Experimental and numerical investigation of scale model used in the development of a spent nuclear fuel transport cask

Author:

Lan Tianbao1ORCID,Dong JiaoJiao1,Sheng Feng1

Affiliation:

1. Beijing Institute of Nuclear Engineering, China Nuclear Power Engineering Co., Ltd, Beijing, China

Abstract

To investigate the dynamic response and validate the structural integrity of a spent fuel transportation cask under the 9 m drop condition, a 1/3 scale model was utilized in a 9 m side drop test, considering the constraints of development cost and test facilities. The relationship between the response variables of the scaled model and the prototype model is obtained by Π theorem under impact drop conditions. The influencing parameters for the scale model of spent fuel transport cask drop were systematically discussed. Several numerical models of varying scales are used for verification. Finally, the 9 m drop test of the 1/3 scale model was conducted to compare the acceleration response and deformation of the 1/3 scale numerical model. The study concludes that the acceleration and deformation of the numerical model closely match the test results, and the numerical model of the prototype model represents the dynamic response of the prototype model. Furthermore, the study examined the reflections of the scale model in comparison to the real model, taking into account the dispersity of wood material and strain rate. The analysis and conclusions can be applied in engineering practice and can inspire subsequent cask designs, especially for a scaled model.

Publisher

SAGE Publications

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