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Development and Preliminary Verification of the 3D Core Neutronic Code: RCAD

[+] Author Affiliations
Xiaosong Chen, Xin Xiong, Lianghui Peng, Zhi Gang, Hong Xu

State Nuclear Power Research Institute (SNPRI), Beijing, China

Zhihong Liu

Tsinghua University, Beijing, China

Paper No. ICONE25-67159, pp. V003T02A044; 4 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


An inherent error occurs in the traditional light water reactor core design calculation, which is generally based on the equivalent homogenization method and diffusion calculation model. Because the boundary conditions and state parameters used in the assembly homogenization calculation is different from the real situation, the equivalent homogenization error is inevitable. This paper introduces the recent progress in the development of the 3D Core Neutronic Code: RCAD. The focus is placed on the equivalent homogenization error correction model and preliminary verification. The preliminary verification result shows that the correction model is effective and RCAD code is qualified for reactor core design for pressurized water reactor (PWR).

Copyright © 2017 by ASME



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