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Monte Carlo Burn-Up Code System MCADS and its Application

[+] Author Affiliations
Xuesong Yan, Ji Qi, Lei Yang, Xunchao Zhang, Yaling Zhang

Chinese Academy of Sciences, Lanzhou, Gansu, China

Paper No. ICONE22-30948, pp. V004T11A013; 6 pages
doi:10.1115/ICONE22-30948
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4594-3
  • Copyright © 2014 by ASME

abstract

A Monte Carlo burn-up code system, MCADS, which combines the Monte Carlo code MCNP and the depletion code LITAC, was developed for evaluation the capabilities of fuel burn-up in reactors. The code can be extremely useful for analysts who perform isotope production, material transformation, and depletion and isotope analyses on complex, non-lattice geometries, and uniform and non-uniform lattices. Three well-documented benchmarking problems including IAEA-ADS, OECD/NEA-PWR and fast reactor were used to validate MCADS. The discrepancy between the MCADS calculation and other codes fell into a reasonable range.

Copyright © 2014 by ASME

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