In this paper, a kind of transport container we designed was introduced. This container was designed to transport nuclear fuel pellets in different enrichment of U-235. The weight of this package is about 400kg, including the contents. One protect shell and two sealed border were designed in this container, which can ensure the contents were intact and the package has no criticality risk after transport accidents. During the design and safety analysis process, finite element analysis methods were used to improve the structure and analyze the safety performances of the container. In addition, we will test the safety performances of this container through a series of experiments in the future, including 9m drop (or crush), puncture, fire, water immersion and so on. Now, the calculate results show that this container was fit to the safety requirements in the transport accidents.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5151-7
PROCEEDINGS PAPER
Design and Safety Analysis of a Kind of UO2 Pellets Transport Container Available to Purchase
Shutang Sun,
Shutang Sun
China Institute for Radiation Protection, Taiyuan, China
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Dongyuan Meng,
Dongyuan Meng
China Institute for Radiation Protection, Taiyuan, China
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Guoqiang Li,
Guoqiang Li
China Institute for Radiation Protection, Taiyuan, China
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Hongchao Sun,
Hongchao Sun
China Institute for Radiation Protection, Taiyuan, China
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Jiangang Zhang,
Jiangang Zhang
China Institute for Radiation Protection, Taiyuan, China
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Dajie Zhuang,
Dajie Zhuang
China Institute for Radiation Protection, Taiyuan, China
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Lei Chen,
Lei Chen
China Institute for Radiation Protection, Taiyuan, China
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Yiren Lian
Yiren Lian
China Institute for Radiation Protection, Taiyuan, China
Search for other works by this author on:
Shutang Sun
China Institute for Radiation Protection, Taiyuan, China
Dongyuan Meng
China Institute for Radiation Protection, Taiyuan, China
Guoqiang Li
China Institute for Radiation Protection, Taiyuan, China
Hongchao Sun
China Institute for Radiation Protection, Taiyuan, China
Jiangang Zhang
China Institute for Radiation Protection, Taiyuan, China
Dajie Zhuang
China Institute for Radiation Protection, Taiyuan, China
Lei Chen
China Institute for Radiation Protection, Taiyuan, China
Yiren Lian
China Institute for Radiation Protection, Taiyuan, China
Paper No:
ICONE26-82291, V007T10A021; 5 pages
Published Online:
October 24, 2018
Citation
Sun, S, Meng, D, Li, G, Sun, H, Zhang, J, Zhuang, D, Chen, L, & Lian, Y. "Design and Safety Analysis of a Kind of UO2 Pellets Transport Container." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events. London, England. July 22–26, 2018. V007T10A021. ASME. https://doi.org/10.1115/ICONE26-82291
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