超临界二氧化碳核能系统负荷运行策略研究  

Study on Load Operation Strategy for Supercritical Carbon Dioxide Nuclear Power System

作　　者：薛琪 冯民 马云铎 吴攀[1] 单建强[1] 黄彦平[2] XUE Qi;FENG Min;MA Yunduo;WU Pan;SHAN Jianqiang;HUANG Yanping(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu 610041,China)

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610041

出　　处：《西安交通大学学报》2023年第5期136-148,共13页Journal of Xi'an Jiaotong University

基　　金：国家自然科学基金资助项目(12175172);中国核工业集团有限公司领创科研项目。

摘　　要：为了确保超临界二氧化碳再压缩布雷顿循环直接冷却核能系统在变负荷工况下的安全经济运行,利用稳态和瞬态回热器换热实验验证了自主研发的瞬态分析程序SCTRAN/CO_(2)在预测布雷顿循环动态特性方面的可行性,并以该程序作为分析工具,开展了超临界二氧化碳再压缩布雷顿循环核能系统分别在反应堆反应性扰动和二次侧冷却水流量扰动两种典型瞬态工况下的开环动态特性研究,开发了主压缩机入口温度恒定、堆芯出口温度恒定及改变循环工质装量的负荷运行策略,研究了系统在100%~50%~100%变负荷工况下的瞬态响应。结果表明,装量控制策略能实现以额定满功率5%/min的速率追踪负荷,并保证系统安全经济运行。此过程中,堆芯压力波动0.6 MPa,堆芯出口温度波动不超过5℃。研究获得的瞬态分析工具、开环特性和控制策略为此核能系统的负荷运行策略研究提供了参考。This paper studies a self-developed transient analysis code SCTRAN/CO_(2)to ensure the safe and economical operation of supercritical CO_(2)directly-cooled nuclear energy system based on the recompression Brayton cycle under variable load conditions.Steady-state and transient recuperator experiments are modeled to prove the feasibility of the code in predicting the characteristics of the Brayton cycle.The code is used as an analysis tool to study the open-loop dynamic characteristics of the supercritical CO_(2)nuclear energy system based on the recompression Brayton cycle under two typical transient conditions:reactor reactivity disturbance and secondary loop cooling water mass flow disturbance.A load operation strategy is developed based on constant main compressor inlet temperature,constant core outlet temperature and varying inventory of working fluid.A study is conducted on the transient response of the system under variable load conditions of 100%—50%—100%.The results show that the inventory control strategy can track the load at a rate of 5%of full power per minute and ensure the safe and economical operation of the system.During this process,the core pressure fluctuated by 0.6 MPa and the core outlet temperature fluctuated by no more than 5℃.The transient analysis tool,open-loop dynamic characteristics and control strategies presented in this paper provide a reference for the development of load operation strategies for such nuclear power systems.

关 键 词：超临界二氧化碳直接冷却反应堆 再压缩布雷顿循环 动态特性 负荷运行策略 

分 类 号：TL333[核科学技术—核技术及应用]