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Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code

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Proceedings of The 20th Pacific Basin Nuclear Conference (PBNC 2016)

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Abstract

In this paper Hualong One nuclear power plant model is established using TRACE code in detail. First according to analysis assumptions in PSAR, research of complete loss of flow accident (CLOFA) for Hualong One is carried out, and then research of core DNBR through the accident is carried out using FLICA III-F code. By comparison the research results and PSAR results are very consistent, it means the research method is feasible and the results are credible. On this basis, the more conservative analysis assumptions are chosen, further accident analysis is carried out. It found that all the research results can meet the acceptance criteria of CLOFA. It indicates that Hualong One is very safe and reliable at CLOFA.

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Acknowledgments

This work was financially supported by National Science and Technology Major Projects “CAP1400 safety review technology and independent verification testing” (No. 2011ZX06002010) and “CAP1400 safety review key technologies research” (No. 2013ZX06002001).

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Correspondence to Bin Jia .

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Jia, B., Jing, J., Feng, J., Zhang, C., Chai, G. (2017). Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2311-8_45

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  • DOI: https://doi.org/10.1007/978-981-10-2311-8_45

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  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-10-2310-1

  • Online ISBN: 978-981-10-2311-8

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