Temperature and wall strain fluctations during the TEMR thermal stratification tests at HDR
- 1. Battelle Institut e.V., Frankfurt (Germany, F.R.)
- 2. VTT Technical Research Centre of Finland, Espoo (Finland)
Description
A form of crack formation has been observed in a number of PWRs and BWRs on the internal surfaces of horizontal feedwater piping upstream of the steam generators and reactor pressure vessels. These cracks are caused by special loading conditions associated with certain operating transients under reduced feedwater mass flow. Under such conditions stratified flow develops and leads to the formation of a rather then, separating mixing layer with large temperature gradients between the cold water at the bottom and the hot water in the upper part of the pipe. To examine these stratification phenomena the HDR-test series TEMR, T33 /1/, has been performed. Under certain flow conditions the separating mixing layer between cold and hot fluid regimes performs wave-type oscillations subjecting the pipe inside surface in its vicinty to fluctuating thermal loads. The impact of this dynamic loading on pipe fatigue is the subject of this paper
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. 183-188.
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
- 21076116
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; HDR REACTOR; PIPES; REACTOR SAFETY; THERMAL FATIGUE; THERMAL STRESSES; THERMODYNAMICS
- Descriptors DEC
- BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FATIGUE; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRESSES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.