海洋核动力平台堆舱非能动冷却特性研究

发布时间：2018-06-09 23:03

本文选题：堆舱非能动冷却系统 + 不凝结气体　；参考：《原子能科学技术》2017年04期

【摘要】：海洋核动力平台以输出电能和生产淡水为目标,为国家海洋能源战略提供保障。针对严重事故下海洋核动力平台堆舱安全性问题,在其堆舱非能动冷却系统(PCCS)方案的基础上,提出采用三维冷凝换热与一维自然循环流动换热耦合计算的方法,利用Fluent软件并结合UDF编程,建立堆舱含不凝结气体环境的蒸汽冷凝与舱外海水自然循环耦合换热模型,并分析失水事故(LOCA)条件下PCCS的热工水力行为特性。结果表明,PCCS能实现对喷放蒸汽的长期冷却,可有效降低LOCA后的堆舱温度与压力,为保障严重事故后的堆舱安全性提供可行措施。相关分析方法也可为开展海洋核动力平台PCCS分析设计提供指导。
[Abstract]:The marine nuclear power platform aims at generating electricity and producing fresh water, which provides guarantee for the national marine energy strategy. In view of the safety problem of marine nuclear power platform under serious accident, based on its passive cooling system (PCCSS) scheme, a method for calculating the coupling of three-dimensional condensation heat transfer and one-dimensional natural circulation heat transfer is proposed. By using fluent software and UDF programming, a coupled heat transfer model between steam condensation and natural circulation of seawater in reactor tank containing uncondensed gas was established, and the characteristics of thermohydraulic behavior of PCCS under the condition of lost water accident (LOCA) were analyzed. The results show that PCCS can realize the long-term cooling of ejected steam, can effectively reduce the temperature and pressure of the reactor tank after LOCA, and provide feasible measures to ensure the safety of the reactor tank after serious accidents. Correlation analysis method can also provide guidance for PCCS analysis and design of marine nuclear power platform.
【作者单位】：武汉第二船舶设计研究所热能动力技术重点实验室;哈尔滨工程大学核科学与技术学院;
【基金】：国家自然科学基金资助项目(51406138) 湖北省自然科学基金资助项目(2015CFB521)
【分类号】：TL364

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