核电厂反应堆保护系统紧急停堆响应时间分析及测试

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Analysis and Test of Respond Time of Nuclear Power Plant Digital Control System to Reactor Trip

摘要: 简要介绍核电厂反应堆保护系统的结构和紧急停堆工况下的数据处理过程,对反应堆保护系统紧急停堆的响应时间进行理论分析。建立响应时间测试原理,并设计相应的测试装置,完成实际测试工作。对测试所得实验数据进行统计学分析的结果表明,反应堆保护系统紧急停堆响应时间的理论最大值为149.1 ms,实验最大值为144.8 ms;实验响应时间符合均值为120.6 ms,方差为90.1 ms的正态分布。
- 核电厂 /
- 数字化仪表控制系统 /
- 停堆响应时间 /
- 测试装置
Abstract: The paper gives a brief introduction on the structure of nuclear power plant reactor protect system and the data processing link to actuate the reactor trip.Theoretical analysis of the response time of reactor trip processing is conducted.Test philosophy is established and relative test device is designed,and the test work is conducted.The statistical analysis of the experimental data from test work shows that,the experimental maximum data of reactor trip response time is 144.8 ms while the theoretic maximum data is 149.1 ms.The experimental data accords with the normal distribution,of which the average value is 120.6 ms,and the variance is 90.1 ms.
- Nuclear power plant /
- Digital control system /
- Reactor trip response time /
- Test device