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Technical Brief

Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor

[+] Author and Article Information
Guido Mazzini

Centrum Výzkumu Řež,
Nuclear Regulation Support Section,
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz

Miloš Kynčl

Centrum Výzkumu Řež,
Nuclear Regulation Support Section,
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: milos.kyncl@cvrez.cz

Marek Ruščák

Centrum Výzkumu Řež,
Nuclear Regulation Support Section,
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: marek.ruscak@cvrez.cz

Manuscript received October 23, 2015; final manuscript received June 22, 2016; published online October 12, 2016. Assoc. Editor: Dmitry Paramonov.

ASME J of Nuclear Rad Sci 2(4), 044505 (Oct 12, 2016) (6 pages) Paper No: NERS-15-1221; doi: 10.1115/1.4034144 History: Received October 23, 2015; Accepted July 02, 2016

In the Czech Republic, as a follow-up, a consortium of research organizations and universities has decided to simulate selected stress tests’ scenarios, in station blackout (SBO) and the loss of ultimate heat sink (LoUHS), with the aim to verify the national stress report and to analyze time response of respective source term releases. These activities are carried out in the frame of the project prevention, preparedness, and mitigation of consequences of severe accident (SA) at Czech NPPs in relation to lessons learned from stress tests after Fukushima, financed by the Ministry of Interior. The Research Centre Rez has been working on a methods for estimation of leakages and consequences of releases (MELCOR) model for VVER1000 nuclear power plant (NPP) starting with a plant systems nodalization. The aim was to benchmark the MELCOR model with the validated TRAC/RELAP advanced computational engine (TRACE) model, first comparing the steady state and continuing in a long-term SBO plus another event until the beginning of the SA. The presented work is based on the previous paper from the ICONE 23rd Conference hosted in Japan. It focuses mainly on the comparison of the thermohydraulics of the two models created in MELCOR and TRACE codes as outcome of the “Fukushima project.” After that, preliminary general results of the SA progression showing the hydrogen production and the relocation phenomena will be shortly discussed. This scenario is considered closed after some seconds to the break of the lower head. It is important to note that this paper is a substantial update of a previous one (Mazzini et al., 2015, “Analyses of SBO Sequence of VVER1000 Reactor Using TRACE and MELCOR Codes,” 23rd International Conference on Nuclear Engineering (ICONE23)) and although it contains the same descriptive sections, all the results are new.

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References

Figures

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Fig. 1

TRACE RVP nodalization

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Fig. 2

MELCOR RVP nodalization

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Fig. 3

SG water mass inventory

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Fig. 5

Temperature of steam in SG

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Fig. 6

SG-SRV integral flow

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Fig. 8

Hot leg temperature

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Fig. 10

RPV water mass inventory

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Fig. 11

PORV integral flow

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Fig. 12

Max fuel temperature

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Fig. 13

Total hydrogen production

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Fig. 14

H2 production from B4C

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