1. Irradiation-Induced Creep and Re-Sintering of Large Grain Sized UO2 Fuel.
- Author
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Mikheev, E. N., Fedotov, A. V., Rysev, N. M., Novikov, V. V., Bakhteev, O. A., Izhutov, A. L., Burukin, A. V., Seredkin, S. V., and Ilyinykh, G. A.
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GRAIN size , *GRAIN , *HIGH temperatures , *WOOD pellets - Abstract
A study of irradiation-induced creep and re-sintering of large grain sized fuel of the VVER type was carried out using the developed procedures and experimental facilities under irradiation with fission rates of 1.0 × 1013 and 1.2 × 1013 1/(cm3 s). Strain diagrams generated during creep studies within the strain range of 10−40 MPa were obtained at effective sample temperatures of 943, 1020, 1200 and 1301 K. It was demonstrated that strain is controlled by irradiation-induced creep within the temperature range of up to 1123 K. This was confirmed by its linear dependency on stress. At higher temperatures, the effect of radiation-thermal creep grows, and its contribution to the total strain increases with the growth of stress. Creep rate values obtained at temperatures of 1200 and 1301 K are higher than those of uranium dioxide with standard grain size. Strain diagram produced during the studies of re-sintering of an 88.32 mm high fuel column was obtained at the effective sample temperature of 960 K. In terms of height, re-sintering amounted to 0.070−0.095%. It was demonstrated that irradiation-induced re-sintering did not affect the irradiation-induced creep rate within the experimental accuracy range. [ABSTRACT FROM AUTHOR]
- Published
- 2022
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