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Sodium Cooled Fast Bread Reactor HCDA Codes Development

[+] Author Affiliations
Shi Tai, Zhang Dong-hui, Hu Wen-jun

China Institute of Atomic Energy, Beijing, China

Paper No. ICONE25-66067, pp. V005T05A003; 7 pages
doi:10.1115/ICONE25-66067
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME

abstract

Liquid metal fast reactor is one of the Gen IV nuclear power, it is necessary to analyze hypothetical core disruptive accident (HCDA) of FBR to ensure that the system can prevent the radioactive material from leaking out. The modified Bethe-Tait model is the primary method to analyze hypothetical core disruptive accident in the world. In order to better analyze the nuclear reactor hypothetical core disruptive accident in China, an improved B-T model is used. At present, on the basis of the improved B-T model, power distribution of the CEFR add to the progress. The results of comparison between the program and SUREX program in France show that the program model can simulate the nuclear reactor hypothetical core disruptive accident in China.

Copyright © 2017 by ASME

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