基于无人潜航器中的热管冷却反应堆安全分析研究

A Study on Safety Analysis of Heat Pipe Cooled Reactor Based on Unmanned Underwater Vehicle

以一种无人潜航器中搭载的紧凑型热管冷却反应堆为基础,建立并优化了一套完整的热管冷却反应堆安全分析模型,其中主要包含堆芯功率瞬变模型、高温热管冷态启动模型与二维热管网格模型,针对研究对象设计了事故工况下的非能动余热排出系统。基于上述模型,开发了热管冷却反应堆安全分析程序,并采用文献公开的冷态启动、稳定运行的实验数据与安全分析程序计算数据进行了对比验证。验证结果表明,程序计算结果与实验数据符合较好,证明了程序的准确性与预测结果的可靠性。使用程序针对研究对象进行了典型事故分析,计算得到了热阱丧失事故下,反应堆在事故发生后延迟3 s停堆与延迟6 s投入余热排出系统条件下峰值温度为1085 K,低于热管最高运行温度;计算得到了引入阶跃正反应性0.47$与线性引入反应性±0.05$下热管冷却反应堆温度的瞬态响应,最高温度低于热管最高运行温度,且在反馈调节作用下反应堆在更高功率水平下达到新的稳态,体现了反应堆设计方案的良好固有安全性。

Based on a compact heat pipe-cooled reactor carried by an unmanned underwater vehicle,a complete safety analysis model of heat pipe cooled reactor is established and optimized in this paper,which mainly includes core power transient model,cold start-up model of high temperature heat pipe and two-dimensional heat pipe grid model.The passive residual heat removal system under accident condition is also designed.A heat pipe-cooled reactor safety analysis program was developed based on the established model,and the program's calculated results were compared and verified with published experimental data of cold start-up and stable operation.The verification results showed good agreement between the program's calculated results and experimental data,demonstrating the accuracy of the program and the reliability of the predicted results.The typical accident of the research object was analyzed by using the program,and the highest temperature was calculated to be 1085K under the heat sink loss accident condition,with a delay of reactor shutdown for 3s and a delay in putting residual heat removal system into operation for 6s,and it's below the maximum operating temperature of the heat pipe.The transient response of the reactor temperature with a step-in positive reactivity insertion of 0.47$ and a linear reactivity insertion of ±0.05$ was also calculated,and the highest temperature was below the maximum operating temperature of the heat pipe.Under feedback regulation,the reactor reached a new steady state at a higher power level,demonstrating the good inherent safety of the reactor design scheme.