Published 1977 | Version v1
Book

Spacers for fuel elements as structural anisotropic plates composed of cylindrical shells

Creators

  • 1. National Research Institute for Machine Design, SVUSS, 250 97 Prague 9-Bechovice, Czechoslovakia

Description

Fuel rods are kept at given distances by means of spacer components. During reactor operations the spacers are subject to a number of temperature and force effects which may cause a failure. The quantitative evaluation of theses effects and their consequences is necessary for the elaboration of a successful design of the spacer components. In this paper the results of investigations concerning the state of stress in the spacers which are assumed to be 'structural anisotropic plates composed of cylindrical shells' (below: 'plates' only), as well as the behaviour of the spacers in the interactions with fuel elements are presented. A method is developed whereby the deformations and stresses in mentioned plates can be computed. An application of the developed method-including its experimental verification-from the region of spacers for nuclear reactors is shown. The agreement between the theoretical results and experimental ones is reasonably good. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85062 7
Imprint Title
Structural mechanics in reactor technology
Journal Page Range
v. D p. D3/2 1-17.

Conference

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

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
10430692
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANISOTROPY; BOUNDARY CONDITIONS; CYLINDRICAL CONFIGURATION; DEFORMATION; FUEL ASSEMBLIES; FUEL RODS; MATRICES; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; PLATES; SHELLS; SPACERS; STRESSES; THERMODYNAMIC PROPERTIES
Descriptors DEC
CONFIGURATION; FUEL ELEMENTS; PHYSICAL PROPERTIES; REACTOR COMPONENTS