Published 1977 | Version v1
Miscellaneous

From Phenix to Super Phenix: mechanical structures assuring reactor vessel tightness at main sodium pump penetrations

  • 1. Societe Nationale d'Etude et de Construction de Moteurs d'Aviation (SNECMA), 75 - Paris (France)
  • 2. Compagnie d'Ingenierie pour les Reacteurs au Sodium (CIRNA), Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

Description

Even though the components of SUPER PHENIX are larger than those of PHENIX, there is no corresponding increase in available vessel height. Furthermore the SUPER PHENIX vessel does not possess a roof. For these reasons, original and patented solutions, which, nevertheless, take advantage of the experimental results and operating experience acquired with PHENIX, were sought. The most important parameters are: weights and sizes of various components; stresses transmitted to the structures differential displacements between the top and bottom positions of components; inclinations due to deformation of the deck; preservation of containment at places where components penetrate the deck. In the solution finally adopted, an elastic torus shaped ring, which forms a ball-and-socket type joint is used. A thin shell structure connects the bottom to the reactor internals in such a way as to permit both vertical and rotational displacements. The upper joint consists of: a bolted double flange system; flanged component; a torus with a gear tooth shape profile made of elastic material; leaktight bellows attached to both flanges. Studies and calculations have been completed with the realization of a 1/5 scale model of the upper torus ring. Displacement, and angular and axial stiffness measurements have confirmed the validity of the hypotheses. Moreover, even though the lower part is an extrapolation of PHENIX, full scale experimental tests have been carried out in sodium, reproducing the real displacements and forces that will be experienced in the reactor. Finally, the pumps will be tested with water; the suspension will be studied (investigation of relevant mechanical parameters, measurement of leaktightness with respect to the outside)

Availability note (English)

MF available from INIS under the Report Number.

Additional details

Publishing Information

Imprint Pagination
F 2/6, 12 p.
Report number
INIS-mf--4541

Conference

Title
4. International conference on structural mechanics in reactor technology.
Dates
15 - 19 Aug 1977.
Place
San Francisco, Calif., USA.

INIS

Country of Publication
European Commission (EC), Brussels (Belgium)
Country of Input or Organization
European Commission (EC), Brussels (Belgium)
INIS RN
10421462
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOLTED JOINTS; COMPARATIVE EVALUATIONS; CONTAINMENT; FLANGES; PHENIX REACTOR; PIPE FITTINGS; PUMPS; REACTOR VESSELS; SEALS; SHELLS; SUPER PHENIX REACTOR
Descriptors DEC
BREEDER REACTORS; CONTAINERS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; JOINTS; LIQUID METAL COOLED REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS