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Numerical simulation of Post Accident Heat Removal in a typical pool-type SFR under severe core relocation scenario

机译:严重堆芯重载情况下典型池型SFR事故后排热的数值模拟

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Under a hypothetical core meltdown and relocation scenario in Sodium cooled Fast Reactor (SFR), there may be a chance for reactor main vessel failure if the core debris are allowed to settle at the bottom of this vessel. To avoid this, an in-vessel core catcher assembly is installed in pool type SFRs just above the bottom wall of the main vessel. The function of this assembly is to collect, retain and passively cool the core debris by assisting natural convection decay heat removal from these debris. In this work, the passive decay heat removal from the core debris settled on single-tray-type design of core catcher has been numerically simulated under different amounts of core relocation using a validated 2-D axisym-metric CFD model. The maximum temperature experienced by the debris bed, core catcher plate and the welded joint between the core support structure and the main vessel (i.e., triple point) are evaluated in order to estimate the amount of core relocation that can be safely handled by the primary containment system under Post Accident Heat Removal (PAHR) scenario. The numerical study revealed that the single-tray-type design of core catcher can potentially assist the passive cooling even under the settling of debris material with heat generation equivalent to 60% of the full core on the core catcher. In addition to this, the effect of the size of opening created on grid plate during core relocation on Post Accident Heat Removal (PAHR) is studied for different amounts of core relocation. From this numerical study, the thermal capability of single-tray type in-vessel core catcher of SFR is assessed. The predictions are useful in determining the safe thermal margins available under core relocation scenarios and extending the functionality of single-tray-type core catcher for handling Whole Core Meltdown Accident (WCA) scenario in future SFRs. (c) 2017 Elsevier Ltd. All rights reserved.
机译:在钠冷快堆(SFR)的假想堆芯熔化和重定位情况下,如果堆芯碎片被允许沉降在该容器底部,则反应堆主容器可能会发生故障。为避免这种情况,在主容器底壁上方的池型SFR中安装了一个船内岩心捕集器组件。该组件的功能是通过辅助自然对流衰减热量从这些碎屑中清除,从而收集,保留和被动冷却堆芯碎屑。在这项工作中,使用经过验证的二维轴对称CFD模型,在不同数量的堆芯重定位下,对在堆芯捕集器的单托盘型设计上从堆芯碎片中去除的被动衰变热量进行了数值模拟。评估碎屑床,岩心捕集板以及岩心支撑结构与主容器之间的焊接接头(即三点)所经历的最高温度,以便估算可以由初级钻机安全处理的岩心移位量事故后排热(PAHR)方案下的安全壳系统。数值研究表明,即使在碎屑物料沉降的情况下,集热器的单托盘式设计也可以潜在地辅助被动冷却,其热量产生等于集热器上整个芯的60%。除此之外,对于不同数量的堆芯重定位,研究了堆芯重定位期间在格栅板上形成的开口尺寸对事故后热量去除(PAHR)的影响。通过该数值研究,评估了单盘式SFR的船上集热器的热容量。这些预测对于确定堆芯重定位方案下可用的安全热裕度以及扩展单托盘型堆芯捕集器的功能很有用,以便在将来的SFR中处理整个堆芯熔毁事故(WCA)方案。 (c)2017 Elsevier Ltd.保留所有权利。

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