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首页> 外文期刊>Fusion Engineering and Design >Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code
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Parametric thermal-hydraulic analysis of the EU DEMO Water-Cooled Lithium-Lead First Wall using the GETTHEM code

机译:使用GETTHEM代码对EU DEMO水冷锂铅第一壁进行参数热工分析

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摘要

The system-level code GETTHEM is applied to the thermal-hydraulic analysis of an entire segment of the Water-Cooled Lithium-Lead (WCLL) First Wall (FW) of the EU DEMO reactor, parametrically varying the heat load of the FW and the coolant mass flow rate. The results show that the WCLL FW design can tolerate variations of the distribution of the heat flux with respect to the design value, without requiring modifications. The top inboard and the bottom outboard regions are identified as most critical from the point of view of the cooling of the FW. Finally, the largest possible extent of the WCLL FW surface where the peak heat load can be safely applied is identified through a parametric analysis, performed on the critical regions, to understand which is the limit of the cooling capacity of the system.
机译:系统级代码GETTHEM用于对欧盟DEMO反应堆的水冷锂铅(WCLL)第一壁(FW)整个段进行热工液压分析,通过参数方式改变FW和反应堆的热负荷。冷却液质量流量。结果表明,WCLL FW设计可以容忍相对于设计值的热通量分布变化,而无需进行修改。从FW的冷却角度来看,顶部内侧区域和底部外侧区域被认为是最关键的区域。最后,通过对关键区域执行的参数分析来确定可以安全施加峰值热负荷的WCLL FW表面的最大可能范围,以了解这是系统冷却能力的极限。

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