Improvements in transient fuel performance modelling

Arttu Knuutila, Jaakko Miettinen, Jan-Olof Stengård

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional


VTT employs the fuel transient performance code FRAPTRAN for safety-related analyses of nuclear fuel. Within the High-burnup Upgrades in Fuel Behaviour Modelling research task (KORU), capabilities of FRAPTRAN have been improved by coupling the fuel performance code to an advanced thermal hydraulic model GENFLO. Further, the mechanical modelling in the FRAPTRAN code has been modernized by implementing a new mechanical model for the fuel rod cladding stress-strain analysis. FRAPTRAN-GENFLO and the new mechanical modelling have been successfully validated against the OECD Halden Project LOCA experiments.
Original languageEnglish
Title of host publicationSAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006
Subtitle of host publicationFinal Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
ISBN (Electronic)951-38-6887-7
ISBN (Print)951-38-6886-9
Publication statusPublished - 2006
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Research Notes


Dive into the research topics of 'Improvements in transient fuel performance modelling'. Together they form a unique fingerprint.

Cite this