• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.415-416
• /
• 2004

• Proceedings of the Korean Nuclear Society Conference
• /
• 2004.10a
• /
• pp.180-181
• /
• 2004

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.05a
• /
• pp.105.1-105
• /
• 2001

• Proceedings of the Korean Nuclear Society Conference
• /
• 1999.05a
• /
• pp.55-55
• /
• 1999

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.05a
• /
• pp.599-600
• /
• 2005

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.10a
• /
• pp.153-153
• /
• 1998

• Proceedings of the Korean Nuclear Society Conference
• /
• 2005.10a
• /
• pp.123-124
• /
• 2005

• Nuclear Engineering and Technology
• /
• v.30 no.6
• /
• pp.592-608
• /
• 1998

Inspection of RCS flow measurements for the domestic pressurized water reactors has been performed by the Korea Institute of Nuclear Safety (KINS) as one of the authorized periodical inspection activities. The inspection results for the Westinghouse-type plants reveal that 1) the RCS flow instrumentation has been calibrated by using the initial design and commissioning test result, without reflecting the cycle specific reference flow measurements, 2) the loop-to-loop now variation in the actual flow measurement which has not been considered in the safety analysis affects the asymmetric How transient results, and 3) the measured RCS flows in Kori 3 and 4, Yonggwang 1 and 2 do not support the definition of the best estimate RCS flow, approaching the RCS flow limit. In this study, the revealed problems were discussed with review of the design and the RCS flow measurement uncertainty evaluation, and the technical approaches and recommendations for resolving these problems were proposed.

• Nuclear Engineering and Technology
• /
• v.51 no.4
• /
• pp.963-967
• /
• 2019

Accurate measurement of the reactivity worth of safety rods is very important for the safe reactor operation, in normal and emergency conditions. In this paper, the reactivity worth of safety rods in Heavy Water Zero Power Reactor (HWZPR) in the new lattice pitch is measured by advanced source jerk method. The average of the results related to two different detectors is equal to 29.88 mk. In order to verify the result, this parameter was compared to the previously measured value by subcritical to critical approach. Different experiment results are finally compared with corresponding calculated result. Difference between the average experimental and calculated results is equal to 2.2%.

• Nuclear Engineering and Technology
• /
• v.50 no.7
• /
• pp.997-1005
• /
• 2018

The regulatory periodic safety inspection system is one of the most important methods for confirming the safety of nuclear power plants and the defense in depth in nuclear safety is the most important basic means for accident prevention and mitigation. Recently, a new regulatory technology based on risk-informed and safety performance has been developed and used in advanced countries. However, since the domestic periodic inspection system is being used in the same way over 30 years, it is necessary to know how the inspection contributes to the safety confirmation of the nuclear power plants. In this study, the domestic periodic inspection system currently in use was analyzed from the perspective of defense in depth in nuclear safety. In addition, the analysis results were compared to the U.S. NRC's safety inspection system to obtain consistency and lessons in this study. As a result of analysis, the NRC's safety inspections were distributed almost evenly at the all levels of defense in depth, while in the case of domestic inspection, they were heavily focused on the level 1 of defense in depth. Therefore, it appeared urgent to improve the inspection system to strengthen the other levels of defense in depth in nuclear safety.