This work describes the computer model development of the water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and its subsequent use for the accident scenarios analysis leading to the core melting. The baseline accident scenario was a stress test case—the station blackout (SBO, the complete loss of alternating current electric power in a nuclear power plant). In addition to this, four other scenarios were analyzed in which the SBO was combined with other technological failures—the loss of steam generator feedwater system and small, medium, and large break coolant accidents (LOCA). The results provided detailed information on the time course of accident scenarios, their temperature and pressure parameters, hydrogen production, and the mass inventory released from the molten corium and debris into the containment of the NPP.
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July 2019
Research-Article
VVER 1000 Severe Accident Analyses Using MELCOR Code
Marek Ruščák,
Marek Ruščák
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
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Guido Mazzini,
Guido Mazzini
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
1Corresponding author.
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Milos Kynčl,
Milos Kynčl
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
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Sevastyan Savanyuk,
Sevastyan Savanyuk
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
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Miroslav Hrehor,
Miroslav Hrehor
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
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Alis Musa,
Alis Musa
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
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Alain Flores y Flores
Alain Flores y Flores
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
Search for other works by this author on:
Marek Ruščák
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Guido Mazzini
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Milos Kynčl
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
Sevastyan Savanyuk
Centrum Výzkumu Řež (CVŘež),
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Hlavní 130,
Husinec–Řež 250 68, Czech Republic
Miroslav Hrehor
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
Alis Musa
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
Alain Flores y Flores
Centrum Výzkumu Řež (CVŘež),
Husinec–Řež 250 68, Czech Republic
Hlavní 130
,Husinec–Řež 250 68, Czech Republic
1Corresponding author.
Manuscript received September 14, 2018; final manuscript received March 29, 2019; published online April 19, 2019. Assoc. Editor: Michal Kostal.
ASME J of Nuclear Rad Sci. Jul 2019, 5(3): 030913 (9 pages)
Published Online: April 19, 2019
Article history
Received:
September 14, 2018
Revised:
March 29, 2019
Citation
Ruščák, M., Mazzini, G., Kynčl, M., Savanyuk, S., Hrehor, M., Musa, A., and Flores y Flores, A. (April 19, 2019). "VVER 1000 Severe Accident Analyses Using MELCOR Code." ASME. ASME J of Nuclear Rad Sci. July 2019; 5(3): 030913. https://doi.org/10.1115/1.4043378
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