次临界能源堆安全性研究

Study on Safety of Sub-critical Nuclear Power Reactor

次临界能源堆由中心的托卡马克装置和围绕其的裂变包层组成。本文根据物理和热工专业分析计算得出的一种针对其裂变包层的燃料和冷却剂通道布置方式,分析设计的包层结构安全性和工程应用中的安全性。包层结构安全性分析使用CFD方法,计算了正常运行工况和冷却剂通道堵管的情况,得到堵管发生后包层的局部状况。通过RELAP程序模拟了裂变包层参与核电厂发电运行过程中,其本身所具有的固有安全性。本文通过计算发现了其安全上的薄弱环节,并提出了改进措施,为以后改进次临界能源堆安全性提供参考。

The sub‐critical nuclear power reactor is composed by the Tokamak device in the center and the fission blanket surrounding it .A design layout of the fuel and coolant channel of the fission blanket was offered in the paper ,in which the safety analysis was done .The CFD code was used for the thermal‐hydraulic design and safety analysis of coolant channel blocked accident . The RELAP code was used to simulate the fission blanket of the sub‐critical nuclear power reactor , and the inherent safety of it was researched .By the analysis ,some safety weak points were found and related sugges‐tions were provided for the future safety improvement of the sub‐critical nuclear power reactor .