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Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation

Autor
Freixa, J.; Manera, A.; Kim, T-W.
Tipus d'activitat
Article en revista
Revista
Nuclear engineering and design
Data de publicació
2013-11
Volum
264
Pàgina inicial
153
Pàgina final
160
DOI
https://doi.org/10.1016/j.nucengdes.2013.02.023 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 (LSTF). Two intermediate break loss-of-coolant-accident (LOCA) experiments (Tests 1 and 2) have been carried out during 2010. The two tests were analyzed by using the US-NRC TRACE best estimate code. A post-test calculation was performed for each test along with uncertainty analysis providing uncertainty ban...
Paraules clau
Pwr, Loca, Thermal-hydraulics, Ccfl
Grup de recerca
ANT - Advanced Nuclear Technologies Research Group

Participants