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Experimental and Numerical Investigation of Turbulent Liquid Metal Heat Transfer along a Heated Rod in Annular Cavity

机译:沿环形腔加热棒湍流液态金属传热的实验性和数值研究

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The turbulent heat transfer from a heated rod concentrically placed in annular cavity towards the liquid metal represents a crucial element for the.design of a fuel assembly of advanced liquid metal cooled nuclear systems. Therein, this configuration represents the most idealized simple geometry tractable by numerical means. Hence the single pin experiment acts in the framework of the EUROpean Research Programme for the TRANSmutation of High Level Nuclear Waste in Accelerator Driven System (EUROTRANS) as the validation case for several thermal-hydraulic fuel assembly experiments aimed at the understanding of the turbulent momentum and heat transport of heavy liquid metal (HLM) flows at reactor conditions. The single experiment operated in Pb~(45)Bi~(55) of the THESYS loop of KALLA covers regarding the Prandtl number, the power density and the pin dimensions the entire range of flow parameters potentially occurring in fuel assemblies of an PDS-XADS (Preliminary Design Studies of an eXperimental Accelerator-Driven System) or of a lead cooled fast reactor (LFR). This study focuses on a complementary experimental and numerical study of the turbulent heat transfer from the heated fuel pin simulated to liquid metal at forced convective flow conditions, since they represent the preferential nominal operation mode of the reactor. Within the experiment velocities and temperatures are recorded around of the fuel pin simulator. The rod is aligned within the gravity field in the loop and it is centred by means of three equidistant placed spacers along its axis. The complementary conducted numerical studies aim at interpreting the experimental results as well as the validation of used turbulent models. The paper presents also the effect of spacer on the flow field, and consecutive on the heat transfer from the heated rod. Regarding the turbulent forced convective flow an acceptable agreement between the numerical and experimental data is obtained both for temperature and velocity field. The observed discrepancies can be attributed to imperfections of the experimental set-up or the neglecting of internals by the numerical simulation.
机译:从加热杆湍流传热同心放置在环形腔朝向液体金属表示的组件先进液态金属冷却核系统的燃料的the.design一个关键因素。在其中,该配置表示通过数值手段最理想化简单的几何形状易于处理。因此,单针实验的作用,在欧洲研究计划的高放核废料的加速器驱动系统(EUROTRANS)作为验证的情况下,主要业务在动荡的势头认识几个热工水力燃料组件的实验和嬗变框架重质液体金属(HLM)的热输送在反应器条件下流动。在单次实验中的Pb〜(45)的Bi关于普朗特数,功率密度和销尺寸的流动参数的整个范围中的PDS-XADS的燃料组件可能发生KALLA盖的THESYS环的〜(55)操作的或的引线(实验加速器驱动系统的初步设计研究)中的冷却快堆(LFR)。本研究的重点上的互补实验和模拟从在强制对流条件下为液体的金属的加热的燃料销湍流传热的数值研究,因为它们代表了反应器的优先标称操作模式。在实验速度和温度的燃料针模拟器的记录身边。该杆在循环重力场内对准,它是由沿其轴线三个等距离放置间隔件装置的中心。互补进行的数值研究旨在解释实验结果以及所使用湍流模型的验证。本文介绍也间隔件的上流场上从加热的杆传热的效果,并且是连续的。关于强制对流流动的数值模拟和实验数据之间的可接受协定湍流被用于温度和速度场得到两者。所观察到的差异可以归因于该实验设置或内部的由数值模拟忽略了缺陷。

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