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THERMAL-HYDRAULIC EVALUATION OF AN LBE COOLED 19-PIN BUNDLE IN THE FRAME OF TRACE VALIDATION

机译:LBE冷却的19针管束在痕迹验证框架中的热工液压评估

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In the frame of the validation and verification of the thermal hydraulic system code TRACE for lead alloy cooled systems, a 19 pin bundle is analyzed, in particular, the influence of the spacers. TRACE is updated and improved in order to be used for the analyses of liquid metal cooled reactors. For the present investigation, isothermal hydraulic experiments, carried out at the Karlsruhe Lead Laboratory, are used to validate the pressure losses related to wall friction and spacers. In this experimental set-up, a 19 rod bundle, cooled by liquid lead-bismuth eutectics (LBE) is used. In addition, thermal analyses are performed in order to evaluate the axial temperature profile of coolant and cladding and to validate the chosen heat transfer models. Since the thermal experiments have not been performed yet, the validation is done by comparing TRACE results to CFD results following a unique approach for the turbulent Prandtl number. Special emphasize is paid to the validation of the models to account for heat transfer enhancement at and in the vicinity of spacers due to increased turbulences.
机译:在铅合金冷却系统的热液压系统代码TRACE的确认和检验框架中,分析了19针束,特别是垫片的影响。 TRACE已更新和改进,可用于分析液态金属冷却反应堆。对于本研究,使用在卡尔斯鲁厄铅实验室进行的等温水力实验来验证与壁摩擦和垫片有关的压力损失。在此实验装置中,使用了一根由液态铅-铋共晶(LBE)冷却的19棒束。此外,进行热分析以评估冷却液和熔覆层的轴向温度曲线,并验证所选的传热模型。由于尚未进行热实验,因此通过采用湍流普朗特数的独特方法将TRACE结果与CFD结果进行比较来进行验证。特别强调了模型的验证,以说明由于湍流增加而在垫片处及其附近的传热增强。

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