Analysis of bellows expansion joints in containment buildings
Creators
- 1. Ames Lab., IA (USA)
- 2. Sandia National Labs., Albuquerque, NM (USA)
Description
Failure of a containment building to perform its function takes place when a leak path is formed. Bellows expansion joints, that are used at the penetrations where piping systems penetrate the containment structures, are one of the potential points of failure. In the event of a severe accident, they can be simultaneously subjected to internal pressure, temperature and gross end displacements as the containment experiences large deformations. Current design and analysis criteria address bellows in only the small strain range. To understand its behavior during a severe accident, a universal bellows expansion joint in the Sequoyah containment vessel was analyzed for large displacements, and high pressures and temperatures. The bellows were analyzed with a three-dimensional finite element model using the ABAQUS finite element code. The model included rigid surfaces and interface elements to model the interaction of the convolutions as they touched each other. 3 refs., 6 figs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91009037; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- SAND--90-2236C
Conference
- Title
- 11. international conference on structural mechanics in reactor technology.
- Dates
- 18-23 Aug 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22085659
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ANNEALING; BELLOWS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DEFORMATION; DESIGN BASIS ACCIDENTS; EXPANSION JOINTS; FABRICATION; FAILURES; FINITE ELEMENT METHOD; INTERFACES; LEAKS; MATHEMATICAL MODELS; PIPES; PRESSURE DEPENDENCE; RELIABILITY; RESEARCH PROGRAMS; SANDIA LABORATORIES; SEQUOYAH-1 REACTOR; SEQUOYAH-2 REACTOR; SPECIFICATIONS; STRAINS; STRESSES; TEMPERATURE DEPENDENCE; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; JOINTS; NATIONAL ORGANIZATIONS; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SANDIA NATIONAL LABORATORIES; SIMULATION; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789; Contract 63-6131
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (USA).
- Secondary number(s)
- CONF-910817--4.