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Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE

Autor
Freixa, J.; Manera, A.
Tipus d'activitat
Article en revista
Revista
Nuclear engineering and design
Data de publicació
2010-07
Volum
240
Número
7
Pàgina inicial
1779
Pàgina final
1788
DOI
https://doi.org/10.1016/j.nucengdes.2010.02.007 Obrir en finestra nova
Resum
Inspections of existing nuclear power plants have pointed out the possibility that small break loss-of-coolant accidents (SBLOCAs) could be initiated by a small break located in the upper head of the reactor pressure vessel. Such type of breaks has been the subject of investigation in some of the tests carried out in the framework of the OECD/NEA ROSA test program for safety research and safety assessment of light water reactors. The ROSA/LSTF test facility simulates a Westinghouse design PWR wi...
Paraules clau
PWR, SBLOCA, thermal-hydraulics
Grup de recerca
ANT - Advanced Nuclear Technologies Research Group

Participants