• Proceedings of the Korean Society of Precision Engineering Conference
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• 2012.05a
• /
• pp.379-380
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• 2012

• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2011.06a
• /
• pp.493-494
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• 2011

• Proceedings of the Korean Society of Precision Engineering Conference
• /
• 2010.11a
• /
• pp.263-264
• /
• 2010

• Nuclear Engineering and Technology
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• v.48 no.5
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• pp.1174-1183
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• 2016

Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.