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A Novel Method for Solving Reactor Physics Diffusion and Transport Equation

[+] Author Affiliations
Hu Wenjun, Cao Yonggang

China Institute of Atomic Energy, Beijing, China

Paper No. ICONE25-66045, pp. V003T02A002; 5 pages
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5781-6
  • Copyright © 2017 by ASME


The computational software based on the numerical technology are widely being utilized in the nuclear design, where the numerical method has been always being a topic attracting abundant concern. Combining the feature of reactor physics equation and non-structure mesh technology, a novel method appropriate for structure/non-structure mesh calculation is proposed. The paper illustrates the implementation of the method taking the diffusion and 1st order discrete ordinate transport equation as an example, by demonstrating the discretization of region, the discretization of equation and the implementation of boundary conditions.

Copyright © 2017 by ASME



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