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

José Maria Caro, Rizwan-Uddin

Research output: Contribution to journalArticle

Abstract

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
Volume96
StatePublished - 2007

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Fast reactors
Sodium

ASJC Scopus subject areas

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

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Comparison analysis of KENO.VI and MCNP-X codes for fast Reactor Assembly. / Caro, José Maria; Rizwan-Uddin.

In: Transactions of the American Nuclear Society, Vol. 96, 2007, p. 825-826.

Research output: Contribution to journalArticle

Caro, José Maria; Rizwan-Uddin / Comparison analysis of KENO.VI and MCNP-X codes for fast Reactor Assembly.

In: Transactions of the American Nuclear Society, Vol. 96, 2007, p. 825-826.

Research output: Contribution to journalArticle

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