE-WRAPPED ROD ASSEMBLIES.
    Suh, Kune Yull
    Todreas, Neil E.
    1600, (76):
  • [39] AN EXPERIMENTAL CORRELATION OF CROSS-FLOW PRESSURE-DROP FOR TRIANGULAR ARRAY WIRE-WRAPPED ROD ASSEMBLIES
    SUH, KY
    TODREAS, NE
    NUCLEAR TECHNOLOGY, 1987, 76 (02) : 229 - 240
  • [40] Comparison on the thermal-hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation
    Zhang, Qi
    Cong, Tenglong
    Xiao, Yao
    Li, Junlong
    Zeng, Chen
    Gu, Hanyang
    ANNALS OF NUCLEAR ENERGY, 2022, 177