LMFBR SYSTEM-ANALYSIS - IMPACT OF HEAT-TRANSPORT SYSTEM ON CORE THERMAL-HYDRAULICS

被引：2
|
作者：
MADNI, IK
AGRAWAL, AK
机构：
来源：
NUCLEAR ENGINEERING AND DESIGN | 1980年 / 62卷 / 1-3期
关键词：
D O I：
10.1016/0029-5493(80)90029-1
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：199 / 218
页数：20
相关论文
共 50 条
  • [21] FFTF PRIMARY HEAT-TRANSPORT HVAC SYSTEM
    UMEK, AM
    HICKS, DF
    SCHWEIGER, DL
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 700 - 701
  • [22] A thermal-hydraulics analysis of pipe breaks in the pebble bed modular reactor main power system
    Mazana, Naison
    International Conference on Nuclear Engineering, Proceedings, ICONE, 2008, 3 : 943 - 950
  • [23] A THERMAL-HYDRAULICS ANALYSIS OF PIPE BREAKS IN THE PEBBLE BED MODULAR REACTOR MAIN POWER SYSTEM
    Mazana, Naison
    ICONE16: PROCEEDING OF THE 16TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2008, VOL 3, 2008, : 943 - 950
  • [24] Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core
    Liu, X. J.
    Cheng, X.
    PROGRESS IN NUCLEAR ENERGY, 2010, 52 (07) : 640 - 647
  • [25] Core thermal-hydraulics analysis during dipped-type direct heat exchanger operation in natural circulation conditions
    Hamase, Erina
    Doda, Norihiro
    Ono, Ayako
    Tanaka, Masaaki
    Miyake, Yasuhiro
    Imai, Yasutomo
    MECHANICAL ENGINEERING JOURNAL, 2022, 9 (04):
  • [26] ECONOMICAL REMOVAL OF SODIUM WATER REACTION-PRODUCTS (SWRP) FROM AN LMFBR INTERMEDIATE HEAT-TRANSPORT SYSTEM (IHTS)
    ANAND, RK
    REYNOLDS, RG
    MECHANICAL ENGINEERING, 1977, 99 (06) : 115 - 115
  • [27] Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF
    Guo, Juanjuan
    Liu, Shichang
    Shang, Xiaotong
    Huang, Shanfang
    Wang, Kan
    ANNALS OF NUCLEAR ENERGY, 2017, 109 : 327 - 336
  • [28] THERMAL-HYDRAULICS OF AN EXTERNAL WATER WALL TYPE PASSIVE CONTAINMENT COOLING SYSTEM
    KATAOKA, Y
    MURASE, M
    FUJI, T
    TOMINAGA, K
    NUCLEAR TECHNOLOGY, 1995, 111 (02) : 241 - 250
  • [29] FFTF HEAT-TRANSPORT SYSTEM (HTS) COMPONENT AND SYSTEM-DESIGN
    YOUNG, MW
    EDWARDS, PA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 34 (JUN): : 698 - 699
  • [30] Development of MCATHAS system of coupled neutronics/thermal-hydraulics in supercritical water reactor
    An, Ping
    Yao, Dong
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (06): : 52 - 55
12345