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Finite-element calculations of near-field transient horizontal temperature and thermal stress distributions for the Climax granite nuclear spent-fuel-storage experiment
Author(s) -
R.C. Greenlaw
Publication year - 1980
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/59206
Subject(s) - homogeneity (statistics) , thermal , plane stress , finite element method , ultimate tensile strength , spent nuclear fuel , stress (linguistics) , horizontal plane , materials science , mechanics , geology , structural engineering , engineering , nuclear engineering , physics , mathematics , composite material , geodesy , thermodynamics , linguistics , statistics , philosophy
Calculations of near-canister temperature and thermal stress fields in a horizontal plane through a typical spent nuclear fuel canister in the Climax granite experiment are presented, assuming homogeneity of the rock mass. The methodology is described. Three different canister spacings were investigated. The resulting temperature and stress plots show that a row of canisters may be satisfactorily approximated by a distributed plane source for points of interest which are at greater distances from the row than the canister spacing. Further, the thermal tensile stress changes are trivial and very much less than the calculated residual horizontal geostatic compressive stresses. A listing of the mesh-generator input is given for use in additional analyses

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