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某小型模块化反应堆核电站二回路系统?分析

Exergy analysis for secondary circuit system in a small modular reactor nuclear power plant

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【作者】 王鑫赵钢曲新鹤王捷

【Author】 WANG Xin;ZHAO Gang;QU Xin-he;WANG Jie;Institute of Nuclear and New Energy Technology of Tsinghua University,Collaborative Innovation Center of Advanced Nuclear Energy Technology,the Key Laboratory of Advanced Reactor Engineering and Safety,Ministry of Education;

【机构】 清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室

【摘要】 本文针对某小型模块化反应堆(small modular reactor,SMR)核电站二回路系统,基于热力学第二定律建立了主要设备的?数学模型,采用EBSILON软件完成了系统的精细建模。通过变工况仿真,在多种功率水平下对核电站二回路主要设备进行了?分析,并得到了二回路系统?损分布情况。在100%热耗率验收工况(turbine heat acceptance,THA)下,二回路的总?损失为97.972 MW,发电效率和?效率分别为42.980%和68.383%。二回路主要设备中,蒸汽发生器的?损失最大,占系统总?损失的41.911%;低压缸?损失居第2位,且?效率较低,存在一定的节能潜力;发电机、泵、加热器等组件在系统总?损失中的占比较小。此外,功率水平变化会对设备的?损失、?效率产生影响。

【Abstract】 This paper focuses on the secondary circuit system of a small modular reactor(SMR) nuclear power plant.Based on the second law of thermodynamics, the mathematical models of the main equipment were established, and the system was finely modeled using EBSILON software.Under various power levels,the main equipment of the secondary circuit of the nuclear power plant was analyzed through simulation calculation,and the exergy distribution loss of the secondary circuit system was obtained. Under the 100% turbine heat acceptance(THA) condition,the total exergy loss of the secondary circuit was 97.972 MW,and the power generation efficiency and exergy efficiency were 42.980% and 68.383% respectively.Among the main equipment of the system,the steam generator had the largest exergy loss,accounting for 41.911% of the total exergy loss.The exergy loss of the low-pressure cylinder was the second highest, and the exergy efficiency of the low-pressure cylinder was low,indicating a certain energy-saving potential.However,other components such as the power generator,pump,and heaters constituted a small proportion of the total system loss.Additionally,the power level also influenced the exergy loss and exergy efficiency of the components.

【基金】 国家重点研发计划资助项目(2018YFB1900500);中核集团领创项目
  • 【会议录名称】 中国核科学技术进展报告(第八卷)中国核学会2023年学术年会论文集 第2册 核能动力 同位素分离
  • 【会议名称】中国核学会2023年学术年会
  • 【会议时间】2023-10-17
  • 【会议地点】中国陕西西安
  • 【分类号】TM623
  • 【主办单位】中国核学会
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