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FUEL BEHAVIOUR [1 record]

Record 1 - external organization data 2007-11-08

English

Subject field(s)
  • Nuclear Fission Reactors
  • Nuclear Power Stations
  • Compartment - Canadian Nuclear Safety Commission
CONT

The nuclear industry standard codes for modelling fuel behaviour during normal operation and a LOCA [loss of coolant accident] or LOR [loss of regulation] event are based on a 1D axi-symmetric model of a fuel element, in which the end cap is not modelled in detail.

French

Domaine(s)
  • Réacteurs nucléaires de fission
  • Centrales nucléaires
  • Tiroir - Commission canadienne de sûreté nucléaire
CONT

Les codes de normalisation de l'industrie du nucléaire pour la modélisation du comportement du combustible durant l'exploitation normale et lors d'un APRP [accident de perte de réfrigérant primaire] ou d'une PCR [perte de contrôle de la réactivité] sont fondés sur un modèle axisymétrique des éléments de combustible, dans lequel le bouchon d'extrémité n'est pas modélisé de manière détaillée.

Spanish

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