Fuel loading, criticality and control rod worth calculations of the Triga Mark III reactor using Serpent and MCNP
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DOI: 10.1504/ijnest.2019.10020879
Abstract: A model of the Triga Mark III reactor of the National Institute for Nuclear Research (ININ) of Mexico was developed with the Monte Carlo codes Serpent and MCNP. The models were verified and validated by… read more here.
Keywords: iii reactor; mark iii; serpent mcnp; fuel ... See more keywords