基于全范围模拟机对压水堆MSLB叠加SGTR事故分析

Analysis of Pressurized Water Reactor’s MSLB with SGTR Based on Full-scope Simulator

主蒸汽管道断裂事故叠加蒸汽发生器传热管破裂事故属于核电厂超设计基准事故.为研究国内M310系列机组对该种事故的处理能力,采用了以宁德核电厂1号机为原型的全范围模拟机对此次事故进程进行模拟,选择了放射性释放较为恶劣的蒸汽管道破口(MSLB)叠加100根蒸汽发生器传热管破裂(SGTR)事故,并应用了最新的SOP规程中的操纵员动作以缓解事故后果,分析了事故发生后一回路压力、蒸汽发生器压力、堆芯出口温度以及一次侧至二次侧破口流量的变化.分析结果表明了在核电厂自动动作和操纵员有效及时干预下,在一定情况下可以避免进入严重事故中,最终可以处于安全可控状态.

Main Steam Line Break accidentplus Steam Generator Tube Rupture accident is the beyond-design base accident of the nuclear power plant.In order to study the handing ability of domestic M310 units for this kind of accident,full scope simulator that based on Ningde Nuclear Power is adopted to simulate the accident process,accident with severe radioactive release caused by main steam line break (MSLB) overlay 100 steam generator tube rupture is selected,and controller actions stipulated in the latest SOP are applied to mitigate the consequences of the accident.The change of the primary circuit pressure,steam generator pressure,core outlet temperature and the flow rate of first-to-second-side break after the accident were analyzed.The experiment analysis shows that the nuclear power plant can finally be in a safe and controllable state under the effective and timely intervention of the nuclear power plant s automatic actions and controllers.