Similarity Analysis Of Thermal Flow Between Prototype And Scaled-down Model For Ventilated Storage Cask

Year
2019
Author(s)
Ju-Chan Lee - Korea Atomic Energy Research Institute
File Attachment
a1419_1.pdf608.23 KB
Abstract
The weight of a spent nuclear fuel concrete storage cask is usually over 100 tons, and thermal testing using a prototype cask is expensive and time consuming. In this study, thermal testing using a scaled-down model is proposed to efficiently perform the thermal testing of the storage casks. Scaling analyses were performed to derive the scale ratios between the prototype and the half-scale model. Thermal analysis and testing were carried out to verify the reliability of the scale ratios and the similarity of the scaled-down model. The analysis results showed that the scale ratios were conserved well between the prototype and the half-scale model. The analysis results agreed well with the test results. From the results of thermal tests, thermal flow similarity has been demonstrated between the prototype cask and the half-scale model.