비파괴검사학회지 (Journal of the Korean Society for Nondestructive Testing)
- 제12권2호
- /
- Pages.14-20
- /
- 1992
- /
- 1225-7842(pISSN)
- /
- 2287-402X(eISSN)
배관해석에 의한 원전 배관부의 검사부위 선정
Careful Determination of Inservice Inspection of piping by Computer Analysis in Nuclear Power Plant
초록
Stress analysis has been performed using computer program ANSYS in the pressurizer surge line in accordance with ASME Sec. III in order to predict possibility of fatigue failure due to thermal stratification phenomena in pipes connected to reactor coolant system of nuclear power plants. Highly vulnerable area to crack generation has been chosen by the analysis of fatigue due to thermal stress in pressurizer surge line. This kind of result can be helpful to choose the location requiring intensive care during inservice inspection of nuclear power plants.
키워드