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.Files
12616373.pdf
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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