【摘要】 Kilopower是NASA(National Aeronautics and Space Administration)提出的空间小型裂变反应堆项目。其测试堆KRUSTY(Kilowatt Reactor Using Stirling TechnologY)已于2018年3月完成了测试，并得到了启堆、稳定功率运行及反应性调整、负荷跟踪瞬态、容错瞬态、反应性控制瞬态、主动散热丧失等实验数据。为了进一步增强针对热管堆瞬态运行的预测能力，评估事故工况下热管堆的行为与安全性能，需要开发热管堆系统分析工具。本文基于多物理场软件Simscape，通过扩展其相关功能，使其具备对热管堆进行系统分析的能力。以KRUSTY为目标，搭建模型并进行模拟分析，将计算获得的功率与温度曲线同实验数据进行对比。结果表明：各个工况的功率平均误差均小于10%；在初始运行阶段，温度误差在10%左右，其余阶段，温度误差小于3%。该结果在一定程度上证明了该研究方法的可行性，为将来深入进行热管堆安全分析工作奠定了基础。更多还原

【Abstract】 [Background] The Kilopower Project is initiated by NASA(National Aeronautics and Space Administration) to demonstrate reactor of small space fission power. KRUSTY(Kilowatt Reactor Using Stirling TechnologY), as a prototypic nuclear-powered test of a 5-kWt kilopower space reactor, is successfully operated in March of 2018. The testing, which operated the reactor at various temperatures and power levels, shows that the reactor is highly tolerant of possible failure conditions and transients. [Purpose] This study aims to further enhance the prediction ability for the transient operation of heat pipe cooled reactor(HPCR) and evaluate the behavior and safety performance of heat pipe cooled reactor under accident conditions. [Methods] Firstly, a multi-domain onedimensional multiphysical field tool of MATLAB/Simulink platform named Simscape was introduced as the modelling environment. Then, related functions was extended to include point reactor module and heat transfer module for heat pipes, making Simscape preserving the ability to systematically analyze the heat pipe cooled reactor. Subsequently, taking KRUSTY as the target, the model was built and the key processes were simulated. Finally, the calculation results, including normal operation and accident conditions, were compared with the experimental data. [Results] The comparison results show that the average power error of each working condition is less than 10%. The temperature error is about 10% in the initial operation stage, but drops to less than 3% in thereafter stages. [Conclusions] The calculated results in this study are in good agreement with experimental data, proving the feasibility of the research method to a certain extent, hence lay a foundation for further safety analysis of heat pipe cooled reactor in the future.更多还原