A hydro-thermo-mechanics analyze of the thermal fatigue in the mixing tee junction
Creators
- 1. CEA Saclay, Dir. de l'Energie Nucleaire, (DEN/DM2S/SEMT/LISN), 91 - Gif sur Yvette (France)
- 2. CEA Saclay, Dir. de l'Energie Nucleaire (DEN/DM2S/SFME/LTMF), 91 - Gif sur Yvette (France)
- 3. Institut de Radioprotection et de Surete Nucleaire (IRSN/DES/SAMS), 92 - 92 - Fontenay aux Roses (France)
Description
Work presented here, has been achieved at Cea, and is related to the comprehension of the mechanisms leading to cracking under thermal loading in the zones of mixing. The main objective of this work is to analyze, by computation, the thermal loading induced by the turbulent mixing following a tee junction and to explain how it can create cracking, from the internal skin of the component to a leakage, as it was observed in Civaux Power Plant in 1998. The phenomenon is still today not completely understood. One of the principal reasons to this partial incomprehension undoubtedly resides in the multi-field aspect of the loading and of the associated damage, utilizing three different and complementary scientific disciplines: thermohydraulics, thermomechanics and material science. The presentation proposed here, consists in connecting the analyses resulting from these various fields. The first part concentrates on thermohydraulics simulations. The choice of an adequate modeling is discussed on the basis of observed cracking in order to highlight phenomena of large scale beats, which are supposed one of the major causes leading to the failure of the structures. The second part deals with the use of the temperature fields obtained in the first part in order to carry out thermomechanical simulations. All these simulations are 3-dimensional and represent the complex geometry of Civaux RRA piping line, including a tee junction and elbows, water flow velocity. Mean and temperatures variations, mean and stresses variations are also presented. As final results make it possible to determine a map of the damage associated with these complex thermal loading. (authors)
Availability note (English)
Available from INIS in electronic formFiles
35106364.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-FR--2726
Conference
- Title
- International conference on supercomputing in nuclear applications SNA'2003
- Dates
- 22-24 Sep 2003
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 35106364
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; CIVAUX-1 REACTOR; COMPUTERIZED SIMULATION; CRACK PROPAGATION; PIPE JOINTS; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION; THERMAL FATIGUE; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; FATIGUE; FLUID MECHANICS; HYDRAULICS; JOINTS; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.