On the use of the Serpent Monte Carlo code for few-group cross section generation

@inproceedings{Fridman2011OnTU,
  title={On the use of the Serpent Monte Carlo code for few-group cross section generation},
  author={Emil Fridman and Jaakko Johannes Lepp{\"a}nen},
  year={2011}
}
Abstract Serpent is a recently developed 3D continuous-energy Monte Carlo (MC) reactor physics burnup calculation code. Serpent is specifically designed for lattice physics applications including generation of homogenized few-group constants for full-core core simulators. Currently in Serpent, the few-group constants are obtained from the infinite-lattice calculations with zero neutron current at the outer boundary. In this study, in order to account for the non-physical infinite-lattice… CONTINUE READING

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