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Similarity analysis of thermal-fluid flow for thermal testing using scaled-down model of spent fuel storage cask
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.anucene.2020.107791
Ju-Chan Lee , Kyung-Sik Bang , Seung-Hwan Yu , Woo-Seok Choi , Sungho Ko

Abstract The weight of spent nuclear fuel concrete storage casks usually exceeds 100 tons. Therefore, thermal testing of prototype casks is expensive and time consuming. In this study, thermal testing method using a scaled-down model of a storage cask was developed to perform the thermal testing of large-scale storage casks efficiently. Scaling analyses were performed to derive scale ratios between a prototype cask and the scaled-down model. Additionally, thermal analyses were performed on the prototype cask and half-scale model using the obtained scale ratios. The analysis results showed that scale ratios between the prototype cask and half-scale model were conserved well. Thermal tests were performed on the prototype cask and half-scale model. The analysis and test results were in good agreement. The thermal test results confirmed the thermal-fluid flow similarity between the prototype cask and half-scale model.

中文翻译:

乏燃料储罐缩小模型用于热试验的热流体流动相似性分析

摘要 乏核燃料混凝土储罐的重量通常超过100吨。因此,原型桶的热测试既昂贵又耗时。在这项研究中,开发了使用按比例缩小的存储桶模型的热测试方法,以有效地执行大型存储桶的热测试。进行缩放分析以推导出原型桶和缩小模型之间的缩放比例。此外,使用获得的比例比例对原型桶和半比例模型进行了热分析。分析结果表明,原型桶与半比例模型之间的比例比例保持良好。对原型桶和半比例模型进行了热测试。分析和测试结果吻合良好。
更新日期:2020-12-01
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