Investigation on two-phase critical flow for loss-of-coolant accident of pressurized water reactor

被引:0
|
作者
徐进良
陈听宽
李鲁伟
机构
关键词
Critical flow; System transition characteristic; Wall surface cavity nucleation model; Pressurized water reactor;
D O I
暂无
中图分类号
O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Investigationontwo-phasecriticalflowforloss-of-coolantaccidentofpressurized water reactorXuJin-Liang(徐进良)(InstituteofNuclearE...
引用
收藏
页码:143 / 150
页数:8
相关论文
共 50 条
  • [21] PRESSURE-DROP THROUGH BROKEN COLD LEG DURING REFLOOD PHASE OF LOSS-OF-COOLANT ACCIDENT OF PRESSURIZED WATER-REACTOR
    AKIMOTO, H
    IGUCHI, T
    MURAO, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1984, 21 (06) : 450 - 465
  • [22] PRESSURIZED-WATER-REACTOR LOSS-OF-COOLANT ACCIDENTS BY HYPOTHETICAL VESSEL RUPTURE
    DOAN, PL
    LANNING, DD
    RASMUSSE.NC
    NUCLEAR SAFETY, 1973, 14 (04): : 291 - 304
  • [23] Simulation of Loss of Coolant Accident in an Integral Pressurized Water Reactor (IPWR)
    Khan, Salah Ud-Din
    Peng, Minjun
    Zubair, Muhammad
    FRONTIERS OF MANUFACTURING SCIENCE AND MEASURING TECHNOLOGY, PTS 1-3, 2011, 230-232 : 410 - 414
  • [24] An Improved Best Estimate Plus Uncertainty Method for Small-Break Loss-of-Coolant Accident in Pressurized Water Reactor
    Sun, Dabin
    Zhang, Zhijian
    Li, Xinyu
    Li, Lei
    Wang, He
    Xu, Anqi
    Chen, Sijuan
    FRONTIERS IN ENERGY RESEARCH, 2020, 8
  • [25] Using Kernel Density Estimation to Detect Loss-of-Coolant Accidents in a Pressurized Water Reactor
    Farber, Jacob A.
    Cole, Daniel G.
    Al Rashdan, Ahmad Y.
    Yadav, Vaibhav
    NUCLEAR TECHNOLOGY, 2019, 205 (08) : 1043 - 1052
  • [27] ECC PERFORMANCE DURING LOSS-OF-COOLANT EXPERIMENTS IN A SMALL PRESSURIZED WATER-REACTOR
    DOUCETTE, CO
    NAFF, SA
    SCHWARZ, WF
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 26 : 49 - 49
  • [28] DAMAGE MECHANISMS TO CABLES IN REACTOR LOSS-OF-COOLANT ACCIDENT ENVIRONMENTS
    LEADON, RE
    LURIE, NA
    NUCLEAR TECHNOLOGY, 1979, 46 (03) : 442 - 446
  • [29] AVAILABILITY OF THE EMERGENCY CORE COOLING SYSTEM OF A CANDU PRESSURIZED HEAVY-WATER REACTOR FOLLOWING A SMALL LOSS-OF-COOLANT ACCIDENT
    ALKUSAYER, TA
    NUCLEAR TECHNOLOGY, 1985, 69 (03) : 293 - 307
  • [30] Modelling of Droplets Entrainment for the Analysis of Reflood Process during a Large-break Loss-of-Coolant Accident in a Pressurized Water Reactor
    Yoo, Jee Min
    Jeong, Jae Jun
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS B, 2020, 44 (06) : 357 - 370