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Additional resources for Carbon-Carbon Composite Molten-Salt Cooled Space Reactors [short article]
The mass of tested fuel was 8-12 g, the exposure time at each temperature was 120 min. The measuremets of FP in argon, nitrogen and steam have been performed using a semiconductor gamma spectrometer and gas radiochromatography. Porous zirconium and aluminium oxides were used for the solid FP deposition from gas environment. 4-7. ' "i ^ ^ - ^ - - - - x - •w\ J -V^ \ u] \ 'J? O , H-UJ ft -~ j >" rv (V H> . » P. '. iv i- • f » c f u e l c o m•* p o s i t i o n 3 of " J '0 - -1 ,0 jf -^ • H- of fuel composition CD CD t* i O CD O OS 00 ui s if CD CD P> CO (0 4 ft) M CD The release of caesium-137 from fuel in vironments (burning- 20,8 Mw day/kg).
In order to simplify the numerical calculations, the fuel element was divided into N=5 concentric cylinders, in each of which the temperature was considered constant. The equation for T(r) was solved for the radial coordinates of the boundaries between the zones. The mean value of the temperature in each zone was then determined and assigned to the zone. Results With the procedure outlined above, several experiments were reproduced. At first, a series of isothermal experiments performed by Zimmermann [8 ] were simulated, which made possible to select the more appropnate set of parameters of the model.
A. MELNICHENKO Institute of Physics and Power Engineering, State Scientific Centre of the Russian Federation, Obninsk, Russian Federation Abstract The out-of-pile experiment results on interaction of the cladding and matrix materials and uranium dioxide at cermet fuel temperature for normal operating conditions of the WWER-440 reactor are analysed. Cermet fuel element behaviour under the maximum designed damage of the WWER-440 reactor is considered. In the AM reactor loop a fission product output from the unsealed cermet fuel elements have been studied.