首页> 外文会议>14th International Conference on Nuclear Engineering(ICONE14) vol.5 >THE CORE MELT STABILIZATION CONCEPT OF THE EPR AND ITS EXPERIMENTAL VALIDATION
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THE CORE MELT STABILIZATION CONCEPT OF THE EPR AND ITS EXPERIMENTAL VALIDATION

机译:EPR的核心熔体稳定概念及其实验验证

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The strategy of the European Pressurized Water Reactor (EPR) to avoid severe accident conditions is based on the improved defense-in-depth approaches of the French "N4" and the German "Konvoi" plants. In addition, the EPR takes measures, at the design stage, to drastically limit the consequences of a postulated core-melt accident. The latter requires a strengthening of the confinement function and a significant reduction of the risk of short- and long-term containment failure. Scenarios with potentially high mechanical loads and large early releases like: high-pressure RPV failure, global hydrogen detonation, and energetic steam explosion must be prevented. The remaining low-pressure sequences are mitigated by dedicated measures that include hydrogen recombination, sustained heat removal out of the containment, and the stabilization of the molten core in an ex-vessel core catcher located in a compartment lateral to the pit. The spatial separation protects the core catcher from loads during RPV failure and, vice versa, eliminates concerns related with its unintended flooding during power operation. To make the relocation of the melt into the core catcher scenario-independent and robust against the uncertainties associated with in-vessel molten pool formation and RPV failure, the corium is temporarily retained, accumulated and conditioned in the pit during interaction with a sacrificial concrete layer. Spreading of the accumulated molten pool is initiated by penetrating a concrete plug in the bottom. The increase in surface-to-volume ratio achieved by the spreading process strongly enhances quenching and cool-down of the melt after flooding. The required water is passively drained from the IRWST. After availability of the containment heat removal system the steam from the boiling pool is re-condensed by sprays. The CHRS can also optionally cool the core catcher directly, which, in consequence, establishes a sub-cooled pool near-atmospheric pressure levels in the containment. The described concept rests on a large experimental knowledge base which covers all main phenomena involved, including melt interaction with structural material, melt spreading, melt and quenching, as well as the efficacy of the core catcher cooling. Besides giving an overview of the EPR core melt mitigation concept, the paper summarizes its R&D bases and describes which conclusions have been drawn from the various experimental projects and how these conclusions are used in the validation of the EPR concept.
机译:欧洲压水堆(EPR)避免严重事故情况的策略是基于法国“ N4”工厂和德国“ Konvoi”工厂改进的纵深防御方法。另外,EPR在设计阶段就采取措施,以极大地限制假定的芯熔事故的后果。后者需要加强约束功能,并大大降低短期和长期安全壳失效的风险。必须避免可能具有较高机械负荷和大量早期释放的场景,例如:高压RPV失效,全局氢爆轰和高能蒸汽爆炸。其余的低压序列可通过专用措施来缓解,这些措施包括氢重组,持续将热量排出安全壳,以及使熔融核稳定在位于坑侧面的隔室中的前容器堆芯捕集器中。空间隔离可防止RPV发生故障时核心捕集器受到负载,反之亦然,消除了与电源运行期间意外溢出有关的担忧。为了使熔体重新定位到堆芯捕集器中,与场景无关,并且能够抵抗与容器内熔池形成和RPV失败相关的不确定性,在与牺牲混凝土层相互作用的过程中,将皮质暂时保留,积累和调节在坑中。累积的熔池的扩散是通过在底部穿透混凝土塞而开始的。通过铺展过程实现的表面体积比的增加极大地增强了注水后熔体的淬火和冷却。所需的水从IRWST被动排放。在安全壳除热系统可用后,沸腾池中的蒸汽通过喷雾重新冷凝。 CHRS还可以选择直接冷却岩心捕集器,从而在安全壳中建立接近大气压的过冷池。所描述的概念基于庞大的实验知识基础,涵盖了所有涉及的主要现象,包括与结构材料的熔体相互作用,熔体散布,熔体和淬火以及堆芯捕集器冷却的功效。除了概述了EPR堆芯减缓概念之外,本文还总结了其研发基础,并描述了从各种实验项目中得出的结论以及这些结论如何用于EPR概念的验证。

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