核动力工程2024,Vol.45Issue(3) :199-205.DOI:10.13832/j.jnpe.2024.03.0199

源量程中子测量反应堆倍增周期算法研究分析及实现

Research Analysis and Implementation of Reactor Doubling Period Algorithm in Source Range Measurement

朱朝阳 常嘉豪 王振涛 邢桂来 李立涛
核动力工程2024,Vol.45Issue(3) :199-205.DOI:10.13832/j.jnpe.2024.03.0199

源量程中子测量反应堆倍增周期算法研究分析及实现

Research Analysis and Implementation of Reactor Doubling Period Algorithm in Source Range Measurement

朱朝阳 1常嘉豪 1王振涛 1邢桂来 1李立涛1
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作者信息

  • 1. 清华大学核能与新能源技术研究院,北京,100084
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摘要

反应堆倍增周期是反应堆控制中重要的监测参数,直接反映反应堆功率水平变化快慢,用于判定反应堆是否处于安全可控状态.反应堆源量程中子测量以脉冲计数率表征中子注量率与功率水平,对应的反应堆倍增周期计算较为复杂.采用数字化技术提出一种基于最小误差的多点拟合倍增周期数字化实时算法,通过现场可编程门阵列(FPGA)具体实现该算法并开展功能与性能测试.测试结果表明:对于反应堆保护阈值±30s内的反应堆倍增周期,采用该算法的FPGA能够输出较准确倍增周期计算结果,作为触发安全保护系统的信号.该反应堆倍增周期算法适用于源量程中子测量系统中堆功率变化的实时监测,以保障启堆阶段的安全可控.

Abstract

The reactor period doubling time is an important monitoring parameter in reactor control,as it directly reflects the rate of change of reactor power level.It is used to determine whether the reactor is in a safe and controllable state.Neutron measurement in reactor source range uses pulse counting rate to characterize neutron fluence rate and power level,and the calculation of corresponding reactor doubling period is complicated.A digital real-time algorithm based on multi-point fitting with minimum error is proposed using digitalization techniques.This algorithm is implemented in field programmable gate array(FPGA)hardware,and functional and performance tests are conducted.The test results show that the FPGA using this algorithm can accurately output the calculated reactor period doubling time within the reactor protection threshold of±3 0s,as the triggering signals for the safety protection system.This reactor period doubling time algorithm is suitable for real-time monitoring of power changes in the source range neutron measurement system,ensuring safety and controllability during startup phase.

关键词

源量程中子测量/反应堆倍增周期/现场可编程门阵列(FPGA)

Key words

Source range neutron measurement/Reactor doubling period/Field programmable gate array(FPGA)

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出版年

2024
核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
参考文献量9
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