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Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation

Autor
Freixa, J.; Kim, T-W.; Manera, A.
Tipus d'activitat
Article en revista
Revista
Nuclear engineering and design
Data de publicació
2012-08
Volum
249
Pàgina inicial
97
Pàgina final
103
DOI
https://doi.org/10.1016/j.nucengdes.2011.08.061 Obrir en finestra nova
Resum
The OECD/NEA ROSA-2 project aims at addressing thermal-hydraulic safety issues relevant for light water reactors by building up an experimental database at the ROSA Large Scale Test Facility. Test 1 of the ROSA-2 program consists of an intermediate break located in one of the hot legs, in particular it represents the rupture of the pressurizer surge line. Using a TRACE model, a blind case calculation was performed. An uncertainty analysis was carried out together with the simulation of Test 1, i...
Paraules clau
Rosa, Loc, Pwr, Uncertainties,
Grup de recerca
ANT - Advanced Nuclear Technologies Research Group

Participants