Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software

被引:3
|
作者
Zubair, Muhammad [1 ]
Al Suwaidi, Reem Rashid [1 ]
Al Souqi, Alwaad Abdullah [1 ]
机构
[1] Univ Sharjah, Dept Mech & Nucl Engn, Sharjah 27272, U Arab Emirates
关键词
Loss of Coolant Accident; Safety injection system; Flownex; Sensitivity; Uncertainty; APR; 1400;
D O I
10.1016/j.pnucene.2021.103949
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 behavior of Emergency Core Cooling System (ECCS) in an Advanced Pressurized Reactor 1400 (APR) during the early stage of Loss of Coolant Accident (LOCA), was analyzed by using Flownex software. The LOCA has been considered in the primary loop in one of the cold legs of APR1400. Through evaluation of the varying break sizes, sensitivity analysis as well as an uncertainty analysis was performed on the Safety Injection System (SIS) where its performance was tested to observe its capability to mitigate a LOCA. The sensitivity analysis was performed on five out puts including core mass flow rate, break mass flow rate, pressure, temperature, and SIS mass flow rate. Ten different break sizes were considered, and sensitivity coefficients were obtained and used to calculate the uncertainty of all outputs. It was observed that all five output responses were sensitive to changes in the input parameter, and both high levels of uncertainty as well as low were observed.
引用
收藏
页数:10
相关论文
共 23 条
  • [1] 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,
  • [2] An alternative cooling solution during loss of coolant accident with emergency core cooling system failure in NUSCALE nuclear reactor
    Susyadi
    Juarsa, Mulya
    Putra, Nandy
    Koestoer, Raldi Artono
    PROGRESS IN NUCLEAR ENERGY, 2024, 169
  • [3] CANDU-6 fuel channel behavior after a loca coincident with loss of emergency core cooling accident
    Ion, RA
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '97, 1997, : 232 - 235
  • [4] Downcomer Boiling Phenomena Analysis during Large Break Loss of Coolant Accident In APR1400
    Yoon, Ho Joon
    Alhashmi, Safa Mohamed Aidaroos Salem
    Addad, Yacine
    24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015), 2015,
  • [5] EXPERIMENTAL INVESTIGATION OF CORE COOLING AND SYSTEM BEHAVIOR FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PWR
    BRAND, B
    MANDL, R
    WATZINGER, H
    ATOMKERNENERGIE-KERNTECHNIK, 1986, 49 (1-2): : 54 - 60
  • [6] Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident
    Park, Kweonha
    Khor, Chong Lee
    NUCLEAR ENGINEERING AND DESIGN, 2015, 293 : 458 - 467
  • [7] INVESTIGATION OF CHEMICAL EFFECTS ON EMERGENCY CORE COOLING FILTRATION HEAD LOSS AFTER LOSS OF COOLANT ACCIDENT
    Park, Jong Woon
    Park, Byung Gi
    Kim, Chang Hyun
    PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, : 511 - 518
  • [8] Passive containment cooling system (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a postulated Loss of Coolant Accident (LOCA)
    Paladino, Domenico
    Dreier, Joerg
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) : 3925 - 3934
  • [9] Effects of oxide and hydrogen on the behavior of Zircaloy-4 cladding during the loss of the coolant accident (LOCA)
    Kim, Jun Hwan
    Choi, Byoung Kwon
    Baek, Jong Hyuk
    Jeong, Yong Hwan
    NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (22) : 2386 - 2393