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Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test

Autor
Freixa, J.; manera, A.
Tipus d'activitat
Article en revista
Revista
Nuclear engineering and design
Data de publicació
2011-03
Volum
241
Número
3
Pàgina inicial
888
Pàgina final
896
DOI
https://doi.org/10.1016/j.nucengdes.2010.12.016 Obrir en finestra nova
URL
http://www.sciencedirect.com/science/article/pii/S0029549311000148 Obrir en finestra nova
Resum
In cooperation with the Finnish Radiation and Nuclear Safety Authority (STUK), a project has been launched at the Paul Scherrer Institute (PSI) aimed at performing safety evaluations of the Olkiluoto-3 nuclear power plant (NPP), the first EPR™, a generation III pressurizer water reactor (PWR); with particular emphasis on small-and large-break loss-of-coolant-accidents (SB/LB-LOCAs) and main steam-line breaks. As a first step of this work, the best estimate system code TRACE has been used to de...
Paraules clau
EPR, LSTF, SBLOCA, scaling
Grup de recerca
ANT - Advanced Nuclear Technologies Research Group

Participants