Published 1989
| Version v1
Book
Thermomechanical analysis of a steam generator bottom
Description
A defect has been detected in a steam generator (SG) bottom. It was located in the area of the weld joining the channel head, the tube plate and the partition plate. To estimate the nocivity of this defect, it is necessary to perform a 3D thermomechanical analysis by F.E.M. of the whole SG bottom. This study examines the mechanical behavior of this component under transient thermal and pressure loadings. The computed stress distribution in the SG can then make up a data base for any kind of investigation or crack propagation analysis
Additional details
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 257 p.
- Series
- LWR pressure components.
- Journal Page Range
- p. 233-238.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076235
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; FRACTURE MECHANICS; REACTOR SAFETY; STEAM GENERATORS; TRICASTIN-4 REACTOR; ULTRASONIC TESTING
- Descriptors DEC
- ACOUSTIC TESTING; BOILERS; ENRICHED URANIUM REACTORS; MATERIALS TESTING; MECHANICS; NONDESTRUCTIVE TESTING; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.