Published 1989 | Version v1
Journal article

Field measurement of the piping system vibration of Ko-Ri unit 4 during the load-following operation

Description

During the load-following operation of nuclear power plants, flow rate, temperature, and pressure in the piping system can be varied by changing the electric power output level, and these variations can cause different vibration phenomena in the piping system. The piping system vibration is important because it is directly related to the dynamic stress of the piping system and can affect the life of the piping system through structural fatigue. An assessment of vibration levels for the classes II and III piping systems of the Ko-Ri Unit 4950-MW nuclear power plant was performed according to the given pattern of the load-following operation to study its feasibility from the viewpoint of piping system vibration. The classes II and III piping system vibration of the Ko-Ri Unit 4 may not cause any potential problem under the given pattern of the load-following operation; however, it is recommended that long-term operation in the 85 to 95% power range be avoided as much as possible

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
59
Series
Trans. Am. Nucl. Soc.
Journal Page Range
311-312
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
4-8 Jun 1989.
Place
Atlanta, GA (USA).

Optional Information

Secondary number(s)
CONF-890604--.