Abstract
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 language | English |
|---|---|
| Title of host publication | SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006 |
| Subtitle of host publication | Final Report |
| Place of Publication | Espoo |
| Publisher | VTT Technical Research Centre of Finland |
| Pages | 69-78 |
| ISBN (Electronic) | 951-38-6887-7 |
| ISBN (Print) | 951-38-6886-9 |
| Publication status | Published - 2006 |
| MoE publication type | Not Eligible |
Publication series
| Series | VTT Tiedotteita - Research Notes |
|---|---|
| Number | 2363 |
| ISSN | 1235-0605 |