Investigation on Post Accident Heat Removal From Partial Core Relocation in Lower Plenum After CDA in SFRs: 3-D CFD Analysis

Vidhyasagar Jhade, A. Sharma, N. Kasinathan
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Abstract

In the present article, authors have carried out a three-dimensional (3D) Computational Fluid Dynamics (CFD) analysis of turbulent natural convection heat transfer from relocated core debris, in typical Sodium cooled Fast Reactors (SFRs), following a Core Disruptive Accident (CDA). Full-Scale analysis of complete sodium pool, i.e., hot and cold pool including immersed decay heat exchanger, has been carried out. k–ω SST model is used for turbulence closure. The model is selected based on the validation exercise. Core catcher (CC) with multiple passive jets over the Heat Shield Plate (HSP) is considered for analysis. Earlier CFD analysis with the assumption of whole core relocation on CC gave a CC temperature higher than the allowable limit. Hence, in this study, the analysis of partial relocation of the core debris on the CC has been carried out. From this, the maximum extent of relocatable core debris on the CC, which conforms with the allowable criteria, has been observed. Therefore, we have investigated the cases where the percentage of core debris relocation varies from 30–100% on HSP and remaining in the original position. This configuration may influence the decay heat removal via the hot pool. Time-dependent decay heat sources are used. Isotherms and streamlines have been presented to understand heat transfer characteristics. It has been found that with the implementation of multi jets CC, debris settled on HSP does not cross the threshold sodium boiling (∼1200 K) temperature up to 70% debris relocated to HSP with single tray configuration. Heat source surface, which remains at the core and in direct contact with coolant (liquid sodium), reaches a maximum value ∼1031 K for the case where the two-third core is intact at the core region. For HSP, it has been found that the thermal design limit exceeds (∼923 K) when 50% of debris relocates to the lower plenum. The transient study shows that time to attain maximum temperature by debris and HSP is inversely proportional to the percentage of intact core.
SFRs CDA后下静压室部分堆芯重新安置事故后放热研究:三维CFD分析
在本文中,作者进行了三维(3D)计算流体动力学(CFD)分析,在典型的钠冷快堆(SFRs)中,在堆芯破坏事故(CDA)之后,从重新安置的堆芯碎片中产生的湍流自然对流传热。对含浸没式衰变换热器的全钠池即冷热池进行了全尺寸分析。湍流闭合采用k -ω海表温度模型。模型是根据验证练习选择的。考虑了在热屏蔽板(HSP)上具有多个被动射流的堆芯捕集器(CC)。先前的CFD分析假设整个堆芯在CC上重新定位,得出的CC温度高于允许的极限。因此,在本研究中,进行了岩心碎屑在CC上的部分迁移分析。由此,观察到CC上可重定位岩心碎片的最大范围,符合允许准则。因此,我们研究了岩心碎片在HSP上迁移的百分比在30-100%之间变化并保持在原始位置的情况。这种结构可能会影响通过热池的衰减散热。采用了时变衰变热源。采用等温线和流线来理解传热特性。研究发现,随着多射流CC的实施,沉淀在HSP上的碎片不会超过阈值钠沸腾(~ 1200 K)温度,高达70%的碎片重新安置到单托盘配置的HSP上。热源表面,留在堆芯并直接与冷却剂(液态钠)接触,在堆芯区域三分之二的堆芯完好无损的情况下,达到最大值~ 1031 K。对于HSP,已经发现当50%的碎片迁移到下充气室内时,热设计极限超过(~ 923 K)。瞬态研究表明,岩屑和热热液达到最高温度的时间与岩心完整率成反比。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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