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首页> 外文期刊>Nuclear Engineering and Design >A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor
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A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor

机译:MELCOR节点化用于模拟沸水堆船内严重事故进程的敏感性研究

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摘要

This paper presents a sensitivity study of MELCOR nodalization for simulation of postulated severe accidents in a Nordic boiling water reactor, with the objective to address the nodal effect on in-vessel accident progression, including thermal-hydraulic response, core degradation and relocation, hydrogen generation, source term release, melt behavior and heat transfer in the lower head, etc. For this purpose, three meshing schemes (coarse, medium and fine) of the COR package of MELCOR are chosen to analyze two severe accident scenarios: station blackout (SBO) accident and large break loss-of-coolant accident (LOCA) combined with station blackout. The comparative results of the MELCOR simulations show that the meshing schemes mainly affect the core degradation and relocation to the lower head of the reactor pressure vessel: the fine mesh leads to a delayed leveling process of a heap-like debris bed in the lower head, and a later breach of the vessel. The simulations with fine mesh also provide more detailed distributions of corium mass and temperature, as well as heat flux which is an important parameter in qualification assessment of the In-Vessel Melt Retention (IVR) strategy.
机译:本文介绍了MELCOR节点化的敏感性研究,用于模拟北欧沸水反应堆中假定的严重事故,目的是解决节点对船内事故进展的影响,包括热工水力响应,堆芯退化和迁移,氢生成为此,选择了MELCOR COR包的三种啮合方案(粗,中,细),以分析两种严重的事故情况:停电(SBO) )事故和大的冷却液中断损失事故(LOCA)并加油站停电。 MELCOR仿真的比较结果表明,啮合方案主要影响堆芯的降解和重新定位到反应堆压力容器下端的位置:精细的网格会导致下端堆状碎屑床的找平过程延迟,后来又违反了船只具有细网格的模拟还提供了更详细的皮质质量和温度以及热通量分布,热通量是评估船内熔体保持力(IVR)策略的重要参数。

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