A PLANT-COMPUTER-BASED PRESSURIZED WATER-REACTOR PRIMARY SYSTEM THERMAL-HYDRAULIC MODEL

被引：0
|
作者：
KAO, SP
MEYER, JE
机构：
[1] ENGN PLANNING & MANAGEMENT INC, FRAMINGHAM, MA 01701 USA
[2] MIT, CAMBRIDGE, MA 02139 USA
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1985年 / 50卷 / NOV期
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：637 / 638
页数：2
相关论文
共 50 条
  • [1] PRESSURIZED WATER-REACTOR THERMAL-HYDRAULIC CORE ANALYSIS WITH THE FLICA COMPUTER CODE
    RAYMOND, P
    SPINDLER, B
    LENAIN, R
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1990, 124 (03) : 299 - 313
  • [2] An improved core thermal-hydraulic model for coastdown transient in pressurized water reactor
    Ahmad, Idrees
    Arshad, Saad
    Tahir, Sajjad
    Nadeem, Qaisar
    Samee, Abdus
    [J]. PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART A-JOURNAL OF POWER AND ENERGY, 2018, 232 (04) : 416 - 424
  • [3] Development of a thermal-hydraulic analysis code for primary system of an integrated small modular pressurized water reactor
    Wang, Dongqing
    Chen, Huandong
    Chen, Jiayue
    Zhan, Dekui
    Xia, Shaoxiong
    [J]. ANNALS OF NUCLEAR ENERGY, 2021, 152
  • [4] A RELAP5 MODEL FOR THE THERMAL-HYDRAULIC ANALYSIS OF A TYPICAL PRESSURIZED WATER REACTOR
    Agamy, Said
    Metwally, Adul Mohsen
    Al-Ramady, Amir Mohammad
    Elaraby, Sayed Mohamed
    [J]. THERMAL SCIENCE, 2010, 14 (01): : 79 - 88
  • [5] A MODEL OF CRUD PARTICLE WALL INTERACTION AND DEPOSITION IN A PRESSURIZED WATER-REACTOR PRIMARY SYSTEM
    DINOV, KA
    [J]. NUCLEAR TECHNOLOGY, 1991, 94 (03) : 281 - 285
  • [6] Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor
    Wu, Y. W.
    Su, G. H.
    Qiu, S. Z.
    Zhuang, C. J.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (01) : 112 - 122
  • [7] ANALYTICAL STUDIES OF THERMAL-HYDRAULIC AND RADIONUCLIDE BEHAVIOR IN SEVERE ACCIDENT AT BOILING WATER-REACTOR
    HARAMI, T
    WATANABE, N
    TAKANO, T
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1990, 27 (02) : 174 - 187
  • [8] PRESSURIZED WATER-REACTOR INHERENT CORE PROTECTION BY PRIMARY SYSTEM THERMOHYDRAULICS
    BABALA, D
    HANNERZ, K
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1985, 90 (04) : 400 - 410
  • [9] SIMPLIFIED THERMAL-HYDRAULIC METHODS FOR ANALYZING LIGHT WATER-REACTOR EVENT SEQUENCE FAMILIES
    FLETCHER, CD
    DAVIS, CB
    OGDEN, DM
    [J]. NUCLEAR ENGINEERING AND DESIGN, 1986, 91 (03) : 359 - 371
  • [10] DESCRIPTIVE MODEL FOR PRESSURIZED WATER-REACTOR CRUD
    CUNNANE, JC
    KENNEDY, AJ
    [J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 816 - 817
12345