Burnup Calculation of a CANDU6 Reactor Using the Serpent and MCNP6 Codes

Validated whole-core burnup in MCNP6 and Serpent against WIMS-AECL, the industry lattice code, with k-effective versus burnup in excellent agreement. Still cited in 2025 work on SMR spent fuel in CANDU.

His part: First author.

Part of: CANDU 6 core modelling →

IAEA INISResearchGate

Cited by: Mohsen et al., Nuclear Technology 2025 (doi 10.1080/00295450.2025.2553262).

@inproceedings{hussein2014burnup,
  author = {M. S. Hussein and H. W. Bonin and B. J. Lewis},
  title = {Burnup Calculation of a CANDU6 Reactor Using the Serpent and MCNP6 Codes},
  booktitle = {19th Pacific Basin Nuclear Conference},
  year = {2014},
  address = {Vancouver},
}