Open AccessCreep analysis of fuel plates for the Advanced Neutron Source
Author(s) -
W. F. Swinson,
G.T. Yahr
Publication year - 1994
Language(s) - English
Resource type - Reports
DOI - 10.2172/43782
Subject(s) - creep , enriched uranium , nuclear fuel , materials science , deformation (meteorology) , nuclear engineering , nuclear reactor core , neutron , uranium , core (optical fiber) , nuclear reactor , neutron source , composite material , nuclear physics , metallurgy , engineering , physics
The reactor for the planned Advanced Neutron Source will use closely spaced arrays of fuel plates. The plates are thin and will have a core containing enriched uranium silicide fuel clad in aluminum. The heat load caused by the nuclear reactions within the fuel plates will be removed by flowing high-velocity heavy water through narrow channels between the plates. However, the plates will still be at elevated temperatures while in service, and the potential for excessive plate deformation because of creep must be considered. An analysis to include creep for deformation and stresses because of temperature over a given time span has been performed and is reported herein