Evolution of RFSP 3.5 for CANDU analysis

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

15 Scopus citations

Abstract

From the outset of the development of the CANDU®1 reactor design, the reactor physics analysis of the core has relied on computer programs developed in Canada and international codes that have been modified and improved. RFSP is the main scientific code for full-core neutronics simulation and analysis of CANDU reactors. Computer codes have evolved to account for the unique characteristics of CANDU reactors. The specific new features, functions, and methodologies that have evolved in RFSP 3.5 series since the last major release of RFSP-IST version 3-04 in 2006 are reviewed in this paper. The new versions of RFSP 3.5 series offer unique capabilities for the design, operate and safety analysis of CANDU-type reactors.

Original languageEnglish
Title of host publicationCanadian Nuclear Society - 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS/CNA Student Conference 2012
Subtitle of host publicationBuilding on Our Past... Building for the Future
Pages1277-1288
Number of pages12
StatePublished - 2012
Externally publishedYes
Event33rd Annual Conference of the Canadian Nuclear Society and 36th CNS/CNA Student Conference 2012: Building on Our Past... Building for the Future - Saskatoon, SK, Canada
Duration: 10 Jun 201213 Jun 2012

Publication series

NameCanadian Nuclear Society - 33rd Annual Conference of the Canadian Nuclear Society and 36th CNS/CNA Student Conference 2012: Building on Our Past... Building for the Future
Volume2

Conference

Conference33rd Annual Conference of the Canadian Nuclear Society and 36th CNS/CNA Student Conference 2012: Building on Our Past... Building for the Future
Country/TerritoryCanada
CitySaskatoon, SK
Period10/06/1213/06/12

Keywords

  • CANDU
  • Neutron diffusion
  • RFSP

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