摘要
[目的]核动力破冰船具有续航时间长、破冰能力强等优点,可以为我国极地科学考察事业提供保障。针对未来我国核动力破冰船的发展方向,开展船用反应堆非能动安全壳冷却系统(PCCS)换热器特性研究。[方法]利用Fluent软件对关键设备的换热器进行建模,研究不同方案下的流量分布情况。[结果]模拟结果显示:增大传热管束中心管间距可提高流量分配的均匀性;分配联箱与汇流联箱的截面积比取为0.7时,流量分配较均匀。[结论]所做研究可为我国新一代核动力破冰船反应堆的方案设计提供技术参考。
[Objectives]The advanced nuclear icebreaker has the advantages of the long endurance and strong icebreaking ability,which can provide guarantee for China's polar exploration.Aiming at the development direction of future nuclear icebreakers,the study on the characteristics of the heat exchanger for the marine Passive Containment Cooling System(PCCS)was carried out.[Methods]The Fluent software was used to model the heat exchanger of key equipment to study the flow distribution under the different schemes.[Results]The simulation results show that:the uniformity of flow distribution is increased by enlarging the distance between the tube bundles in the heat transfer tubes;when the cross section ratio of the distribution header and the combining header is 0.7,the flow distribution is even.[Conclusions]It provides technical reference for the design of the new generation of nuclear icebreaker reactors.
作者
武光江
刘辰
王畅
郝锐
Wu Guangjiang;Liu Chen;Wang Chang;Hao Rui(Naval Armament Department of PLAN,Beijing 100080,China;China Ship Development and Design Center,Wuhan 430064,China)
出处
《中国舰船研究》
CSCD
北大核心
2019年第S01期28-34,40,共8页
Chinese Journal of Ship Research
基金
国家自然科学基金资助项目(51609227)
关键词
核动力破冰船
非能动安全壳冷却系统
换热器
流量分配
数值模拟
nuclear powered icebreaker
Passive Containment Cooling System(PCCS)
heat exchanger
flow distribution
numerical simulation