雅典娜主热交换器概念设计与RELAP5规范热水力评价

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-02-27 DOI:10.1115/1.4056973
Tommaso Del Moro, P. Lorusso, F. Giannetti, M. Tarantino, M. Caramello, D. Mazzi, M. Constantin
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引用次数: 0

摘要

在支持ALFRED反应堆开发的设想实验基础设施中,FALCON财团将ATHENA确定为解决池热水力挑战的设施之一,并演示修改ALFRED配置的可行性,以及其主要部件的热水力性能。ATHENA是一个大型水池型铅冷却多用途实验设施,具有大尺寸容器(直径3.2米,高10米),可容纳近800吨铅,用于测试ALFRED相关的比例组件。安装在主容器内的测试部分包括一个由7个FAs组成的电加热堆芯模拟器,该模拟器向主冷却剂提供2210 kW的标称热功率,一个用于铅循环的主冷却剂泵和一个逆流壳管主热交换器,该热交换器的管束由专用二次回路的加压水供给。已经进行了初步的分析计算,以确定最适合ATHENA热交换器的配置,以及实现组件的初步尺寸。最终的布局是一束91个卡口管,排列成圆柱形,有效长度为3000 mm,采用带有加压氦气间隙的外部双壁管。利用热工液压系统代码RELAP5/Mod3.3建立了该换热器的数值模型,并对其几何参数和工作参数进行了数值敏感性分析,验证了该换热器的性能。
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Athena Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment with RELAP5 Code
Among the envisaged experimental infrastructures supporting ALFRED reactor development, FALCON consortium identified ATHENA as one of the facilities to address the pool thermal-hydraulic challenges and demonstrate the feasibility of the revised ALFRED configuration, along with the thermal-hydraulic performances of its main components. ATHENA is a large pool-type lead-cooled multi-purpose experimental facility featuring a large size vessel (3.2 m diameter, 10 m in height), conceived to host almost 800 tons of lead to test ALFRED relevant scaled components. The test section to be installed in the main vessel includes an electrically heated core simulator, made of 7 FAs, which delivers to the primary coolant a nominal thermal power of 2210 kW, a main coolant pump for lead circulation and a counter-current shell and tubes main heat exchanger, which tube bundle is fed by pressurized water by a dedicated secondary circuit. A preliminary analytical calculation has been performed to identify the most suitable configuration for the ATHENA heat exchanger, as well as to achieve a preliminary sizing of the component. The final layout foresees a bundle of 91 bayonet tubes, arranged in a cylindrical geometry, having an active length of 3000 mm and adopting an external double wall tube with a pressurized helium gap. A numerical model of the heat exchanger has been developed using the thermal-hydraulic system code RELAP5/Mod3.3, and a numerical sensitivity analysis on the geometrical and operating parameters has been carried out to verify the performances of the component.
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期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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