Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

Author:

Tabadar Z.,Hadad K.,Nematollahi M.R.,Jabbari M.,Khaleghi M.,Hashemi-Tilehnoee M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference9 articles.

1. Barrachina, T., Miró, R., Verdú, G., Pereira, C., Da Silva, C., Ortego, A., Martínez-Murillo, J.C., 2009. REA 3D-dynamic analysis in ALMARAZ NPP with RELAP5/PARCS v27 and SIMTAB cross-sections tables. In: International nuclear Atlantic conference (INAC-2009). Springer, Berlin.

2. Valuation of power oscillations in a BWR after control rod banks withdrawal events;Costa;IEEE Trans. Nucl. Sci.,2010

3. Simulation of loss-of-flow transient in a VVER-1000 nuclear power plant with RELAP5/MOD3.2;Grudev;Prog. Nucl. Energy,2004

4. International Atomic Energy Agency (IAEA), 2003. Accident analysis for nuclear power plants with pressurized water reactors safety Reports, No. 30, Vienna.

5. Development of system response analysis method for rod ejection accident of OPR1000 and APR1400 using RETRAN code;Kim;J. Nucl. Sci. Technol.,2008

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