STATISTICAL TECHNIQUES FOR CORE THERMAL-HYDRAULIC DESIGN - REGULATORS POINT OF VIEW

被引:0
|
作者
HODGES, MW [1 ]
机构
[1] US NUCL REGULATORY COMMISS,WASHINGTON,DC 20555
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:552 / 552
页数:1
相关论文
共 50 条
  • [31] Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation
    Bandini, G.
    Buck, M.
    Hering, W.
    Godin-Jacqmin, L.
    Ratel, G.
    Matejovic, P.
    Barnak, M.
    Paitz, G.
    Stefanova, A.
    Tregoures, N.
    Guillard, G.
    Koundy, V.
    PROGRESS IN NUCLEAR ENERGY, 2010, 52 (01) : 148 - 157
  • [32] THERMAL-HYDRAULIC ANALYSIS OF THE FFTF CORE USING SUPERENERGY-2
    CRAMER, ER
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 764 - 765
  • [33] Application of BPNN algorithm in thermal-hydraulic analysis of unwrapped LFR core
    Qiu, Hanrui
    Yu, Jiacheng
    Wang, Mingjun
    Tian, Wenxi
    Su, Guanghui
    INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2024, 203
  • [34] Thermal-Hydraulic modelling and analysis of VVER-1200 reactor core
    El-Morshedy, Salah El -Din
    Awad, Mostafa M.
    El-Fetouh, Mohamed Abo
    ANNALS OF NUCLEAR ENERGY, 2023, 194
  • [35] Optimization of an Integrated Neutronic/Thermal-Hydraulic Reactor Core Analysis Model
    Mylonakis, A. G.
    Varvayanni, M.
    Grigoriadis, D. G. E.
    Savva, P.
    Catsaros, N.
    23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
  • [36] EFFECT OF STAINLESS-STEEL SWELLING ON THERMAL-HYDRAULIC CORE PERFORMANCE
    SHA, WT
    MARR, WW
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (01): : 327 - &
  • [37] Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor
    Liu, Xiao
    Zhang, Ran
    Liang, Yu
    Tang, Simiao
    Wang, Chenglong
    Tian, Wenxi
    Zhang, Zhuohua
    Qiu, Suizheng
    Su, Guanghui
    ANNALS OF NUCLEAR ENERGY, 2020, 142
  • [38] Thermal-Hydraulic Evaluation of the Advanced Safety Design Features of APR
    Bang, Young Seok
    Lee, Gong-Hee
    Woo, Sweng-Woong
    Andong-Shin
    22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
  • [39] THERMAL-HYDRAULIC ANALYSIS TECHNIQUES FOR AXISYMMETRIC PEBBLE BED REACTOR CORES
    STROH, KR
    JIACOLETTI, RJ
    OLSON, HG
    NUCLEAR ENGINEERING AND DESIGN, 1979, 52 (03) : 343 - 347
  • [40] Thermal-hydraulic design and accident analysis of small simplified BWR
    Chen, Jing
    Gao, Zuying
    Qinghua Daxue Xuebao/Journal of Tsinghua University, 2001, 41 (06): : 52 - 55