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An assessment of radiological source terms for loss of cooling and coolant accidents of a PWR spent fuel pool

机译:评估损失PWR废燃料池冷却和冷却剂事故的放射源术语

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This paper presents the MELCOR code simulation study regarding how a dedicated severe accident mitigation (SAM) measure the release of radiological FPs to the environment in the spent fuel pool (SFP) of a reference pressurized water reactor (PWR) plant. To draw up relevant insights, a series of accident scenarios have been investigated, taking into account a combination of two initiating events (loss-of-cooling and loss-of-coolant accidents), two SFP operating modes (normal and refueling), and three external water makeup strategies through an external cooling water injection as one of dedicated SAM strategies for a long-term cooling of the SFP. For the analysis, relevant code modeling has been made for a broad spectrum of severe accident-related phenomena being expected during the SFP accidents. As a result, the evolution of relevant physical phenomena has been investigated and discussed in light of the release of FPs, and several points of uncertain issues, which need to address more carefully (a) either when implementing a cross-comparison for different code predictions (such as MELCOR and MAAP) for SFP accident progression or (b) when assessing radiological risk and/or developing dedicated SAM strategies for the SFP of PWR plant, have been drawn up.
机译:本文介绍了关于专用严重事故减缓(SAM)测量放射性FPS在参考加压水反应器(PWR)植物的燃料池(SFP)中的环境中释放的熔体代码仿真研究。为了提高相关见解,已经调查了一系列事故情景,考虑到两种发起事件(冷却丧失和冷却损失的事故)的组合,两个SFP操作模式(正常和加油)和通过外部冷却水注入三个外部水化妆策略作为专用SAM策略,用于SFP的长期冷却。对于分析,已经为在SFP事故期间预期的广泛的严重事故相关现象进行了相关的代码建模。因此,根据FPS的释放和几个不确定问题的释放,研究了相关物理现象的演变,并在实现不同代码预测的交叉比较时需要更仔细地解决(a)的几点(如甜瓜和MAAP)对于SFP事故进展或(b)在评估放射性风险和/或开发PWR植物SFP的专用SAM策略时,已经提出。

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