An experimental investigation of a passive cooling unit for nuclear plant containment

被引:149
|
作者
Liu, H [1 ]
Todreas, NE [1 ]
Driscoll, MJ [1 ]
机构
[1] MIT, Dept Nucl Engn, Cambridge, MA 02139 USA
关键词
D O I
10.1016/S0029-5493(00)00229-6
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
A set of condensation experiments in the presence of noncondensables (e.g. air, helium) was conducted to evaluate the heat removal capacity of a passive cooling unit in a post-accident containment. Condensation heat transfer coefficients on a vertically mounted smooth tube have been obtained for total pressure ranging from 2.48 x 10(5) Pa(abs) to 4.55 x 10(5) Pa(abs) and air mass fraction ranging from 0.30 to 0.65. An empirical correlation for heat transfer coefficient (h), has been developed in terms of a parameter group made up of steam mole fraction (Xs), total pressure (P-t), temperature difference between bulk gas and wall surface (dT). This correlation covers all data points within 20%. All data points are also in good agreement with the prediction of the diffusion layer model (DLM) with suction and are approximately 2.2 times the Uchida heat transfer correlation. Experiments with an axial shroud around the test tube to model the restriction on radial flow experienced within a tube bundle demonstrated a reduction of the heat transfer coefficient by a factor of about 0.6. The effect of helium (simulating hydrogen) on the heat transfer coefficient was investigated for helium mole fraction in noncondensable gases (X-He/X-nc) at 15, 30 and 60%. It was found that the condensation heat transfer coefficients are generally lower when introducing helium into noncondensable gas. The difference is within 20% of air-only cases when X-He/X-ac is less than 30% and total pressure is less than 4.55 x 105 Pa(abs). A gas stratification phenomenon was clearly observed for helium mole fraction in excess of 60%. (C) 2000 Elsevier Science S.A. All rights reserved.
引用
收藏
页码:243 / 255
页数:13
相关论文
共 50 条
  • [21] Experimental Investigation on Buckling of Ellipsoidal Head of Steel Nuclear Containment
    Li, Keming
    Zheng, Jinyang
    Zhang, Zekun
    Gu, Chaohua
    Zhang, Xiaoping
    Liu, Shenghua
    Ge, Honghui
    Gu, Caisheng
    Lin, Guanghua
    [J]. JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2017, 139 (06):
  • [22] Experimental Investigation on Buckling of Steel Nuclear Containment with Elliptical Head
    Li, Keming
    Zheng, Jinyang
    Zhang, Zekun
    [J]. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 5, 2017,
  • [23] Analysis of a passive containment cooling system for NPPs
    Huang, Zheng
    [J]. Hedongli Gongcheng/Nuclear Power Engineering, 2014, 35 (06): : 31 - 36
  • [24] Passive containment cooling of PWRS with thermosyphon loops
    Hurtado, AM
    Leiendecker, M
    [J]. ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 95 - 98
  • [25] Passive containment cooling of PWRs with thermosyphon loops
    Hurtado, AM
    Leiendecker, M
    [J]. ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 95 - 98
  • [26] Containment passive-cooling design concepts
    Gavrilas, M
    Todreas, NE
    Driscoll, MJ
    [J]. PROGRESS IN NUCLEAR ENERGY, 1998, 32 (3-4) : 647 - 655
  • [27] Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant
    Di Maio, Francesco
    Nicola, Giancarlo
    Borgonovo, Emanuele
    Zio, Enrico
    [J]. RELIABILITY ENGINEERING & SYSTEM SAFETY, 2016, 151 : 12 - 19
  • [28] Numerical investigation of natural convection inside the containment with recovering passive containment cooling system using GASFLOW-MPI
    Li, Yabing
    Zhang, Han
    Xiao, Jianjun
    Travis, J. R.
    Jordan, Thomas
    [J]. ANNALS OF NUCLEAR ENERGY, 2018, 114 : 1 - 10
  • [29] Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety
    Haag, Michel
    Dolganov, Iurii
    Leyer, Stephan
    [J]. NUCLEAR TECHNOLOGY, 2024, 211 (01) : 111 - 126
  • [30] RESEARCH ON THERMAL HYDRAULIC CHARACTERISTICS OF PASSIVE CONTAINMENT COOLING SYSTEM FOR SHIP NUCLEAR POWER PLATFORM
    Dai, Chunhui
    Wu, Jun
    Tan, Sichao
    Zhao, Zhenxing
    Xiao, Qi
    Liu, Zhouyang
    Liu, Yong
    [J]. PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 2, 2016,