Title BWR reaktoriaus panaudoto branduolinio kuro išlaikymo baseino termohidraulinių procesų studija /
Translation of Title Study of thermal-hydraulic processes in the spent nuclear fuel storage of the BWR reactor.
Authors Graževičius, Audrius
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Pages 62
Keywords [eng] pool ; fuel ; nuclear
Abstract [eng] The pool is filled 3828 bundles of various ages in high and low – density racking. Thermal power of spent fuel pool for low – density racking is 2526 and 3143 kW, for high – density racking is 2952 and 3567 kW. And the most important accident (cooling and cleaning system accident) was modeled with 6688 kW thermal power. The initial cooling water temperature is 31℃. The study showed that in the worst scenario cooling water to boil-up at 18 hour after cooling and cleaning system accident, the spent nuclear fuel to uncover after 106 hours. Also, in this study was investigated the natural circulation phenomena in the spent fuel pool then him is loaded various age and thermal power spent fuel bundles.
Dissertation Institution Kauno technologijos universitetas.
Type Master thesis
Language Lithuanian
Publication date 2015