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Analysis of Kuosheng Station Blackout accident using MELCOR 1.8.4

机译:使用MELCOR 1.8.4分析国盛站停电事故

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摘要

The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs). A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release functions associated with the SBO accident were simulated. The predicted results are plausible and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future. References: 10
机译:由桑迪亚国家实验室开发的MELCOR代码是一个完全集成的、运行速度相对快的代码,用于模拟商业轻水核电站(NPP)中严重事故的进展。使用 MELCOR 1.8.4 代码模拟了 Kuosheng (BWR-6) NPP 的特定站停电 (SBO) 事故。国盛核电站的MELCOR输入平台是根据国盛核电站设计数据和MELCOR用户指南建立的。初始稳态条件是用开发的自初始化算法生成的。模拟了与SBO事故相关的主要严重事故现象和裂变产物释放函数。根据目前对严重事故现象的理解,预测的结果是合理的,并且符合预期。简要讨论了该分析的不确定性 描述了 MELCOR 1.8.4 的重要特性。估算结果为国盛核电站的概率风险评估(PRA)提供了有用的信息。该工具将在不久的将来应用于国盛核电厂的PRA、严重事故分析和严重事故管理研究。[参考文献: 10]

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