Autor: |
Sabundjian, Gaianê, Andrade, Delvonei A., Belchior Jr., Antonio, da Silva Rocha, Marcelo, Conti, Thadeu N., Torres, Walmir M., Macedo, Luiz A., Umbehaun, Pedro E., Mesquita, Roberto N., Masotti, Paulo H. F., de Souza Lima, Ana Cecília |
Předmět: |
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Zdroj: |
AIP Conference Proceedings; May2013, Vol. 1529 Issue 1, p151-154, 4p |
Abstrakt: |
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 cm2, which represents 100% of the ECCS pipe flow area. Results showed that the cooling is enough to guarantee the integrity of the reactor core. [ABSTRACT FROM AUTHOR] |
Databáze: |
Complementary Index |
Externí odkaz: |
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