Published 1990 | Version v1
Book

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).

Optional Information

Secondary number(s)
CONF-900617--.