池式钠冷快堆事故余热排出系统一回路仿真研究

发布时间：2018-06-13 11:31

本文选题：余热排出系统 + 自然循环　；参考：《原子能科学技术》2015年05期

【摘要】：池式钠冷快堆事故余热排出系统采用了非能动工作原理,依靠液态钠及空气的自然对流排出堆芯余热。为研究事故工况下余热排出系统一回路的换热能力,基于FORTRAN语言,建立堆芯单通道及盒间流模型,采用全隐二阶迎风差分格式及改进的欧拉法离散求解,对事故余热排出系统一回路系统进行数值模拟,并对全厂断电事故进行仿真计算验证。结果表明:该程序能较好地反映事故余热排出系统瞬态变化过程,并可达到超实时仿真。
[Abstract]:The reactor core residual heat is discharged by natural convection of liquid sodium and air. In order to study the heat transfer capacity of the residual heat discharge system under accident conditions, based on FORTRAN language, the single-channel and inter-box flow models of reactor core are established, and the fully hidden second-order upwind difference scheme and the improved Euler method are used to solve the problem. The primary circuit system of the accident residual heat discharge system is numerically simulated, and the power failure accident of the whole plant is simulated and verified. The results show that the program can well reflect the transient process of the accident residual heat discharge system, and can achieve super real time simulation.
【作者单位】：哈尔滨工程大学核安全与仿真技术国防重点学科实验室;
【基金】：国家自然科学基金资助项目(51476040,11105034) 核能开发项目资助第46批教育部留学回国人员科研启动基金资助项目
【分类号】：TL433;TL364.4

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