Thermal hydraulic simulations of the Angra 2 PWR

Author:

González-Mantecón Javier,Costa Antonella Lombardi,Veloso Maria Auxiliadora Fortini,Pereira Claubia,de Lima Reis Patrícia Amélia,Hamers Adolfo R.,Scari Maria Elizabeth

Publisher

EDP Sciences

Reference10 articles.

1. THE RELAP5-3D©CODE DEVELOPMENT TEAM, RELAP5-3D©User's Manual(Idaho National Laboratory, Idaho Falls, 2009)

2. The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code

3. Rocha M.S., Sabundjian G., Belchior A. et al., Angra 2 Small Break LOCA Flow Regime Identification Through RELAP5 Code, inProceedings of ENCIT 2012, 14th Brazilian Congress of Thermal Sciences and Engineering, Rio de Janeiro, Brazil(2012)

4. Crook T., Vaghetto R., Vanni A., Hassan Y.A., Sensitivity analysis of a PWR response during a loss of coolant accident under a hypothetical core blockage scenario using RELAP5-3D, inProceedings of the 2014, 22nd International Conference on Nuclear Engineering, ICONE22, Prague, Czech Republic(2014)

5. Eletrobrás Eletronuclear,Final Safety Analysis Report – Central Nuclear Almirante Álvaro Alberto – Unit 2, Eletrobrás Termonuclear S.A., Rev.13(2013)

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