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