Calculational study of thermomechanical characteristics of fuel elements for power reactors
Description
The nonstationary thermomechanical model of a fuel rod with compacted UO2 is suggested. The TEMPO program (FORTRAN, BESM-6 computer) developed on the basis of this model is described. The program gives an opportunity to calculate the fuel element parameters (temperature profiles in the fuel and can, the value of the fuel rod-can gap, the gap contact heat transfer, the fuel cracking level, fuel structure change, the fuel contact pressure on the can, fuel rod and can axial elongations, distributions of strains in the fuel and can, gas pressure inside the fuel can) under stationary and transient operational conditions. The conclusion is made that the model under consideration provides correct calculation of the complex of parameters characterizing the WWER and RBMK type reactor fuel element reliability
Availability note (English)
MF available from INIS under the Report Number.Files
15010197.pdf
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Additional details
Additional titles
- Original title (Russian)
- Расчетное исследование термомеханических характеристик твэлов энергетических реакторов
Publishing Information
- Imprint Pagination
- 23 p.
- Report number
- IAE--3564/4
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 15010197
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALGORITHMS; BESM COMPUTERS; BOUNDARY CONDITIONS; COMPUTER CALCULATIONS; ELONGATION; FLOWSHEETS; FORTRAN; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; LWGR TYPE REACTORS; MATHEMATICAL MODELS; NUCLEAR FUELS; REACTOR OPERATION; RELIABILITY; STRAINS; T CODES; TEMPERATURE DISTRIBUTION; TRANSIENTS; URANIUM DIOXIDE; VERY HIGH TEMPERATURE; WWER TYPE REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; COMPUTERS; DEFORMATION; DIAGRAMS; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; GRAPHITE MODERATED REACTORS; INFORMATION; MATERIALS; OPERATION; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PROGRAMMING LANGUAGES; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 20 refs.; 10 figs.