Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink accident using RELAP5/MOD3.2 code

Author:

Tabadar Z.,Ansarifar G.R.,Pirouzmand A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference14 articles.

1. Hisham El-Khatib, Salah El-Din El-Morshedy, Maher.G. Higazy, Karam El-Shazly, 2013. Modeling and simulation of loss of the ultimate heat sink in a typical material testing reactor. Ann. Nuclear Energy 51, 156–166.

2. Konstantina Voukelatou, Paolo Turroni, 2012. Stress test for the nuclear power plants of European and neighboring Countries, RdS/2012/133.

3. Fukushima Daiichi accident as a stress test for the national system for the protection of the public in event of severe accident at NPP;Kutkov;Nucl. Energy Technol.,2017

4. Considerations for severe accident management under extended station blackout conditions in nuclear power plants;Park;Prog. Nucl. Energy,2016

5. The RELAP/SCDAP Code Development Team (RCDT), 2011. RELAP/SCDAP Code Manual. Idaho National Engineering Laboratory.

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