基于热管堆的超临界二氧化碳核动力系统参数设计与优化研究

戴春辉, 郭斯茂, 宋苹, 赵振兴, 柯志武

工程热物理学报 ›› 2024, Vol. 45 ›› Issue (4) : 1069-1075.

PDF(2284 KB)
PDF(2284 KB)
工程热物理学报 ›› 2024, Vol. 45 ›› Issue (4) : 1069-1075.

基于热管堆的超临界二氧化碳核动力系统参数设计与优化研究

  • 戴春辉1,2, 郭斯茂3, 宋苹1, 赵振兴1, 柯志武1
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Research on the Design and Optimization of the Supercritical Carbon Dioxide Nuclear Power System Based on Heat Pipe Reactor

  • DAI Chunhui1,2, GUO Simao3, SONG Ping1, ZHAO Zhenxing1, KE Zhiwu1
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摘要

为获得超临界二氧化碳动力系统最优设计参数,本文建立了热力分析模型和主要设备模型,开展热管式反应堆为热源、简单回热架构的超临界二氧化碳发电装置系统参数性能分析和多目标参数优化设计。形成1 MW(e) 输出功率的发电装置系统参数最优解集,并开展系统敏感性分析。研究结果表明提升系统参数可达到提升系统循环效率的目的,但同时也增加了设备尺寸规模,对提升紧凑性不利,各主要热力参数对系统效率和体积的敏感性相差较大。最终优化解的选择可从本文最优解集中,按可布置空间大小选取,从而获得兼顾效率和紧凑性的最优设计参数。

Abstract

In order to obtain the optimum design parameters of the supercritical carbon dioxide power system, this paper establishes a thermal analysis model of system and main equipment. parameter performance analysis and multi-objective optimization design of the supercritical carbon dioxide power generation device system with a heat pipe reactor is carried out. We develop an optimal solution set of power generation device system parameters with an output power of 1 MW(e), and conduct system sensitivity analysis. The research results indicate that increasing system parameters can achieve the goal of improving system cycle efficiency, but it also increases the size and scale of the equipment, which is unfavorable for improving compactness. The sensitivity of various main thermal parameters to system efficiency and volume varies greatly. The final optimization solution can be selected from the optimum solutions set in this article, based on the size of the available space, in order to obtain the optimum design parameters with better efficiency and compactness.

关键词

热管堆 / 超临界二氧化碳 / 系统热力参数。

Key words

heat pipe reactor / supercritical carbon dioxide / thermal parameters of system

引用本文

导出引用
戴春辉, 郭斯茂, 宋苹, 赵振兴, 柯志武. 基于热管堆的超临界二氧化碳核动力系统参数设计与优化研究[J]. 工程热物理学报, 2024, 45(4): 1069-1075
DAI Chunhui, GUO Simao, SONG Ping, ZHAO Zhenxing, KE Zhiwu. Research on the Design and Optimization of the Supercritical Carbon Dioxide Nuclear Power System Based on Heat Pipe Reactor[J]. Journal of Engineering Thermophysics, 2024, 45(4): 1069-1075

基金

国家重点研发计划(No.2019YFB1901200)
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