실험계획법을 이용한 원자력 발전소에서의 냉각제 상실사고에 대한 연구

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

  • 임영문 (강릉대학교 산업시스템공학과) ;
  • 이성모 (울진원자력발전소 안전과)
  • 발행 : 2005.10.01

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).

키워드