百万千瓦级压水堆严重事故后再注水的有效性评价

发布时间：2018-03-11 20:24

本文选题：MELCOR　切入点：严重事故　出处：《原子能科学技术》2015年11期 　论文类型：期刊论文

【摘要】：根据现有的设计资料,使用一体化严重事故分析程序MELCOR1.8.6建立了核电厂一、二回路系统,非能动堆芯冷却系统和安全壳系统的模型,并模拟冷段2英寸(5.08cm)小破口叠加重力注入失效的严重事故发生后,将冷却剂注入堆芯的情形,分析其对严重事故进程的缓解能力。本文选取3个严重事故的不同阶段,将冷却剂分别以小流量(10kg/s)、中流量(50kg/s)和大流量(200kg/s)的速率注入堆芯,通过比较氢气产生量、堆芯放射性产生量及堆芯温度等数据来评估在严重事故不同阶段再注水的可行性。结果表明:在堆芯损伤初期,可认为10kg/s以上的流量足以冷却百万千瓦级事故安全。而当严重事故发展到堆芯开始坍塌阶段,200kg/s的注水流量可认为是基本可行的,而小于此流量的注水应慎重考虑。
[Abstract]:According to the existing design data, the models of nuclear power plant's first and second loop system, inactive core cooling system and containment system are established by using the integrated serious accident analysis program MELCOR1.8.6. After simulating the serious accident of small crack superimposed gravity injection failure, the coolant is injected into the core of the reactor to analyze its ability to mitigate the serious accident process. In this paper, three different stages of serious accident are selected. The coolant was injected into the core at the rate of 10 kg / s of small flow rate, 50 kg / s of medium flow rate and 200 kg / s of large flow rate, respectively. In order to evaluate the feasibility of water injection at different stages of serious accident, the results show that in the early stage of core damage, the feasibility of water injection is evaluated by the data of core radioactive production and core temperature, and the results show that in the early stage of core damage, It can be considered that the flow rate above 10 kg / s is enough to cool the safety of the million kilowatts accident, and when the serious accident develops to the stage of core collapse, the water injection flow of 200 kg / s can be considered as basically feasible, but the water injection less than this flow rate should be carefully considered.
【作者单位】：国核华清(北京)核电技术研发中心有限公司;
【基金】：国家科技重大专项资助项目(2011ZX06004-008)
【分类号】：TL421.1;TL364.4

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