Seismic analysis of the HIFAR nuclear reactor secondary coolant pipework and associated inlet and outlet headers

被引：0
|
作者：
Bendeich, P [1 ]
Payten, W [1 ]
机构：
[1] Australian Nucl Sci & Technol Org, Div Mat, Menai, NSW 2234, Australia
来源：
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING | 2000年 / 77卷 / 2-3期
关键词：
seismic; pipework; nuclear reactor;
D O I：
10.1016/S0308-0161(99)00085-X
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
A seismic analysis was carried out to examine the integrity of the secondary coolant circuit within the reactor containment building for the HIFAR reactor located at Lucas Heights. Eigen evaluations of the structure for the first 40 modes were determined for a number of piping configurations. A response spectrum for a 0.2g earthquake was then used to excite the structure and the resulting stresses were examined for areas of potential failure. (C) 2000 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码：133 / 138
页数：6
相关论文
共 50 条
  • [21] Performance analysis on a novel microchannel heat sink with secondary flow channels and staggered inlet and outlet
    Li, Lin
    Hu, Yu-Peng
    Li, You-Rong
    INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, 2024, 159
  • [22] Seismic analysis of a nuclear reactor with fluid-structure interaction
    Sigrist, Jean-Francois
    Broc, Daniel
    Laine, Christian
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2005, VOL 4, 2005, 4 : 37 - 44
  • [23] COMPUTERIZED PROCESS ANALYSIS OF THE SECONDARY COOLANT CIRCUIT IN NUCLEAR-POWER-PLANTS
    HENSEL, W
    HOLLASKY, R
    KERNENERGIE, 1990, 33 (11): : 431 - 432
  • [24] Analysis of coolant flow distribution characteristics at core inlet of small pressurized water reactor under rolling condition
    Zeng, Jinyuan
    Mao, Yulong
    Li, Bingwen
    Zhu, Jianmin
    Hu, Yisong
    Chen, Jun
    FRONTIERS IN ENERGY RESEARCH, 2024, 11
  • [25] Simulation and Analysis of Reactor Coolant System for Two-Loop Nuclear Power Plant
    Zeng C.
    Zhao Y.
    Ye Z.
    Ren Y.
    Hedongli Gongcheng/Nuclear Power Engineering, 2018, 39 : 58 - 61
  • [26] Thermal analysis of heated cylinder simulating nuclear reactor during loss of coolant accident
    Sato, Hiroyuki
    Ohashi, Hirofumi
    Tachibana, Yukio
    Kunitomi, Kazuhiko
    Ogawa, Masuro
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2014, 51 (11-12) : 1317 - 1323
  • [27] CONTINUOUS RADIOCHEMICAL ANALYSIS OF FISSION-PRODUCTS IN AN AQUEOUS COOLANT OF A NUCLEAR-REACTOR
    MOSKVIN, LN
    ZAKHAROV, LK
    LEONTEV, GG
    MELNIKOV, VA
    ORLENKOV, IS
    SLUTSKII, GK
    SOVIET ATOMIC ENERGY, 1975, 39 (06): : 1070 - 1073
  • [28] RESEARCH ON THE STRUCTURE INTEGRITY ANALYSIS OF FLYWHEEL OF REACTOR COOLANT PUMP IN NUCLEAR POWER PLANT
    Zhang, Jian
    Zuo, Yongde
    Chen, Xingjiang
    Zhang, Qinghong
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 2, 2017,
  • [29] Hydrodynamics of the Coolant in the Outlet Section of a Fuel Cartridge with Heads of Different Designs of the Reactor Core RITM of a Low-Power Nuclear Plant
    S. M. Dmitriev
    T. D. Demkina
    A. A. Dobrov
    D. V. Doronkov
    D. S. Doronkova
    M. A. Legchanov
    A. N. Pronin
    A. V. Ryazanov
    D. N. Solntsev
    A. E. Khrobostov
    Thermal Engineering, 2023, 70 : 849 - 859
  • [30] Hydrodynamics of the Coolant in the Outlet Section of a Fuel Cartridge with Heads of Different Designs of the Reactor Core RITM of a Low-Power Nuclear Plant
    Dmitriev, S. M.
    Demkina, T. D.
    Dobrov, A. A.
    Doronkov, D. V.
    Doronkova, D. S.
    Legchanov, M. A.
    Pronin, A. N.
    Ryazanov, A. V.
    Solntsev, D. N.
    Khrobostov, A. E.
    THERMAL ENGINEERING, 2023, 70 (11) : 849 - 859
12345