Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITL

被引:16
作者
Min, Byung-Yeon [1 ]
Park, Hyun-Sik [1 ]
Shin, Yong-Chul [1 ]
Yi, Sung-Jae [1 ]
机构
[1] Korea Atom Energy Res Inst, Taejon 305353, South Korea
基金
新加坡国家研究基金会;
关键词
SMART; VISTA-ITL; PRHRS; Natural circulation; CIRCULATION;
D O I
10.1016/j.anucene.2014.03.001
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
The purpose of this paper is to verify the integrity and performance of the passive residual heat removal system (PRHRS) for the SMART design during a steady state condition. The system's overall thermal-hydraulic behavior during the steady state operation of the PRHRS of the SMART reactor was simulated using the VISTA-ITL, a small-scale integral effect test loop for the SMART design. The PRHRS is operated properly when the reactor is shutdown considering all the operating conditions of the SMART plant. The steady-state PRHRS performance tests are divided into three conditions of 100% scaled power, 20% scaled power, and hot standby condition. The experimental results show that PRHRS's integrity and performance are proper for these three conditions. The steady state condition was well operated to satisfy the initial test conditions presented in the test requirement, and its boundary condition was properly simulated. The natural circulation flow rate in the primary system was about 10.0%, 10.6%, and 10.6% for 100% scaled power, 20% scaled power, and hot standby condition, respectively. The PRHRS's natural circulation flow was formed as much as 10.1%, 11.7% and 9.1% for 100% scaled power, 20% scaled power and hot standby condition of its nominal value in the early stage of the PRHRS operation, respectively. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:118 / 124
页数:7
相关论文
共 50 条
  • [41] EXPERIMENTAL RESEARCH ON NON-CONDENSABLE GASES EFFECTS IN PASSIVE DECAY HEAT REMOVAL SYSTEM
    Liu, Yang
    Jia, Haijun
    Li Weihua
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 3, 2016,
  • [42] Analysis of start-up and long-term operation characteristics of passive residual heat removal system
    Lyu, Xing
    Peng, Minjun
    Xia, Genglei
    ANNALS OF NUCLEAR ENERGY, 2019, 130 : 69 - 81
  • [43] Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor
    Huang, Tao
    Zhang, Y. P.
    Gong, Houjun
    Tian, W. X.
    Su, G. H.
    Qiu, S. Z.
    PROGRESS IN NUCLEAR ENERGY, 2016, 90 : 164 - 174
  • [44] Risks Analysis and Countermeasures in Natural Circulation Test of CAP1400 Passive Residual Heat Removal System
    Li W.
    Li P.
    Li W.
    Kong X.
    Huang Y.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 (01): : 167 - 171
  • [45] A multi-scale CFD-system coupled code for transient analysis of the passive residual heat removal system of MHTGR
    Zhao, Hangbin
    Zheng, Yanhua
    Ma, Tao
    Dong, Yujie
    ANNALS OF NUCLEAR ENERGY, 2020, 141 (141)
  • [46] Design of a natural draft air-cooled condenser and its heat transfer characteristics in the passive residual heat removal system for 10 MW molten salt reactor experiment
    Zhao, Hangbin
    Yan, Changqi
    Sun, Licheng
    Zhao, Kaibin
    Fa, Dan
    APPLIED THERMAL ENGINEERING, 2015, 76 : 423 - 434
  • [47] Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower
    Na, Min Wook
    Shin, Doyoung
    Park, Jae Hyung
    Lee, Jeong Ik
    Kim, Sung Joong
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (05) : 964 - 974
  • [48] Thermal Hydraulic Analysis of a Novel Passive Residual Heat Removal System with Loop Thermosyphons for the Pool-vessel Reactor
    Wu, Xubin
    Zhang, Wenwen
    Hao, Wentao
    Ye, Zishen
    Xie, Heng
    Shi, Lei
    NUCLEAR ENGINEERING AND DESIGN, 2023, 412
  • [49] Experimental Demonstration of Flow Diodes Applicable to a Passive Decay Heat Removal System for Sodium-Cooled Reactors
    Chikazawa, Yoshitaka
    Aizawa, Kousuke
    Shiraishi, Tadashi
    Sakata, Hideyuki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2009, 46 (04) : 321 - 330
  • [50] Numerical analysis on transient characteristics of AP1000 passive residual heat removal system under station blackout accident
    Wang, Bao-Sheng
    Wang, Dong-Qing
    Dong, Hua-Ping
    Jiang, Jing
    Zhang, Jian-Min
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (09): : 1514 - 1521