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RELAP5 code simulation of the small break loss of coolant accident of 80 cm?? in the cold leg of Angra2 primary loop
Registro en:
0000-0001-9544-4509
Autor
BORGES, EDUARDO M.
SABUNDJIAN, GAIANE
BRAZ FILHO, FRANCISCO A.
GUIMAR??ES, LAMARTINE N.F.
INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
Resumen
The aim of this paper was to simulate and evaluate the basic design accident of 80 cm?? small break loss of
coolant accident (SBLOCA) in the cold leg of the primary loop of the Angra2 nuclear power plant. In this
simulation, it was verified that the actuation logics of the Angra2 Reactor Protection System (RPS) and the
Emergency Core Cooling System (ECCS) used in this simulation worked correctly, maintaining core integrity
with acceptable temperatures throughout the event. The results obtained were satisfactory when compared with
those presented by the Angra2 Final Safety Analysis Report (FSAR/A2).
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