Theoretical and experimental studies on bellows type expansion joints behaviour of Chinon 3 primary coolant system
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service des Etudes Mecaniques et Thermiques
- 2. Electricite de France, 75 - Paris. Direction de la Production et du Transport
- 3. Electricite de France, 75 - Paris. Direction des Etudes et Recherches
Description
The vibration study of the bellows was performed in two stages. A series of vibration tests was performed on a real bellow joint. By comparing the experimental results with calculations using the finite elements method for revolution shells it was possible to qualify the representation of the waves and reinforcement rings. The resonant frequencies and modes were calculated for the various joints under reactor conditions. According to the excitation sources considered, the amplitude of the displacements and stresses can be determined from these characteristic modes. The corrugations are protected internally from the aerodynamic effects of the gas flow by an inner sleeve welded to the primary piping upstream and free downstream. The annular space between this sleeve and the corrugations forms a resonant volume liable to be excited by flow-induced pressure fluctuations. It was possible to calculate the characteristic resonance frequencies and modes of this gas column (air at normal temperature and pressure). A full-scale mock-up test under conditions corresponding to the calculation hypotheses gave experimental proof of the calculation results. Owing to the good correlation between the results of these two studies an attempt was made to calculate the acoustical behaviour of these cavities for nominal running conditions (temperature and pressure) as a function of the known excitation sources. The results obtained from all these tests show that the use of bellows type expansion joints on a primary reactor circuit offers the same guarantees of reliability and resistance as any other circuit component under pressure, as long as the strains they undergo remain within the limits specified by the regulations and nuclear codifications
Availability note (English)
MF available from INIS under the Report Number.Additional details
Publishing Information
- Imprint Pagination
- F 6/6, 9 p.
- Report number
- INIS-mf--2084
Conference
- Title
- 3. International conference on structural mechanics in reactor technology.
- Dates
- 01 Sep 1975.
- Place
- London, UK.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 7240986
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHINON-3 REACTOR; FATIGUE; MECHANICAL VIBRATIONS; PERFORMANCE TESTING; PIPE JOINTS; PRIMARY COOLANT CIRCUITS; STRESS ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; GAS COOLED REACTORS; GCR TYPE REACTORS; GRAPHITE MODERATED REACTORS; JOINTS; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS