Probabilistic safety assessment (PSA) method was explored to be introduced in radiation risk assessment of radioactive material transport (RMT), and then radiation risk of road transport (RT) of new fuel element (FE) of commercial High Temperature Reactor-Pebblebed Modules (HTR-PM) was analyzed. By accident scenario analysis, mechanical analysis and criticality analysis, both accident conditions of package radiation level hoist and criticality were chosen for accident frequency analysis. Since the results show that accident frequency of package radiation level hoist is low and accident frequency of criticality is extremely low, criticality accident can be neglected in the sequential risk assessment. The consequence of typical accident scenarios was estimated, and the results show that the maximum external exposure dose arising from the accident for emergency workers is 0.55mSv, and 4.55×10−3mSv for public people around, which is acceptable. The global radiation risk is 1.24×10−10person·Sv/(vehicle·each transport), for which impact accident contributes the maximum percent.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5782-3
PROCEEDINGS PAPER
PSA Research of Transport of New Fuel of HTR-PM
Wang Renze,
Wang Renze
China Institute for Radiation Protection, Taiyuan, China
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Zhang Jiangang,
Zhang Jiangang
China Institute for Radiation Protection, Taiyuan, China
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Li Guoqiang,
Li Guoqiang
China Institute for Radiation Protection, Taiyuan, China
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Zhuang Dajie,
Zhuang Dajie
China Institute for Radiation Protection, Taiyuan, China
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Meng Dongyuan,
Meng Dongyuan
China Institute for Radiation Protection, Taiyuan, China
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Wang Xuexin,
Wang Xuexin
China Institute for Radiation Protection, Taiyuan, China
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Sun Hongchao,
Sun Hongchao
China Institute for Radiation Protection, Taiyuan, China
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Sun Shutang
Sun Shutang
China Institute for Radiation Protection, Taiyuan, China
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Wang Renze
China Institute for Radiation Protection, Taiyuan, China
Zhang Jiangang
China Institute for Radiation Protection, Taiyuan, China
Li Guoqiang
China Institute for Radiation Protection, Taiyuan, China
Zhuang Dajie
China Institute for Radiation Protection, Taiyuan, China
Meng Dongyuan
China Institute for Radiation Protection, Taiyuan, China
Wang Xuexin
China Institute for Radiation Protection, Taiyuan, China
Sun Hongchao
China Institute for Radiation Protection, Taiyuan, China
Sun Shutang
China Institute for Radiation Protection, Taiyuan, China
Paper No:
ICONE25-66012, V004T14A002; 5 pages
Published Online:
October 17, 2017
Citation
Renze, W, Jiangang, Z, Guoqiang, L, Dajie, Z, Dongyuan, M, Xuexin, W, Hongchao, S, & Shutang, S. "PSA Research of Transport of New Fuel of HTR-PM." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management. Shanghai, China. July 2–6, 2017. V004T14A002. ASME. https://doi.org/10.1115/ICONE25-66012
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