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Heat transfer conditions in water-cooling of a fusion reactor divertor

机译:融合反应器偏移器水冷中的传热条件

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The diverters of planned fusion reactors such as ITER require removal of heat fluxes that are large in magnitude and are spatially peaked. Single-side energy deposition on the plasma-facing surface is transferred by conduction and provides an axially and circumferentially non-uniform heat flux on the wall of the cooling channel. Promising candidate cooling systems are based on the use of highly subcooled water (subcooling more than 100/spl deg/C) flowing at very high velocities (more than 5 m/s). These conditions are quite different from those used to obtain existing correlations for single-phase convection and subcooled nucleate boiling. Through experimental assessments this paper suggests that existing correlations can be applied for single-phase convection. However, available data in the range of interest for the subcooled nucleate boiling show that extrapolations of existing correlations cannot be used. This is due to the suppression of nuclear boiling, resulting in high wall temperatures, sometimes far above expected and very close to the temperature of homogeneous nucleation (THN). Based on experimental data, a new correlation is proposed for subcooled nucleate boiling region. The range of application for the new correlation is defined as follows pressure 2-3 MPa, bulk water temperatures 19-25/spl deg/C, heat fluxes up to 25 MW/m/sup 2/, flow velocities from 3 to 15 m/s.
机译:诸如ITER的计划融合反应器的分流器需要去除大幅度的热量,并且在空间上达到峰值。面向等离子体表面上的单侧能量沉积通过传导传递并在冷却通道的壁上提供轴向和周向不均匀的热通量。承诺的候选冷却系统基于在非常高速(超过5m / s)的高水压用水(过冷超过100 / SPL DEG / C)的使用。这些条件与用于获得单相对流和亚过冷核沸腾的现有相关性的条件不同。通过实验评估本文表明,可以应用现有相关性用于单相对流。但是,在逐核核心煮沸的兴趣范围内的可用数据表明,不能使用现有相关性的外推。这是由于抑制核沸腾,导致高壁温度,有时远高于预期,非常接近均匀成核(THN)的温度。基于实验数据,提出了一种新的相关性用于过冷核沸点区域。新相关的应用范围定义如下压力2-3MPa,大量水温19-25 / SPL DEG / C,热通量高达25 mW / m / sup 2 /,从3到15米的流速/ s。

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