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.

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