The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code
Journal Article
·
· AIP Conference Proceedings
This work discusses the behavior of Angra 2 nuclear power plant core, for a postulate Loss of Coolant Accident (LOCA) in the primary circuit for Small Break Loss Of Coolant Accident (SBLOCA). A pipe break of the hot leg Emergency Core Cooling System (ECCS) was simulated with RELAP 5 code. The considered rupture area is 380 cm{sup 2}, which represents 100% of the ECCS pipe flow area. Results showed that the cooling is enough to guarantee the integrity of the reactor core.
- OSTI ID:
- 22111942
- Journal Information:
- AIP Conference Proceedings, Vol. 1529, Issue 1; Conference: 35. Brazilian workshop on nuclear physics, Sao Paulo (Brazil), 2-6 Sep 2012; Other Information: (c) 2013 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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