Abstracts and Available Papers Presented at the
1997 International RERTR Meeting

TESTS OF EXPERIMENTAL FUEL ELEMENTS BY THE METHOD OF NUCLEAR-THERMAL PULSE LOADINGS IN "HYDRA" REACTOR

O. V. Nastoyashchaya, Yu. M. Lebedev, A. M. Chechurov, Ye. Khvostionov

Institute of Nuclear Reactors
Russian Research Center "Kurchatov Institute"
Kurchatov sq., 1 Moscow. 123182, Russia

ABSTRACT

The results of tests of experimental fuel elements with uranium dioxide fuel composition embedded in Al and Zr matrix with the enrichment from 90% to 36% in respect to U-235 performed at the pulse <<HYDRA>> reactor are presented in this paper. Testing is performed in the frame-work of extensive research program studying the behavior of fuel elements (FE) of research and mini nuclear power systems in case of practically immediate energy release in the fuel taking place during the RIA-type accidents. Duration of the neutron pulse when testing in <<HYDRA>> reactor is from 7 to 20 ms.

The methods of diagnostics of the state of FE prior to and after testing in the reactor are developed and verified. Mathematical model describing temperature fields inside the FE in the process of testing. and accounting for non-uniformity of fuel composition has been developed in order to summarize experimental results. Experimental data on the limiting values of the energy density leading to deformation and degradation of FE depending on the type of fuel compositeon have been obtained and the mechanisms for the development of these processes have been determined. The nature of physical-chemical processes taking place in the fuel composition and fuel cladding depending on material composition under different levels of energy deposition is demonstrated. The data on hydrogen generation and radioactive product release out of fuel after failure of FE are presented.

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