Integral Material Studies of Nuclear Fuel at Institute of Reactor Materials
| Autor: | M. V. Chernetsov |
|---|---|
| Rok vydání: | 2017 |
| Předmět: |
Materials science
Nuclear fuel 020209 energy Nuclear engineering Metallurgy chemistry.chemical_element 02 engineering and technology Nitride Uranium Microstructure Carbide Shear modulus chemistry.chemical_compound Nuclear Energy and Engineering chemistry 0202 electrical engineering electronic engineering information engineering Uranium carbide Radiation resistance |
| Zdroj: | Atomic Energy. 121:255-258 |
| ISSN: | 1573-8205 1063-4258 |
| DOI: | 10.1007/s10512-017-0193-4 |
| Popis: | Survey information on integral material studies of advanced fuel compositions performed at the Institute of Reactor Materials over a period of 50 years is presented. The influence of the reactor testing conditions on the radiation resistance of different forms of nuclear fuel was investigated: oxide, carbide, nitride, carbosulfide, and some of their compounds. Uranium oxides possessed a different initial microstructure and were doped with the oxides Y2O3, TiO2, Sc2O3, and others. Carbide fuel was tested in the form of solid solutions of uranium carbide with Zr, Nb, and Ta carbides. The dimensional, phase, and structural stability of fuel compositions were studied in hot boxes; the electrophysical and mechanical properties, such as strength in compression and bending, Young’s modulus, the shear modulus, and Poisson’s ratio were investigated. The experimental data on the radiation resistance of advanced fuel compositions formed the basis for the validation of the serviceability of different nuclear reactors. |
| Databáze: | OpenAIRE |
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