Development and analysis of passive residual heat-removal system on secondary side of small reactor

被引：0
|
作者：
Dong B. [1 ]
Xiao Y. [1 ,2 ]
Li J. [2 ]
Xu Z. [2 ]
Liu M. [2 ]
Liu L. [2 ]
Fu J. [2 ]
Gu H. [2 ]
机构：
[1] College of Smart Energy, Shanghai Jiaotong University, Shanghai
[2] School of Mechanical Engineering, Shanghai Jiaotong University, Shanghai
来源：
He Jishu/Nuclear Techniques | 2024年 / 47卷 / 03期
基金：
中国国家自然科学基金;
关键词：
Natural circulation; Passive; RELAP5; Residual heat-removal system; Small reactor;
D O I：
10.11889/j.0253-3219.2024.hjs.47.030602
中图分类号：
学科分类号：
摘要：
[Background] Passive residual heat-removal system (PRHRS) based on natural circulation has been widely used in small reactors connected on secondary side loop. [Purpose] This study aims to develop and analyze a passive residual heat-removal system on the secondary side of a small reactor to improve reactor safety. [Methods] Based on the completed heat-transfer experiment of the intermediate circuit of a small integrated nuclear power plant, Reactor Excursion and Leak Analysis Program (RELAP) was employed to determine and analyze the natural circulation characteristics of the intermediate loop were determined and analyzed. [Results] The heat transfer rate results of the program are in good agreement with the experimental data, and the natural cycle characteristics of PRHRS can be characterized. The pressure of the system loop is determined by the average temperature of the primary side of the steam generator (SG), and the difference in the inlet temperature of the SG primary side, mass flow rate, and height of the cooling and heating sources significantly influence the heat-transfer performance of the SG system. The heat-transfer performance of the waste-heat-removal system is more sensitive to the resistance of the system loop when the temperature of the primary-side inlet of the SG is higher. [Conclusions] These results provide a valuable application for further investigations of passive systems in small reactors. © 2024 Science Press. All rights reserved.
引用
收藏
相关论文
共 16 条
  • [1] HUANGFU Youming, Design and research of passive waste heat removal system on secondary side of offshore floating power station based on RELAP5, (2019)
  • [2] Schulz T L., Westinghouse AP1000 advanced passive plant [J], Nuclear Engineering and Design, 236, 14 − 16, pp. 1547-1557, (2006)
  • [3] Li Y Q, Chang H J, Ye Z S, Et al., Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient[J], Progress in Nuclear Energy, 88, pp. 375-397, (2016)
  • [4] Cho Y J, Bae S W, Bae B U, Et al., Analytical studies of the heat removal capability of a passive auxiliary feedwater system (PAFS) [J], Nuclear Engineering and Design, 248, (2012)
  • [5] CHEN Bingde, XIAO Zejun, ZHOU Renming, Et al., Test facility and research program of AC600 secondary sidePassive emergency core residual heat removal system [J], Nuclear Power Engineering, 19, 2, (1998)
  • [6] Wang M J, Zhao H, Zhang Y P, Et al., Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000[J], Annals of Nuclear Energy, 45, (2012)
  • [7] Sun D C, Li Y, Xi Z, Et al., Experimental evaluation of safety performance of emergency passive residual heat removal system in HPR1000[J], Nuclear Engineering and Design, 318, (2017)
  • [8] Zhang Y P, Qiu S Z, Su G H, Et al., Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part Ⅰ: air cooling condition[J], Progress in Nuclear Energy, 53, 5, (2011)
  • [9] Wu G W, Li Y Z, Wang M H, Et al., Design and performance analysis of passive residual heat removal system for a lead-cooled fast reactor[J], Progress in Nuclear Energy, 103, pp. 236-242, (2018)
  • [10] Bae B U, Kim S, Park Y S, Et al., Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident[J], Nuclear Engineering and Design, 275, pp. 249-263, (2014)
12