CFD analysis of flow distribution of reactor core and temperature rise of coolant in fuel assembly for VVER reactor

被引:0
|
作者
Du, Dai-Quan [1 ]
Zeng, Xiao-Kang [1 ]
Yang, Xiao-Qiang [2 ]
Xiong, Wan-Yu [1 ]
机构
[1] CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu,610041, China
[2] CNNC Jiangsu Nuclear Power Corporation, Lianyungang,222042, China
关键词
Compendex;
D O I
10.7538/yzk.2015.49.03.0429
中图分类号
学科分类号
摘要
Computational fluid dynamics
引用
收藏
页码:429 / 432
相关论文
共 50 条
  • [21] AXIAL TEMPERATURE DISTRIBUTION IN A REACTOR COOLANT CHANNEL
    FORGHIER.R
    PAPA, G
    ENERGIA NUCLEARE, 1968, 15 (09): : 571 - &
  • [22] CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core
    Atomic Energy Authority, Reactors Department, 13759 Cairo, Egypt
    Ann Nucl Energy, (26-39): : 26 - 39
  • [23] CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core
    Salama, Amgad
    El-Morshedy, Salah El-Din
    ANNALS OF NUCLEAR ENERGY, 2012, 41 : 26 - 39
  • [24] COOLANT TEMPERATURE DISTRIBUTION AT VVER-440 CORE INLET
    TSIMBALOV, SA
    KRAIKO, AV
    SOVIET ATOMIC ENERGY, 1982, 52 (05): : 292 - 296
  • [25] Simulation of the Coolant Hydrodynamics in the Outlet Section of the Fuel Assembly of the Cartridge Core of the RITM Type Reactor
    Dmitriev, S. M.
    Demkina, T. D.
    Dobrov, A. A.
    Doronkov, D. V.
    Doronkova, D. S.
    Pronin, A. N.
    Ryazanov, A. V.
    Solntsev, D. N.
    Khrobostov, A. E.
    THERMAL ENGINEERING, 2023, 70 (07) : 523 - 533
  • [26] Simulation of the Coolant Hydrodynamics in the Outlet Section of the Fuel Assembly of the Cartridge Core of the RITM Type Reactor
    S. M. Dmitriev
    T. D. Demkina
    A. A. Dobrov
    D. V. Doronkov
    D. S. Doronkova
    A. N. Pronin
    A. V. Ryazanov
    D. N. Solntsev
    A. E. Khrobostov
    Thermal Engineering, 2023, 70 : 523 - 533
  • [27] Coolant Temperature Measurements in the Core of TRIGA Research Reactor
    Henry, Romain
    Matkovic, Marko
    25TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2016), 2016,
  • [28] SIMULATION ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD
    Li, H.
    Qiu, S. Z.
    Su, G. H.
    ICONE17, VOL 4, 2009, : 667 - 672
  • [29] Neutronic analysis of nanofluids as a coolant in the Bushehr VVER-1000 reactor
    Zarifi, Ehsan
    Jahanfarnia, Gholamreza
    Veisy, Farzad
    NUKLEONIKA, 2012, 57 (03) : 375 - 381
  • [30] CFD study on coolant mixing in VVER-440 fuel rod bundles and fuel assembly heads
    Toth, S.
    Aszodi, A.
    NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (09) : 2194 - 2205