Mechanical damage experience in major light water reactor systems
Creators
- 1. Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID (USA)
Description
This paper describes the nuclear power industry's experience with mechanical (as opposed to thermal or electrochemical) damage in the major systems of light water reactor (LWR) plants. Almost all of the occurrences of damage were caused by mechanical vibration. The sources of vibration include flow-induced vibration, water-hammer events, and pump and valve vibration. However, the damage has sometimes been initiated or aggravated by other sources, such as stress corrosion cracking, loss of preload, or corrosion-fatigue. Mechanical vibration can also cause metal loss in the walls of thin tubes when they impact with their supports. Some of the components that have experienced mechanical damage are reactor coolant pump shafts, PWR and BWR reactor vessel internals, PWR instrument tubes, thermal sleeves in piping, and steam generator tubes. Various mitigation methods can e implemented to reduce or eliminate these problems
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (USA)
- ISBN
- 0-7918-0511-5
- Imprint Title
- Advances in dynamics of piping and structural components
- Imprint Pagination
- 83 p.
- Journal Page Range
- p. 7-14.
Conference
- Title
- 1990 pressure vessels and piping conference.
- Dates
- 17-21 Jun 1990.
- Place
- Nashville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22056078
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; HAZARDS; MECHANICAL VIBRATIONS; PIPES; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; TUBES
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900617--.