Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.019 seconds
Barzegari, M.; Aghaie, M.; Zolfaghari, A., E-mail: M_Aghaie@sbu.ac.ir2019
AbstractAbstract
[en] After the Fukushima disaster, interest in the evaluation of severe accidents in nuclear power plants and off-site consequences has significantly increased. Because experimental studies are difficult to conduct, computational methods play a substantial role in accident analysis. In this study, a severe accident in the Bushehr pressurized water reactor power plant caused by a station blackout with a total loss of alternating current power supply has been evaluated. This analysis presents the in-core damage of fuel rods and the release of fission products as well as the thermal hydraulic response of the station components during the loss of active emergency cooling systems. In this manner, a perfect model of the Bushehr nuclear power plant using the MELCOR code is prepared. The accident progression is simulated, and the thermal responses of the fuels and hydraulic components are presented. It is shown that, without operator intervention, steam generators will become dry in approximately 3000 s, and the heat sink of the reactor will be lost. The simulation results show that at approximately 8600 s, the upper parts of the core start melting. This model calculates the shortest available time for accident prevention and proves that the time available is sufficient for operator manual action to prevent a nuclear disaster.
Primary Subject
Source
Copyright (c) 2019 China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Country of publication
ACCIDENTS, BEYOND-DESIGN-BASIS ACCIDENTS, BOILERS, CURRENTS, ELECTRIC CURRENTS, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, FUEL ELEMENTS, HYDRAULICS, MECHANICS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR SITES, REACTORS, SEVERE ACCIDENTS, SINKS, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue