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Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

VVER 1000 Severe Accident Analyses Using MELCOR Code

[+] Author and Article Information
Marek Ruščák, Sevastyan Savanyuk

Centrum Výzkumu Řež (CVŘež),
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

Milos Kynčl, Miroslav Hrehor, Alis Musa, Alain Flores y Flores

Centrum Výzkumu Řež (CVŘež),
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 5(3), 030913 (Apr 19, 2019) (9 pages) Paper No: NERS-18-1086; doi: 10.1115/1.4043378 History: Received September 14, 2018; Revised March 29, 2019

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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References

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Figures

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Fig. 1

Schematic of the developed methodology

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Fig. 2

Loop A nodalization sketch SRV + PORV

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Fig. 3

Reactor pressure vessel (RPV) nodalization sketch (accumulators (ACC))

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Fig. 5

Pressure in the pressurizer

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Fig. 6

Pressure in the SGs

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Fig. 7

SG water inventory

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Fig. 8

RPV water inventory

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Fig. 9

Maximum fuel temperature

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Fig. 10

Total H2 production from metal/control rods and water reaction

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Fig. 11

H2 production from B4C and water reaction

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Fig. 12

CO production from B4C and water reaction

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Fig. 13

CO2 production from B4C and water reaction

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Fig. 14

Methane production from B4C and water reaction

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Fig. 15

Pressure in the containment dome

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Fig. 16

Temperature in the containment dome

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Fig. 17

FPs MELCOR classes [3] releases from fuel for V1 calculation

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Fig. 18

FPs MELCOR classes [3] releases from fuel for V2 calculation

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Fig. 19

FPs MELCOR classes [3] transport in the containment for V1 calculation

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Fig. 20

FPs MELCOR classes [3] transport in the containment for V2 calculation

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