Qualifying the codes and methodologies used for the evaluation of the BR2 core maximum nominal heat flux

Benoit Dionne, Constantine P. Tzanos, Arne P. Olson, John G. Stevens, Silva Kalcheva, Geert Van den Branden, Edgar Koonen

Research outputpeer-review

Original languageEnglish
Title of host publicationTransactions of the American Nuclear Society
PublisherAmerican Nuclear Society
Pages857-860
Number of pages4
Volume106
StatePublished - 2012
Event2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012 - Chicago, IL
Duration: 24 Jun 201228 Jun 2012

Publication series

NameTransactions of the American Nuclear Society
PublisherAmerican Nuclear Society
ISSN (Print)0003-018X

Conference

Conference2012 ANS Annual Meeting and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NFSM 2012
Country/TerritoryUnited States
CityChicago, IL
Period2012-06-242012-06-28

ASJC Scopus subject areas

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

Cite this