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
VTT acquires and maintains independent calculation tools to be applied to fuel performance analyses ...
International audienceSince the early 1990s, the French “Institut de Radioprotection et de Sûreté Nu...
Thermal hydraulic simulation capability for accident conditions is needed at present in VTT in sever...
Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnu...
The modelling in fuel behaviour codes that are in use at VTT has been subject to extensive upgrading...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
Work is described that has been done to modernise the mechanical modelling of FRAPCON and FRAPTRAN c...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
Assessment, validation, and further development of the fuel behaviour codes in use at VTT have been ...
Fuel rod analysis program transient (FRAPTRAN) code was used to study the fuel rod performance durin...
This volume describes the fuel rod material and performance models that were updated for the FRAPCON...
There is a clear economic incentive for the industry to continue the trend of pursuing higher fuel d...
In assuring reactor safety with increasing target burnups, fuel behaviour in postulated accident con...
A review of the current thermomechanical needs along with a recommendation of the most urgent ones t...
VTT acquires and maintains independent calculation tools to be applied to fuel performance analyses ...
International audienceSince the early 1990s, the French “Institut de Radioprotection et de Sûreté Nu...
Thermal hydraulic simulation capability for accident conditions is needed at present in VTT in sever...
Reactor analyses are becoming more and more challenging. Due to pursuing higher fuel discharge burnu...
The modelling in fuel behaviour codes that are in use at VTT has been subject to extensive upgrading...
Demands for reactor safety assessments and for the tools to make these are continuously growing. Apa...
Work is described that has been done to modernise the mechanical modelling of FRAPCON and FRAPTRAN c...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
VTT maintains and further developes a comprehensive safety analysis code system ranging from the bas...
Assessment, validation, and further development of the fuel behaviour codes in use at VTT have been ...
Fuel rod analysis program transient (FRAPTRAN) code was used to study the fuel rod performance durin...
This volume describes the fuel rod material and performance models that were updated for the FRAPCON...
There is a clear economic incentive for the industry to continue the trend of pursuing higher fuel d...
In assuring reactor safety with increasing target burnups, fuel behaviour in postulated accident con...
A review of the current thermomechanical needs along with a recommendation of the most urgent ones t...
VTT acquires and maintains independent calculation tools to be applied to fuel performance analyses ...
International audienceSince the early 1990s, the French “Institut de Radioprotection et de Sûreté Nu...
Thermal hydraulic simulation capability for accident conditions is needed at present in VTT in sever...