NST  >> Vol. 5 No. 4 (October 2017)

    核反应堆堆芯在线监测方法研究
    The Research of Method for Core On-Line Monitoring

  • 全文下载: PDF(681KB) HTML   XML   PP.216-225   DOI: 10.12677/NST.2017.54028  
  • 下载量: 286  浏览量: 1,015  

作者:  

张欣:黑龙江省电力科学研究院,黑龙江 哈尔滨

关键词:
实时仿真在线监测程序耦合Real-Time Simulation On-Line Monitoring Codes Coupling

摘要:

堆芯内布置的探测器数量通常非常有限,因此堆芯内很多运行参数无法在线监测,比如燃料包壳表面温度,燃料芯块中心温度,DNBR等,对这些安全性指标进行在线监测及分析可以辅助操作员更好的了解整个堆芯运行状态,提高反应堆运行安全性。本论文以秦山一期反应堆为研究对象,利用THEATRe程序对反应堆热工水力部分进行仿真,通过REMARK程序对反应堆堆芯物理部分进行仿真,然后在GSE仿真平台上对两个程序进行耦合,实现对反应堆堆芯物理、热工的反馈计算,并在此基础上以秦山一期核电站仿真机数据作为边界和输入条件对秦山一期核电站进行实时计算,以实现耦合仿真程序实现对堆芯安全性参数的在线监测。

Because of the lack of detectors placed in the reactor core, the reactor operators cannot monitor some important core operation parameters on line, such as the maximum cladding surface temperature, the maximum fuel pellet center and MDNBR. Online monitoring those parameters can help the operator to know the status of reactor core better and improve the operate safety. In this paper, the reactor physics real-time simulation program REMARK and the thermal hydraulic real-time simulation program THEATRe are coupled on the GSE simulation platform to simulate the Qinshan Phase I reactor. The operation data of simulator are used as boundary conditions of coupling codes. The results show that the values are in good agreement with the actual situation and can fully meet the requirements of real-time computing.

文章引用:
张欣. 核反应堆堆芯在线监测方法研究[J]. 核科学与技术, 2017, 5(4): 216-225. https://doi.org/10.12677/NST.2017.54028

参考文献

[1] 李富, 周旭华, 王登营, 郭炯, 罗征培. 采用堆芯外探测器监测堆内功率分布[J]. 核动力工程, 2010, 31(2): 92.
[2] Beard, C.L., Morita, T., et al. (1988) Core Power Distribution Methodology in the BEACON PWR Core Monitoring System. Proceedings of the 1988 ANS International Reactor. Physics Conference, Jackson Hole, September 1988, IV.175-IV.183.
[3] Banda, L.A. and Bollac-asa, D. (1991) Evolution of Core Power Monitoring Systems at ABB Combustion Engineering Nuclear Power. Proceedings of a Spe-cialists’ Meeting on In-Core Instrumentation and Reactor Core Assessment. OECD NEA, USA.
[4] Vegh, J., Pos, I., Horvath, C., Kalya, Z. and Parko, T. (2015) An Enhanced Reactor Analysis Tool Applied for Continuous Core Parameter Monitoring at Paks NPPJ. Nuclear Engineering and Design, 292, 262-264.
[5] 周琴. 堆芯安全性在线分析[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2014.
[6] GSE (2003) GSE.THEATRe TM User Guide.2003:2P.
[7] 欧阳予. 秦山核电工程[M]. 北京: 原子能出版社, 2000: 60-68.