Calculation of the Radial and Axial Flux and Power Distribution for a CANDU 6 Reactor with both the MCNP6 and Serpent Codes

Built full 3-D MCNP6 and Serpent models of the CANDU 6 (Gentilly-2) core with 37-element bundles and compared flux and power-density maps; Serpent matched MCNP6 and was the more efficient of the two.

His part: First author.

Part of: CANDU 6 core modelling →

IAEA INISResearchGate

@inproceedings{hussein2014power,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis},
  title = {Calculation of the Radial and Axial Flux and Power Distribution for a CANDU 6 Reactor with both the MCNP6 and Serpent Codes},
  booktitle = {19th Pacific Basin Nuclear Conference},
  year = {2014},
  address = {Vancouver},
}