Advanced
search

To read this content please select one of the options below:

A coupled thermal-drop impact analysis-based safety assessment of radioactive material cask

Qiang Liu (Center for System Reliability and Safety, School of Mechanical and Electrical Engineering, University of Electronic Science and Technology of China, Chengdu, China)
Shun-Peng Zhu (Center for System Reliability and Safety, School of Mechanical and Electrical Engineering, University of Electronic Science and Technology of China, Chengdu, China)
Zheng-Yong Yu (Center for System Reliability and Safety, School of Mechanical and Electrical Engineering, University of Electronic Science and Technology of China, Chengdu, China)
Ran Ding (Reactor Operation and Application Division, Nuclear Power Institute of China, Chengdu, China)

International Journal of Structural Integrity

ISSN: 1757-9864

Article publication date: 9 April 2018

113

Abstract

Purpose

Transport is an integral part of the nuclear fuel cycle. The procedures employed are designed and conducted to ensure the public and environment protection both routinely and when transport accidents occur. According to this, the purpose of this paper is to focus on a coupled thermal-drop impact analysis-based safety assessment of a nuclear fuel cask.

Design/methodology/approach

For the cask, high altitude falling and fire accidents are the two most serious accidents during its transportation. In this paper, a sequentially coupled thermal-drop impact analysis is performed by using a nuclear fuel cask model for safety assessment. High altitude falling and fire accidents of the nuclear fuel cask were conducted by using finite element simulations for coupled thermal-drop impact analysis.

Findings

Results showed that the cask can withstand a drop test and survive a fire of 800°C for 30 minutes. In addition, an improved design is explored and evaluated, which provides a reference for structural design and safety assessment of nuclear fuel casks.

Originality/value

A coupled thermal-drop impact analysis-based safety assessment procedure is developed for the nuclear fuel cask.

Keywords

Acknowledgements

The authors would like to acknowledge the financial support of the National Natural Science Foundation of China under the Contract Nos 11672070 and 11302044 and the Fundamental Research Funds for the Central Universities under the Contract No. ZYGX2016J208.

Citation

Liu, Q., Zhu, S.-P., Yu, Z.-Y. and Ding, R. (2018), "A coupled thermal-drop impact analysis-based safety assessment of radioactive material cask", International Journal of Structural Integrity, Vol. 9 No. 2, pp. 185-195. https://doi.org/10.1108/IJSI-05-2017-0028

Publisher

:

Emerald Publishing Limited

Copyright © 2018, Emerald Publishing Limited

Related articles

Manage cookies

We’re listening — tell us what you think

Join us on our journey