TY  - CONF
ID  - upm20436
UR  - http://oa.upm.es/20436/
A1  - Jiménez Varas, Gonzalo
A1  - Queral Salazar, José Cesar
A1  - Rebollo, M.J.
A1  - Martínez-Murillo Méndez, Juan Carlos
Y1  - 2012///
N2  - A Steam Generator Tube Rupture (SGTR) in a Pressurized Water Reactor (PWR) can lead to an atmospheric release bypassing the containment via the secondary system and exiting though the Pressurized Operating Relief Valves of the affected Steam Generator. That is why SGTR historically have been treated in a special way in the different Deterministic Safety Analysis (DSA), focusing on the radioactive release more than the possibility of core damage, as it is done in the other Loss of Coolant Accidents(LOCAs).
TI  - Simulación del accidente de SGTR en un PWR-W con TRACE para distintas metodologías de análisis determinista de seguridad
SP  - 1
M2  - Cáceres, Spain
AV  - public
EP  - 1
T2  - 38º Reunion Anual de la Sociedad Nuclear Española
ER  -