期刊文献+

基于MATLAB的反应堆保护系统功能逻辑测试设计方法研究 被引量:1

Research on Test Design Method of Reactor Protection System Based on Simulation Software
下载PDF
导出
摘要 核电站反应堆保护系统需要进行复杂的运算处理,在对其进行功能测试时,需要设计复杂的功能测试用例,执行功能测试来验证其运算处理功能的正确性。通过人工方式进行测试用例的设计,存在效率低、难以胜任复杂的多变量运算等问题。为此测试人员研究了通过计算机仿真平台,实现反应堆保护系统功能测试用例的计算机辅助设计的方法。该方法显著提高了复杂逻辑运算的测试用例设计效率和准确率。该方法已经在CPR1000、ACPR1000、HTR等多种堆型的反应堆保护系统测试中得到应用。 Nuclear power plant reactor protection system requires complex arithmetic processing. When performing functional tests on it, it is necessary to design complex functional test cases and perform functional tests to verify the correctness of its arithmetic processing functions. The design of test cases through manual methods has several problems such as the low efficiency and incompetence of complex multivariable operations. Therefore, in order to improve the design efficiency and accuracy of test cases, the testers studied computer-aided design methods for implementing functional test cases of reactor protection systems through a computer simulation platform. This method has been applied in the testing of various reactor protection systems such as CPR1000, ACPR1000, and HTR.
出处 《自动化博览》 2018年第11期93-95,共3页 Automation Panorama1
关键词 反应堆保护系统 功能测试 测试用例 测试设计 Reactor protection system Function test Test case Test design
  • 相关文献

参考文献2

二级参考文献12

  • 1李经纬,刘昌文,胡德勇.秦山核电二期工程反应堆超温△T和超功率△T保护定值设计[J].核动力工程,2003,24(z1):20-23. 被引量:9
  • 2沈元隆.信号与系统[M].北京:人民邮电出版社,2000..
  • 3Westinghouse. Bases of digital overpower and over-temperature delta-T (OPAT/OTAT) reactor trips[R]. Westinghouse Electric Company LLC, Pittsburgh, PA, 2011.
  • 4Westinghouse. Westinghouse AP1000 design control document[R]. Westinghouse Electric Company LLC, Pittsburgh, PA, 2011.
  • 5Mitsubishi Heavy Industries. Over temperature AT and over power AT reactor trip functions and setpoint determination Process[R]. Tokyo, 2012.
  • 6BTP 7-21, Guidance on digital computer real-time performance[S]. Rock Ville: NRC, 2007.
  • 7IEEE standard for criteria for the periodic surveillance testing of nuclear power generating station safety systems[R]. IEEE Std 338, 2012.
  • 8中华人民共和国国家质量监督检验检疫总局.GB/T5204,核电厂安全系统定期试验与监测[S],2008.
  • 9林诚格,郁祖盛.非能动安全先进压水堆核电技术[M].北京:原子能出版社,2008:150-176.
  • 10郑伟智,李相建,朱毅明.核电站数字化反应堆保护系统停堆响应时间分析[J].自动化博览,2010,27(8):74-76. 被引量:19

共引文献6

同被引文献3

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部