Comparison analysis of KENO.VI and MCNP-X codes for fast Reactor Assembly

José Maria Caro, Rizwan Uddin

Research output: Contribution to journalConference articlepeer-review


The k∞ of a sodium cooled fast reactor assembly was calculated for two cases. Quantitative results were obtained and as a consequence of the results we observed that KENO.VI is a factor of 2 or 3 times faster than the MCNP calculations while maintaining comparable accuracy. For this reason it is concluded that KENO.VI can be used in scoping design calculations while MCNP may be reserved for more thorough work.

Original languageEnglish (US)
Pages (from-to)825-826
Number of pages2
JournalTransactions of the American Nuclear Society
StatePublished - 2007
Event2007 Annual Meeting on American Nuclear Society - Boston, MA, United States
Duration: Jun 24 2007Jun 28 2007

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality


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