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ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION

JOSIP ĐAKOVIĆ orcid id orcid.org/0000-0002-3214-5197 ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, 10000 Zagreb, Croatia
DAVOR GRGIĆ ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, 10000 Zagreb, Croatia


Puni tekst: engleski pdf 1.673 Kb

preuzimanja: 346

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Sažetak

The Spent Fuel Pool (SFP) in a nuclear power plant is a robust structure
designed to withstand large seismic loads. After the terrorist attacks on September
11 and the accident in the Fukushima nuclear power plant, special attention was
focused on safety assessments and taking measures to mitigate possible accidents
related to the spent fuel pool. This paper will provide an insight into spent fuel pool
loss of coolant phenomenology and consequence mitigation strategies. Model of NPP
Krško SFP was presented in MELCOR code which has been used as a case-study for
evaluating accident propagation. The calculations were carried out using the latest
version of MELCOR code which was updated for the analysis of severe accidents in
nuclear spent fuel pools.

Ključne riječi

Spent Fuel Pool; Loss of Coolant accident; fuel heatup, cladding oxidation, decay heat, NPP Krško

Hrčak ID:

199743

URI

https://hrcak.srce.hr/199743

Datum izdavanja:

15.12.2017.

Posjeta: 920 *