Published February 1980 | Version v1
Journal article

Model of the mechanical behaviour of a PWR fuel element

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. des Reacteurs a Eau
  • 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Div. d'Etudes et de Developpement des Reacteurs

Description

Irradiated fuel in pressurized water reactors (PWRs) frequently displays rod bowing, due to two kinds of assymmetry. The first originates in the fabrication of the sheath, causing eccentricity, ovalization and thickness non-uniformity. The other comes from in-pile fuel element conditions such as off-line grids compressing the rods, circumferential thermal gradients on the sheath, and pellet-clad interactions. The MAC code was developed for parametric studies of some of these effects. It shows that: In the case of fuel rods undergoing compressive forces by the spacer grids the usual friction forces are unable to bow the rods significantly, except when the rods are blocked by the spacer grid springs. In some assembly configurations, the temperature difference between adjacent rods is able to bow them, requiring an increase in number of spacer grids. Localized pellet-clad interactions may cause significant bowing, particularly when they occur near the grids. (orig.)

Additional details

Additional titles

Original title (French)
Modele de comportement mecanique d'element combustible dans un assemblage PWR

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
56
Journal Issue
1
Series
Nucl. Eng. Des.
Journal Page Range
105-116
ISSN
0029-5493

Conference

Title
IAEA specialists' meeting on fuel element performance computer modelling.
Dates
13 - 17 Mar 1978.
Place
Blackpool, UK.

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
11532048
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; DEFORMATION; FUEL RODS; FUEL-CLADDING INTERACTIONS; M CODES; MECHANICAL PROPERTIES; PWR TYPE REACTORS; SIMULATION
Descriptors DEC
COMPUTER CODES; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS