海水淡化堆非能动余热排出特性模拟实验研究
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  • 英文篇名:Simulation Experimental Research on Passive Residual Heat Removal Performance for Nuclear Seawater Desalination Reactor
  • 作者:聂常华 ; 许世杰 ; 刘逊 ; 卓文彬 ; 李长林 ; 郑华 ; 李朋洲 ; 余庆林
  • 英文作者:NIE Chang-hua;XU Shi-jie;LIU Xun;ZHUO Wen-bin;LI Chang-lin;ZHENG Hua;LI Peng-zhou;Yu Qing-lin;Reactor Engineering Sub-Institute, Nuclear Power Institute of China;
  • 关键词:海水淡化堆 ; 非能动余热排出系统 ; 实验研究 ; RELAP5程序
  • 英文关键词:Nuclear seawater desalination reactor,Passive residual heat removal system,Experiment research,RELAP5 code
  • 中文刊名:HDLG
  • 英文刊名:Nuclear Power Engineering
  • 机构:中国核动力研究设计院反应堆工程研究所;
  • 出版日期:2013-12-15
  • 出版单位:核动力工程
  • 年:2013
  • 期:v.34;No.201
  • 语种:中文;
  • 页:HDLG201306024
  • 页数:5
  • CN:06
  • ISSN:51-1158/TL
  • 分类号:106-110
摘要
在规模因子为1/45的海水淡化堆综合模拟实验装置上,开展海水淡化堆非能动余热排出特性模拟实验研究。验证海水淡化堆非能动安全系统能够保证在诸如全场断电等事故导致紧急停堆后堆芯余热的有效导出,分析系统参数对非能动余热排出特性的影响规律。利用RELAP5/MOD3.2程序对非能动余热排出实验进行模拟分析,结果表明RELAP5/MOD3.2程序能够较好模拟海水淡化堆非能动安全系统的非能动余热导出过程,计算结果与实验结果符合较好。
        Simulation experiments were conducted on the integral simulation test facility with scaling ratio 1/45 for nuclear seawater desalination reactor, the performance of the passive residual heat removal from the core was presented in the paper. The experimental results demonstrated that residual heat can be removed from the core effectively after the reactor was shut off in emergency because some accidents take place, such as station blackout accidents. The paper also presented the RELAP5/MOD3.2 code simulation results for the experimental conditions, and the calculation results of the code is well accordance with the experimental results.
引文
[1]Ishii M,Kataoka I.Similarity Analysis and Scaling Criteria for PWRS under Single-Phase and Two-Phase Natural Circulation[R].NUREG/CR-3267.1983.

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