Design & development of microcontroller based programmable ramp generator for AC-DC converter for simulating decay power transient in experimental facility for nuclear power plants

G. Srivastava, R. D. Kulkarni
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引用次数: 7

Abstract

In nuclear power plants, fuel is subjected to a wide range of power and temperature transients during normal and abnormal conditions. The reactor setback and step-back power pattern, fast temperature profile occurred during Loss of Coolant Accident and decay power followed by shutdown of power plant are the typical transients in nuclear power plant. For a variety of reactor engineering and reactor safety related study, one needs to simulate these transients in experimental facility. In experimental facilities, high response AC-DC converters are used to handle these power and temperature transients safely in a controlled manner for generating a database which is utilized for design of thermal hydraulic system, development of computer codes, study of reliability of reactor safety system, etc. for nuclear power plants. The paper presents the methodology developed for simulating the typical reactor decay power transient in an experimental facility. The design and simulation of AC-DC power electronic converter of 3 MW capacity is also presented. The microcontroller based programmable ramp generator is designed & hardware implemented for feeding reference voltage to the closed loop control system of AC-DC converter for obtaining the decay power profile at the converter output. The typical decay power transient of the nuclear power plant is divided into several small power ramps for simulating the transient. The signal corresponding to each power ramp is generated by programmable ramp generator and fed to the comparator for generating control signal for the converter. The actual decay power transient obtained from the converter is compared with the theoretical decay power transient.
基于单片机的可编程斜坡发电机的设计与开发,用于模拟核电站实验装置中衰减功率暂态的交直流变换器
在核电站中,燃料在正常和异常情况下都要经受大范围的功率和温度瞬变。反应堆的回退功率模式、失冷过程中出现的快速温度分布以及核电站停堆后的衰减功率是核电站中典型的瞬态。在各种反应堆工程和反应堆安全相关的研究中,需要在实验设施中模拟这些瞬变。在实验设施中,采用高响应交直流变流器对这些功率和温度暂态进行可控的安全处理,生成数据库,用于核电站热液压系统设计、计算机代码编写、反应堆安全系统可靠性研究等。本文介绍了在实验装置中模拟典型反应堆衰变功率暂态的方法。介绍了容量为3mw的交直流电力电子变换器的设计与仿真。设计并硬件实现了基于单片机的可编程斜坡发生器,为交直流变换器闭环控制系统提供参考电压,从而获得变换器输出端的衰减功率曲线。将典型的核电站衰变功率暂态划分为几个小功率斜坡进行暂态模拟。每个功率坡道对应的信号由可编程坡道发生器产生,并提供给比较器产生用于转换器的控制信号。将变换器得到的实际衰减功率暂态与理论衰减功率暂态进行了比较。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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