Published March 1982 | Version v1
Journal article

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