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作 者:黄哲 梁铁波[2] 杨雯[2] 卢川[2] 李洋 何中海 沈昕[1] Huang Zhe;Liang Tiebo;Yang Wen;Lu Chuan;Li Yang;He Zhonghai;Shen Xin(School of Mechanical Engineering,Shanghai Jiao Tong University,Shanghai,200240,China;Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
机构地区:[1]上海交通大学机械与动力工程学院,上海200240 [2]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
出 处:《核动力工程》2024年第2期103-109,共7页Nuclear Power Engineering
摘 要:铅铋快堆的安全稳定运行与换热器一二次侧间的散热性能密切相关。本研究通过建立基于铅铋快堆的直流蒸汽发生器(OTSG)稳态与瞬态耦合分布参数模型,分析对比了不同负荷条件下OTSG内部热工水力特性的分布差异,并进一步揭示了铅铋快堆一次侧焓值及流量扰动对换热器动态散热性能的影响。结果表明:稳态传热时铅铋快堆一次侧温降主要集中在过冷沸腾及核态沸腾区,二次侧负荷减小将导致管壁面温度飞升前移;动态调节显示在设计工况下一次侧入口焓值仅下降5%,就可能导致铅铋快堆循环在90 s后进入事故工况。研究结果为铅铋快堆的OTSG动态流动换热特性研究及结构设计优化提供了有价值的建议。The safe and stable operation of lead bismuth fast reactor is closely related to the heat dissipation performance between the primary and secondary sides of the heat exchanger.In this study,the steady-state and transient coupled distribution parameter model of once-through steam generator(OTSG)based on lead bismuth fast reactor is established.The distribution difference of thermal and hydraulic characteristics in OTSG under different load conditions is analyzed and compared,and the influence of primary enthalpy and flow disturbance of lead bismuth fast reactor on the dynamic heat dissipation performance of heat exchanger is further revealed.The steady-state results show that the temperature drop on the primary side of the lead bismuth fast reactor was mainly concentrated in the subcooled boiling and nucleate boiling regions,and the decrease in the secondary side load can cause the temperature jump on the tube wall.The dynamic results show that the primary side inlet enthalpy only decreases by 5% under design conditions,which may lead to the lead bismuth reactor cycle entering accident conditions after 90 seconds.The relevant results provide valuable suggestions for the study of OTSG flow and heat transfer characteristics and structural design optimization of the lead bismuth fast reactor.
关 键 词:铅铋快堆 直流蒸汽发生器 热工水力分析 分布参数模型
分 类 号:TL334[核科学技术—核技术及应用]
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