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Optimal Gap Size for Downward Facing Boiling and Steam Venting in a Hemispherical Annular Channel

机译:半球形环形通道中向下的沸腾和蒸汽排放的最佳间隙尺寸

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摘要

A theoretical model has been developed to predict the behavior of a buoyancy-driven upward co-current two-phase flow in an annular channel with uniform gap size that forms between a hemispherical vessel and its surrounding structure. The vessel is fully submerged in water and is heated from within, leading to downward facing boiling on its outer surface. The problem under consideration is relevant to the so-called in-vessel retention (IVR) of core melt, which is a key severe accident management strategy for some advanced pressurized water reactors (APWRs). One available means for IVR is the method of external reactor vessel cooling by flooding of the reactor cavity with water during a severe accident. Design features of most APWRs have the provision for substantial water accumulation in the reactor cavity during numerous postulated accident sequences. With water covering the lower external surfaces of the reactor pressure vessel, significant energy (i.e., decay heat) could be removed from the core melt through the vessel wall by downward facing boiling on the vessel's outer surface. As boiling of water takes place on the vessel outer surface, the vapor generated on the surface would flow upward through the annular channel under the influence of grav-rnity. The vapor motions would entrain liquid water, thus resulting in a buoyancy-driven upward co-current two-phase flow in the channel. While the flow is induced entirely by the boiling process, the rate of boiling, in turn, can be significantly affected by the resulting two-phase flow. As long as the heat flux from the core melt to the vessel wall does not exceed the critical heat flux limit for downward facing boiling, nucleate boiling is the prevailing regime and-the vessel wall can be maintained at relatively low temperatures to prevent failure of the lower head. With this scenario in mind, the problem is formulated by considering the conservation of mass, momentum, and energy in the two-phase mixture, along with the use of available information on two-phase frictional drop and void fraction. The resulting governing system is solved numerically to predict the total mass flow rate that would be induced in the channel by the boiling process. Based on the numerical results, the optimal gap size that would maximize the steam venting rate and the rate of downward facing boiling over a range of wall heat fluxes is determined. The effects of system pressure and liquid level in the reactor cavity on the induced mass flow rate have also been identified.
机译:已经开发出理论模型来预测浮力驱动的向上并流两相流在环形通道中的行为,该环形通道具有在半球形容器及其周围结构之间形成的均匀间隙大小。该容器完全浸没在水中,并从内部进行加热,导致其外表面朝下沸腾。正在考虑的问题与所谓的堆芯熔体的滞留(IVR)有关,对于某些先进的压水堆(APWR),这是关键的严重事故管理策略。用于IVR的一种可用手段是在严重事故期间通过用水淹没反应堆腔室来冷却外部反应堆容器的方法。大多数APWR的设计特点是,在许多假定的事故序列中,反应堆腔体内会大量积水。在水覆盖反应堆压力容器的下部外表面的情况下,通过使容器的外表面朝下沸腾,可以通过容器壁从堆芯熔体中除去大量能量(即,衰减热)。当水在容器外表面上沸腾时,在重力的影响下,表面上产生的蒸汽将向上流过环形通道。蒸气运动会夹带液态水,从而在通道中导致浮力驱动的向上并流两相流。虽然流动完全是由沸腾过程引起的,但沸腾的速度又会受到所得两相流的影响。只要从堆芯熔体到容器壁的热通量不超过朝下沸腾的临界热通量极限,则主要采用成核沸腾方式,并且可以将容器壁保持在较低的温度下,以防止容器壁失效。下头。考虑到这种情况,问题是通过考虑两相混合物中质量,动量和能量的守恒,以及有关两相摩擦降和空隙率的可用信息来解决的。对所得的控制系统进行数值求解,以预测沸腾过程将在通道中引起的总质量流量。基于数值结果,确定了最佳的间隙尺寸,该间隙尺寸将在一定范围的壁热通量范围内最大化蒸汽的排出速率和朝下的沸腾速率。还已经确定了系统压力和反应器腔中的液位对诱导质量流率的影响。

著录项

  • 来源
    《Nuclear Technology》 |2009年第1期|178-186|共9页
  • 作者单位

    The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802;

    The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802;

    The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    boiling heat transfer; nuclear reactor safety; multiphase flow;

    机译:沸腾传热核反应堆安全;多相流;
  • 入库时间 2022-08-18 00:44:14

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