Calcul des distributions de temperature dans les plaques combustibles de BR2 avec decollement du gainage ou inclusion d'uranium pur

Research output: Report/book › BLG - Open report

Authors

R. De Meersman
Georges Minsart

Institutes & Expert groups

Neutron Calculations

SCK•CEN - Studiecentrum voor Kernenergie/Centre d’Etude de l’Energie Nucléaire

Documents & links

Documents

BLG-188
Final published version, 17.1 MB, PDF document

Abstract

The equations of the heat diffusion are solved with the help of a neutron diffusion code. This method is used for the study of two kinds of defects in the fuel plates of the BR2 reactor: cIad bonding defect and uranium inclusion . The corresponding hot spot factors are computed . Defects of circular and rectangular section are studied.

Details

Original language	English
Publisher	Studiecentrum voor Kernenergie
Number of pages	41
Publication status	Published - Dec 1962

Publication series

Name	SCK•CEN Reports
Publisher	Studiecentrum voor Kernenergie
No.	BLG-188

Keywords

ID: 6871546