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Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT

[+] Author Affiliations
Weiyan Yang, Chuntao Tang, Hongbo Zhang, Bo Yang

Shanghai Nuclear Engineering Research and Design Institute, Shanghai, China

Paper No. ICONE25-66567, pp. V003T02A017; 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


SCAP (SNERDI Core Analysis Package) is a nuclear core design code system newly developed by Shanghai nuclear engineering research and design institute (SNERDI), which includes three main codes: core calculation code CYCAS, automatic link code AutoLink and lattice code PANDA. By numerical comparison and analysis between SCAP system and the next generation code MPACT developed by university of Michigan, on the one hand to validate the accuracy and applicability of SCAP system, on the other hand to analyze the performance in actual nuclear power plant simulation between the second generation and the next generation codes. The benchmark applied to compare is the first cycle of the U.S. in service nuclear power plant Watts Bar # 1. The reference values include the measured data and results calculated by Monte Carlo code KENO. The numerical results indicate that, for the general core parameters, such as critical boron concentration and control rod worth, the accuracy of SCAP and MPACT is similar; for the local parameters, such as peak power factors FΔH and FQ, some biases are observed.

Copyright © 2017 by ASME
Topics: Design



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