Response of fast-reactor core subassemblies to pressure transients
- 1. Commission of the European Communities, Ispra (Italy). Joint Research Centre
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. des Reacteurs a Neutrons Rapides
Description
An Arbitrary Lagrangian-Eulerian (ALE) finite element method for analyzing the transient, nonlinear fluid-structure interaction in fast-reactor core subassemblies is presented. The method combines the basic attributes of the finite element technique-namely, ease in modeling complex geometries and in mixing fluid elements with structural elements - and the flexibility in moving the fluid mesh offered by the ALE description. The result of this combination is a very versatile modeling technique which permits accommodation of large fluid and structure displacements and logically simple, but accurate fluid-structure coupling. Numerical results are presented to illustrate the effectiveness of the proposed method. These include the response of a single hexagonal duct to internal, static or dynamic, pressure loading for which numerical predictions are compared to experimental data, and applications to clustered hexcans. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 68
- Journal Issue
- 2
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 153-174
- ISSN
- 0029-5493
Conference
- Title
- International seminar on internal loading and containment of fast breeder reactors (CONFABRE-3).
- Dates
- 24 - 25 Aug 1981.
- Place
- Ispra, Italy.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 13696019
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FBR TYPE REACTORS; FINITE ELEMENT METHOD; FLUID-STRUCTURE INTERACTIONS; FUEL ASSEMBLIES; NONLINEAR PROBLEMS; PRESSURE DROP; PRESSURE GRADIENTS; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; NUMERICAL SOLUTION; REACTORS; SAFETY