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A Study on Loss of Coolant Accident in Nuclear Power Plant Using DOE

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대한안전경영과학회지 (Journal of Korea Safety Management & Science)
대한안전경영과학회 (Korea Safety Management & Science)
초록

The main objective of this paper is to search whether containment vessel's best pressure may increase until how long when loss of coolant accident (LOCA) happened in containment vessel of Ulchin nuclear power plant 1 and 2. Another goal of this research is to find the influential factors that increase containment vessel pressure. Model for this research is Ulchin nuclear power plant 1 with 10 cycles. Data were collected by simulator of Ulchin nuclear power plant 1 and design of experiment was used for data analysis. For the experiment, seven factors that are going to influence in containment vessel pressure were chosen. It was found that fatter which influences in early rise of containment vessel pressure after LOCA is only explosion size. Also, containment vessel's best pressure (3.74 bar.a) was much lower than limit (4.86 bar.a) of FSAR (Final Safety Analysis Report).

저자
  • 임영문 | Leem, Young-Moon
  • 이성모 | Lee, Sung-Mo