Modeling and Analysis of Nuclear Reactor System Using Supercritical-CO_2 Brayton Cycle

Abstract

超临界二氧化碳(S-CO2)有可能作为循环工质应用于第四代核能系统中的3种快中子反应堆系统和当前常见商用反应堆系统内.使用工程等式求解器(EngInEErIng EQuATIOn SOlVEr,EES)工具,对S-CO2布雷顿循环进行了理论建模和分析.其中,针对系统中的重要部件换热器,进行了较为详细的建模.分析了S-CO2布雷顿循环系统的循环热效率,并与核工业中常用的循环工质进行对比.结果表明,S-CO2作为循环工质在特定的温度下具有较高的热转化效率.同时,针对不同的反应堆类型,对比分析S-CO2布雷顿循环与各种类型反应堆系统耦合时的热力循环效率与特性.结果表明,SCO2作为循环工质材料最适合在气冷快堆与液态金属快堆(钠冷快堆和铅冷快堆)中使用,具有热效率和铀资源利用率高等优势.The supercritical carbon dioxide(S-CO2)is considered as a potential working medium for the commercial nuclear reactor system and three types of Gen IV fast reactors.Engineering equation solver(EES)was introduced to set up a model for SCO2 Brayton cycle,and a detailed modeling for the significant components,such as heat exchanger,turbine and compressor,was carried out.After the analysis of thermal efficiency of the S-CO2 Brayton cycle system,results were compared with common mediums used in current nuclear industry,which shows the S-CO2 using as working medium has the highest thermal efficiency under the specific temperature.Meanwhile,thermal efficiencies and characteristics of the S-CO2 Brayton cycle system,coupling with various types of reactor systems,were analyzed.Preliminary analysis showed that S-CO2,using as cycle working fluid material,was most suitable for the gas-cooled fast reactor and the liquid metal-cooled fast reactor(the sodium-cooled fast reactor and the lead-cooled fast reactor),with the advantage of high thermal efficiency and high utilization of uranium resources.教育部重点实验室开发基金(ARES201402

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