小型铅铋冷却快堆瞬态安全分析

Transient Safety Analysis of Small Leaded-Bismuth Cooled Fast Reactor

本文基于多通道热工模型与功率计算模型,在快堆分析程序SARAX的基础上开发了可用于分析小型铅铋冷却快堆在无保护超功率事故、无保护失流事故及无保护失热阱事故发生时瞬态安全特性的计算功能,并利用该程序计算了在不同事故情况下,堆芯反应性、功率以及热工参数随时间的变化,分析评价了堆芯的中子学和热工水力学性能。结果表明所设计的堆芯在发生事故时具有固有安全特性。

Based on the multi-channel thermal model and the power model,the calculation code which could be used in the transient safety analysis of fast reactor was developed in unprotected overpower accident,unprotected loss of flow accident and unprotected loss of hot sink accident in the paper.By this code,the core reactivity,power and thermal parameter changes with time in different accident cases were calculated and the core neutronics and thermal-hydraulics performance was analyzed.The results indicate that the core design has safety features when accident happens.