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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076201
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOAD MANAGEMENT; MECHANICAL VIBRATIONS; PIPES; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; STEADY-STATE CONDITIONS; STEAM; TRANSIENTS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890604--.