Published 1975 | Version v1
Report

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