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Evaluation of the kinetics of molten pool stratification in case of In-Vessel Melt Retention Strategy

机译:容器内熔体保留策略下熔池分层动力学的评估

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The In-Vessel Retention (IVR) strategy for Light Water Reactors (LWR) intends to stabilize and retain the core melt in the reactor pressure vessel. This type of Severe Accident Management (SAM) strategy has already been incorporated in the SAM guidance (SAMG) of several operating small size LWR (reactors below 500MWe, like VVER440) and is part of the SAMG strategies for some Gen Ⅲ+ PWRs of higher power like the AP1000. One of the main issues for the demonstration of the success of the IVR strategy lies in the evaluation of the transient heat fluxes applied by the corium pool along the vessel wall. Indeed, these transient heat fluxes, during the corium pool stratification evolution, are expected to be higher than the steady-state ones, in particular due to the concentration of the heat flux in the top metal layer when it is thin (so called focusing effect). Another issue appears when a heavy metal is initially formed and rises later to the top (inversion of stratification): in such a situation, the metal goes through the oxide phase and accumulates a significant superheat which is likely to produce a high transient heat flux. Thus, it is of primary importance to be able to evaluate the duration of these transient peaks in order to evaluate the minimal residual vessel thickness after such fast transient ablation and draw conclusions about the vessel integrity. This paper first presents the phenomenology associated to the transient molten pool stratification and the model implemented in the severe accident integral code ASTEC (Accident Source Term Evaluation Code) to evaluate this kinetics. Then, evaluations are presented, based on a typical PWR reactor configuration. A sensitivity study is proposed to consider the impact of the main uncertainties on parameters which govern this kinetics. A particular focus is made on the physical phenomena driving the transient stratification of material layers in the corium pool and on the identification of critical situations with possible consequences in terms of vessel failure. The characteristic times of each individual process (chemistry, stratification, natural convection) are compared. In particular, the limiting cases of very fast chemistry or very slow chemistry are evaluated. This work is performed in the frame of the European H2020 project IVMR (In-Vessel Melt Retention) coordinated by IRSN. This project has been launched in 2015 and gathers 27 organizations with, as main objective, the evaluation of feasibility of IVR strategy for LWR (PWR, VVER, BWR) of total power 1,000M We or higher.
机译:轻水反应堆(LWR)的容器内保留(IVR)策略旨在稳定并保留堆芯熔体在反应堆压力容器中。这种类型的严重事故管理(SAM)策略已被纳入几个运行中的小型轻水堆(低于500MWe的反应堆,如VVER440)的SAM指南(SAMG)中,并且是某些更高版本的Ⅲ+ PWR的SAMG战略的一部分像AP1000一样强大。演示IVR策略成功的主要问题之一是评估沿血管壁的皮质池所施加的瞬态热通量。确实,这些瞬态热通量在钙池分层发展过程中预计要高于稳态热通量,特别是由于顶部金属层薄时热流密度集中(所谓的聚焦效应) )。当最初形成重金属并随后上升到顶部(分层反转)时,会出现另一个问题:在这种情况下,金属会穿过氧化物相并积聚大量过热,这很可能产生高瞬态热通量。因此,最重要的是能够评估这些瞬时峰值的持续时间,以便评估在这种快速瞬时消融之后的最小残留血管厚度并得出关于血管完整性的结论。本文首先介绍了与瞬态熔池分层相关的现象学,以及在严重事故积分代码ASTEC(事故源术语评估代码)中实施的模型,以评估这种动力学。然后,基于典型的PWR反应堆配置提出了评估。建议进行敏感性研究,以考虑主要不确定性对控制该动力学的参数的影响。特别关注驱动皮质池中材料层瞬变分层的物理现象,以及识别可能导致血管衰竭的可能后果的关键情况。比较每个过程(化学,分层,自然对流)的特征时间。特别地,评估了非常快的化学反应或非常慢的化学反应的极限情况。这项工作是在IRSN协调的欧洲H2020项目IVMR(船内熔体滞留)的框架内完成的。该项目于2015年启动,聚集了27个组织,其主要目标是评估总功率1,000M We或更高的LWR(PWR,VVER,BWR)IVR策略的可行性。

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