Thermal-hydraulic tests on passive containment cooling system of advanced PWR

被引：0
|
作者：
Tan, Shu-Shi [1 ]
Leng, Gui-Jun [1 ]
Cheng, Xu [1 ]
Ni, Yong-Jun [1 ]
机构：
[1] Nucl. Power Inst. of China, Chengdu 610041, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2002年 / 23卷 / SUPPL.期
关键词：
Cooling systems - Nuclear reactor accidents;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Thermal-hydraulic tests on the passive containment cooling system performed at the modified PASCO test facility is a key project of the advanced PWR. It includes heat transfer tests under dry conditions, wet conditions and radiating tests. The effect of the temperature, channel dimension, wall emissivity water film flow are discussed in the tests. The experimental data can be used to verify the models in computer codes and to give a reference for designing PCCS, and improve the understanding of passive safety features involved in PCCS.
引用
收藏
页码：30 / 33
相关论文
共 50 条
  • [11] Optimal design of passive containment cooling system for innovative PWR
    Ha, Huiun
    Lee, Sangwon
    Kim, Hangon
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (05) : 941 - 952
  • [12] EVALUATION OF ADVANCED THERMAL-HYDRAULIC SYSTEM CODES FOR SAFETY ANALYSIS OF INTEGRAL TYPE PWR
    Choi, J.
    Woods, B.
    PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2013, VOL 6B, 2014,
  • [13] Thermal-hydraulic tests of finned recirculating cooling equipment
    Lychakov, V. D.
    Egorov, M. Yu
    Matyash, A. S.
    Shcheglov, A. A.
    XXXV SIBERIAN THERMOPHYSICAL SEMINAR, 2019, 2019, 1382
  • [14] TAPINS: A THERMAL-HYDRAULIC SYSTEM CODE FOR TRANSIENT ANALYSIS OF A FULLY-PASSIVE INTEGRAL PWR
    Lee, Yeon-Gun
    Park, Goon-Cherl
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2013, 45 (04) : 439 - 458
  • [15] Thermal-hydraulic analysis on the effect of operator action in the loss of shutdown cooling system accident in a PWR
    Son, Young-Seok
    Shin, Jee-Young
    NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (19) : 2054 - 2063
  • [16] Improvement of the MELCOR condensation heat transfer model for the thermal-hydraulic analysis of a PWR containment
    Yoo, Jee Min
    Kang, Jin Hoon
    Yun, Byong Jo
    Hong, Seong Wan
    Jeong, Jae Jun
    PROGRESS IN NUCLEAR ENERGY, 2018, 104 : 172 - 182
  • [17] Influence of Passive Containment Cooling System on containment thermal hydraulic transients during a postulated severe accident
    Adinarayana, K. N., V
    Ali, Seik Mansoor
    PROGRESS IN NUCLEAR ENERGY, 2021, 142
  • [18] THERMAL-HYDRAULIC CHARACTERISTICS AND HEAT REMOVAL CAPABILITY OF CONTAINMENT COOLING SYSTEM WITH EXTERNAL WATER WALL
    KATAOKA, Y
    FUKUI, T
    HATAMIYA, S
    MURASE, M
    NAITOH, M
    SUMIDA, I
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1990, 27 (09) : 802 - 814
  • [19] THERMAL-HYDRAULIC ANALYSIS OF A PASSIVE CONTAINMENT COOLING SYSTEM USING DYNAMIC LIQUID FILM MODEL IN CFD CODE GASFLOW-MPI
    Xiao, Jianjun
    Travis, John R.
    Bottoni, Maurizio
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016,
  • [20] Research on Thermal Hydraulic Characteristic of HPR1000 Passive Containment Cooling System
    Ge K.
    Wang H.
    Wang M.
    Tian W.
    Su G.
    Qiu S.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (05): : 769 - 777
12345