Published March 1980 | Version v1
Report Open

Finite-element calculations of near-field transient horizontal temperature and thermal stress distributions for the Climax granite nuclear spent-fuel-storage experiment

Description

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

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Additional details

Publishing Information

Imprint Pagination
47 p.
Report number
UCID--18840

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12616373
Subject category
S42: ENGINEERING;
Descriptors DEI
A CODES; COMPUTER CALCULATIONS; CONTAINERS; SPATIAL DISTRIBUTION; SPENT FUEL STORAGE; THERMAL STRESSES
Descriptors DEC
COMPUTER CODES; DISTRIBUTION; STORAGE; STRESSES