核动力工程2024,Vol.45Issue(1) :237-245.DOI:10.13832/j.jnpe.2024.01.0237

热管堆耦合开式布雷顿循环系统运行特性研究

Research on Operation Characteristics of Heat Pipe Reactor Coupled with Open-Air Brayton Cycle

刘玖松 刘承敏 易经纬 李毅 李思广
核动力工程2024,Vol.45Issue(1) :237-245.DOI:10.13832/j.jnpe.2024.01.0237

热管堆耦合开式布雷顿循环系统运行特性研究

Research on Operation Characteristics of Heat Pipe Reactor Coupled with Open-Air Brayton Cycle

刘玖松 1刘承敏 1易经纬 1李毅 1李思广1
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作者信息

  • 1. 中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213
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摘要

为探究热管堆与开式布雷顿循环耦合的核电转换系统在堆芯功率和负荷变化时的运行特性,基于Modelica语言建立系统仿真模型,包括堆芯模型、热管传热模型和布雷顿循环模型,并验证了各模型的准确性.采用建立的模型对甩负荷工况和升、降功率过程进行了瞬态仿真和计算.计算结果表明,在瞬态过程中,负荷或堆芯功率的变化将导致转速的改变,需通过旁通调节阀控制涡轮流量使转速恢复稳定.在甩负荷工况中,甩负荷导致堆芯温度下降,反应性反馈将导致堆芯功率升高2.3%、燃料最高温度升高1.7 K.在升、降功率过程中,反应性反馈导致的归一化堆芯功率峰值分别为102.6%和100.7%.本文研究结果可为热管堆与开式布雷顿循环耦合带来的安全风险及其安全分析提供参考.

Abstract

In order to explore the operation characteristics of nuclear power conversion system with open-air Brayton cycle coupled with heat pipe reactor when the core power and load change,the system simulation model is established based on Modelica language,including the sub-models of the reactor core,the heat pipe and the Brayton cycle,and the accuracy of each model is verified.The transient simulation and analysis of loss of load(LOL)and power increment and reduction processes are carried out by using the established model.The calculation results show that in the transient process,the change of load or core power will lead to the change of rotating speed,and it is necessary to control the turbine flow through the bypass control valve to restore the rotating speed to stability.Under LOL condition,the core temperature will drop,and the reactivity feedback will increase the core power by 2.3%and the maximum fuel temperature by 1.7 K.During the reactor power increment and reduction,the peak normalized core power caused by reactivity feedback is 102.6%and 100.7%respectively.The results of this paper provide a reference for the safety analysis of the heat pipe reactor coupled with open-air Brayton cycle.

关键词

热管堆/开式布雷顿循环/Modelica/运行特性

Key words

Heat pipe reactor/Open-air Brayton cycle/Modelica/Operation characteristics

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基金项目

四川省科技计划(2022JDRC0026)

出版年

2024
核动力工程
中国核动力研究设计院

核动力工程

CSTPCDCSCD北大核心
影响因子:0.3
ISSN:0258-0926
参考文献量23
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