Published 1982 | Version v1
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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.

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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

Optional Information

Notes
20 refs.; 10 figs.