Stress analysis in piping connection thermal sleeves - some design criteria
Description
A statement of the problems that present piping connections subjected to sudden cooling has been made, emphasizing the importance of a suitable choise of the design to reduce thermal stresses. The analysis methodology has also been explained by means of finite element programs. The application to two specific thermal sleeve cases has permitted discussion of the results in the most critical sections and locations. On modifying the dimensions of one of them, the impact on thermal stresses has been verified, proving that it is significant only as far as fatigue is concerned. The stress values obtained are very high, making the simplified elastoplastic procedure necessary. Even after this, the results are very near the admissible limits. This means that in even more critical cases than those considered above, design validation would require a stress analysis based on plastic behavior. (orig.)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-767-0
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. F
- Imprint Pagination
- 419 p.
- Journal Page Range
- p. 379-384.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19045619
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; FINITE ELEMENT METHOD; MESH GENERATION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; SLEEVES; STRESS ANALYSIS; STRESS INTENSITY FACTORS; TEMPERATURE DEPENDENCE; THERMAL CYCLING; THERMAL FATIGUE; THERMAL STRESSES
- Descriptors DEC
- COOLING SYSTEMS; DEFORMATION; ENRICHED URANIUM REACTORS; FATIGUE; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS