Radiation dose and personnel protection are among the safety goals of geological disposal of high-level radioactive waste. The calculation of the dose field on the surface of the packaging container is of great significance for the research on the dose constraint value of the repository. This paper built model consulting the Sweden KBS-3 canister, the temporal and spatial distribution of the dose rate on canister surface was calculated by Monte Carlo method, the temporal and spatial distribution of radiation dose rate of the tunnel was obtained. The research results showed that the photon dose rate on canister surface was greater than the neutron dose rate by 4 to 6 orders of magnitude, and the dose value of repository tunnel within 100 thousand years was lower than the ICRP recommended dose limit value (0.3 mSv/a) by 5 orders of magnitude.
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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
The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface Available to Purchase
Bo Yang,
Bo Yang
East China University of Technology, Nanchang, China
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Qianglin Wei,
Qianglin Wei
East China University of Technology, Nanchang, China
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Hexi Wu,
Hexi Wu
East China University of Technology, Nanchang, China
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Xujia Luo,
Xujia Luo
East China University of Technology, Nanchang, China
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Yibao Liu
Yibao Liu
East China University of Technology, Nanchang, China
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Bo Yang
East China University of Technology, Nanchang, China
Qianglin Wei
East China University of Technology, Nanchang, China
Hexi Wu
East China University of Technology, Nanchang, China
Xujia Luo
East China University of Technology, Nanchang, China
Yibao Liu
East China University of Technology, Nanchang, China
Paper No:
ICONE26-82056, V007T10A019; 4 pages
Published Online:
October 24, 2018
Citation
Yang, B, Wei, Q, Wu, H, Luo, X, & Liu, Y. "The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface." 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. V007T10A019. ASME. https://doi.org/10.1115/ICONE26-82056
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