EVALUATION OF THE SCALING ANALYSIS MODEL OF THE EU-APR1400 CORE CATCHER COOLING SYSTEM TEST FACILITY

被引：0
|
作者：
Rhee, Bo W. [1 ]
Ha, K. S. [1 ]
Park, R. J. [1 ]
Song, J. H. [1 ]
机构：
[1] Korea Atom Energy Res Inst, Yuseong, Daejon, South Korea
来源：
PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 2A | 2014年
关键词：
D O I：
暂无
中图分类号：
TH [机械、仪表工业];
学科分类号：
0802 ;
摘要：
This paper describes the basic design features of the EU-APR1400 reactor core catcher cooling system and its test facility, and the associated scaling analysis model An assessment of the validity of the scaling analysis using the preliminary performance test result of the test facility is described. This includes comparison of the predicted mass flow rate of the test loop as a function of the heat load to the facility, inlet flow subcooling and system pressure to the experimental results.
引用
收藏
页数：5
相关论文
共 25 条
  • [1] Detailed evaluation of two phase natural circulation flow in the cooling channel of the ex-vessel core catcher for EU-APR1400
    Park, Rae-Joon
    Ha, Kwang-Soon
    Rhee, Bo-Wook
    Kim, Hwan Yeol
    NUCLEAR ENGINEERING AND DESIGN, 2016, 298 : 33 - 40
  • [2] Experimental study on two-phase flow natural circulation in a core catcher cooling channel for EU-APR1400 using air-water system
    Song, Ki Won
    Thanh Hung Nguyen
    Ha, Kwang Soon
    Kim, Hwan Yeol
    Song, Jinho
    Park, Hyun Sun
    Revankar, Shripad T.
    Kim, Moo Hwan
    NUCLEAR ENGINEERING AND DESIGN, 2017, 316 : 75 - 88
  • [3] TWO-PHASE NATURAL CIRCULATION COOLING PERFORMANCE ASSESSMENT AND SAFETY ANALYSIS FOR APR1400 CORE CATCHER SYSTEM
    Song, Ki Won
    Revankar, Shripad T.
    Park, Hyun Sun
    Rhee, Bo
    Ha, Kwang Soon
    Park, Rae Joon
    Song, Jin Ho
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 5, 2014,
  • [4] Systematic analysis of a station blackout scenario for APR1400 with test facility ATLAS and MARS code from scaling viewpoint
    Yu, Xin-Guo
    Park, Hyun-Sik
    Kim, Yeon-Sik
    Kang, Kyoung-Ho
    Cho, Seok
    Choi, Ki-Yong
    NUCLEAR ENGINEERING AND DESIGN, 2013, 259 : 205 - 220
  • [5] Assessment of APR-1400 Emergency Core Cooling System Performance for Design Basis LOCA Redefinition
    Kang, Dong Gu
    Ahn, Seung-Hoon
    Chang, Soon Heung
    Huh, Byung-Gil
    Bang, Young-Seok
    Seul, Kwang-Won
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 3, 2014,
  • [6] Scaling analysis of core pressure drop in reduced height integral test facility
    Ju, P.
    Long, B.
    Li, L.
    Su, Q.
    Wu, X.
    Lu, D.
    KERNTECHNIK, 2018, 83 (03) : 178 - 180
  • [7] Development of RCS-Containment Coupled Analysis Model and Evaluation of LBLOCA for APR-1400
    Kim, Jeongyun
    Bang, Young-Seok
    26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017), 2017,
  • [8] CMT scaling analysis and distortion evaluation in passive integral test facility
    Deng, Cheng-Cheng
    Chang, Hua-Jian
    Qin, Ben-Ke
    Wang, Han
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (11): : 2026 - 2032
  • [9] Study of Two-Phase Natural Circulation Cooling of Core Catcher System Using Scaled Model
    Revankar, Shripad T.
    Song, Kiwon
    Rhee, B. W.
    Park, R. J.
    Ha, K. S.
    Song, J. H.
    JOURNAL OF THERMAL SCIENCE AND ENGINEERING APPLICATIONS, 2015, 7 (03) : 1 - 9
  • [10] Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software
    Zubair, Muhammad
    Al Suwaidi, Reem Rashid
    Al Souqi, Alwaad Abdullah
    PROGRESS IN NUCLEAR ENERGY, 2021, 141
123