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Application of RELAP/SCDAPSIM and COCOSYS Codes for Severe Accident Analysis in RBMK-1500 Reactor

机译:RBMK-1500反应器中REAP / SCDAPSIM和COCOSIC和COCOSYS码在严重事故分析中的应用

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Regardless low probability of occurrence the severe accident phenomena are investigated for all types of nuclear reactors in the world because the consequences of such accident could be catastrophic. Most of research is performed for the prevailing vessel-type light water reactors like PWRs and BWRs. Less research is performed for the channel-type reactors like CANDUs and RBMKs as they are operated just in a few countries. Up to now the phenomena that could occur in case of a severe accident in RBMK reactors were not analysed in detail and little literature is available on this topic. The paper presents one of the first integrated analyses of severe accident in RBMK-1500 reactor. RELAP/SCDAPSIM code is used to simulate the phenomena in the reactor core and reactor cooling system and COCOSYS code is used to simulate the confinement phenomena during the same accident scenario. The performed analysis provided information regarding code acceptability for the severe accident analysis in RBMK reactor and assessment of the timing of the key events, i.e. core uncovery, fuel cladding rupture, etc, and provided assessment regarding hydrogen distribution in confinement.
机译:无论出现的概率低概率都针对世界上所有类型的核反应堆调查了严重的事故现象,因为此类事故的后果可能是灾难性的。大多数研究是针对PWRS和BWR等主要血管型轻水反应器进行的。对烛台和RBMK等渠道型反应器执行较少的研究,因为它们在几个国家/地区运营。到目前为止,在RBMK反应堆中发生严重事故的情况下可能发生的现象没有详细分析,并且在本主题上有很少的文献。本文介绍了RBMK-1500反应堆中严重事故的第一个综合分析之一。 RETAP / SCDAPSIM代码用于模拟反应堆核心和电抗器冷却系统中的现象,并且Cocosys代码用于在同样的事故情景期间模拟限制现象。所进行的分析关于代码可接受用于RBMK反应器和关键事件的定时的评估,即核心揭盖,燃料包壳破裂等的严重事故分析所提供的信息,以及关于在禁闭氢气分配提供评估。

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