Review of worldwide reactor-physics codes and their applicability to CANDU® and ACR-1000® analysis

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Abstract

This paper reviews and summarizes the current stochastic (Monte Carlo) codes and deterministic codes used in reactor-physics analysis, with particular emphasis on those aspects relevant to CANDU® and ACR-1000® analysis. The review concentrates on the main features of each reactor-physics toolset with respect to state-of-the-art reactor-physics and numerical modelling aspects, as well as to new methodologies. Where relevant, the applicability of these codes to CANDU and ACR-1000 analysis is covered as well.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009
Pages879-894
Number of pages16
StatePublished - 2009
Externally publishedYes
Event30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009 - Calgary, AB, Canada
Duration: 31 May 20093 Jun 2009

Publication series

NameCanadian Nuclear Society - 30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009
Volume2

Conference

Conference30th Annual Canadian Nuclear Society Conference and 33rd CNS/CNA Student Conference 2009
Country/TerritoryCanada
CityCalgary, AB
Period31/05/093/06/09

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