反应堆压力容器在典型事故工况下的结构完整性评估

Structural Integrity Assessment for RPV under Typical Event Transients

以反应堆压力容器(RPV)堆芯带区和入口接管为研究对象,建立断裂力学有限元分析模型,以典型事故瞬态的详细热工水力分析结果作为输入条件,对其进行瞬态温度场分析和应力分析。结合RPV辐照脆化计算结果,采用确定性断裂力学分析方法,对RPV在4种典型瞬态下的结构完整性进行了分析评估。分析结果表明,40年寿期内,关注区域不会发生脆性断裂失效,但要关注冷却剂温度变化速率大的瞬态。

The beltline region and inlet nozzle of the reactor pressure vessel （RPV） is investigated in this paper. Fracture mechanics,finite element model is built, the transient temperature filed and stress filed are analyzed using the detailed thermal engineering analysis result of typical event transients as the input conditions. Combining with the irradiation embrittlement assessment result, the structure integrity of RPV under events is analyzed and assessed adopting the analysis method for the deterministic fracture mechanics. The analysis result shows that brittle rupture would not happen in the interesting region of RPV during the life time of forty years, but attention should be paid to the transients with great changing rate of coolant temperature.