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ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION

JOSIP ĐAKOVIĆ   ORCID icon 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 (2 MB) str. 0-0 preuzimanja: 35* citiraj
APA 6th Edition
ĐAKOVIĆ, J. i GRGIĆ, D. (2017). ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION. Journal of Energy, 66 (1-4), 0-0. Preuzeto s https://hrcak.srce.hr/199743
MLA 8th Edition
ĐAKOVIĆ, JOSIP i DAVOR GRGIĆ. "ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION." Journal of Energy, vol. 66, br. 1-4, 2017, str. 0-0. https://hrcak.srce.hr/199743. Citirano 26.05.2020.
Chicago 17th Edition
ĐAKOVIĆ, JOSIP i DAVOR GRGIĆ. "ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION." Journal of Energy 66, br. 1-4 (2017): 0-0. https://hrcak.srce.hr/199743
Harvard
ĐAKOVIĆ, J., i GRGIĆ, D. (2017). 'ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION', Journal of Energy, 66(1-4), str. 0-0. Preuzeto s: https://hrcak.srce.hr/199743 (Datum pristupa: 26.05.2020.)
Vancouver
ĐAKOVIĆ J, GRGIĆ D. ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION. Journal of Energy [Internet]. 2017 [pristupljeno 26.05.2020.];66(1-4):0-0. Dostupno na: https://hrcak.srce.hr/199743
IEEE
J. ĐAKOVIĆ i D. GRGIĆ, "ANALYSIS OF SPENT FUEL POOL LOSS OF COOLANT INVENTORY ACCIDENT PROGRESSION", Journal of Energy, vol.66, br. 1-4, str. 0-0, 2017. [Online]. Dostupno na: https://hrcak.srce.hr/199743. [Citirano: 26.05.2020.]

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

Posjeta: 69 *