Analysis of bellows expansion joints in the Sequoyah containment
- Ames Lab., IA (United States)
Bellows expansion joints are an integral part of the containment building pressure boundary in some nuclear power plants. They are used at piping penetrations to minimize the loadings on the containment shell due to differential movement between the shell and piping. The purpose of this study was to investigate bellows behavior in the unlikely event of a severe accident inside the containment building. The study began with a survey of available information on bellows design, analysis, and past test programs. This information was then used to assess the ultimate behavior of the bellows in the Sequoyah containment. It was determined that the bellows at penetration X-47 in the Sequoyah containment would experience the worst loading conditions during a severe accident. Finite element calculations of bellows X-47 were conducted to examine the deformation and resulting strains caused by the combination of axial compression, lateral offset, bending, and internal pressure that would be applied to the bellows during a severe accident. Because of covergence problems, the analyses could not be continued to a point of obvious bellows failure. However, large inelastic bending stains, up to 8%, were calculated. A test program to determine the ultimate bellows behavior and develop data for validation of analytical methods is recommended.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Sandia National Labs., Albuquerque, NM (United States); Ames Lab., IA (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6032276
- Report Number(s):
- NUREG/CR-5561; SAND--90-7020; ON: TI92005371
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BELLOWS
COMPRESSION
CONTAINMENT
CONTAINMENT SYSTEMS
DEFORMATION
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EXPANSION JOINTS
FINITE ELEMENT METHOD
JOINTS
MECHANICAL STRUCTURES
NUMERICAL SOLUTION
PIPES
POWER REACTORS
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTORS
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS