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Physical properties of monolithic U8wt.%–Mo
- Source :
- Journal of Nuclear Materials. 402:74-80
- Publication Year :
- 2010
- Publisher :
- Elsevier BV, 2010.
-
Abstract
- As a possible high density fuel for research reactors, monolithic U8 wt.%–Mo (“U8Mo”) was examined with regard to its structural, thermal and electric properties. X-ray diffraction by the Bragg-Brentano method was used to reveal the tetragonal lattice structure of rolled U8Mo. The specific heat capacity of cast U8Mo was determined by differential scanning calorimetry, its thermal diffusivity was measured by the laser flash method and its mass density by Archimedes’ principle. From these results, the thermal conductivity of U8Mo in the temperature range from 40 °C to 250 °C was calculated; in the measured temperature range, it is in good accordance with literature data for UMo with 8 and 9 wt.% Mo, is higher than for 10 wt.% Mo and lower than for 5 wt.% Mo. The electric conductivity of rolled and cast U8Mo was measured by a four-wire method and the electron based part of the thermal conductivity calculated by the Wiedemann-Frantz law. Rolled and cast U8Mo was irradiated at about 150 °C with 80 MeV 127I ions to receive the same iodine ion density in the damage peak region as the fission product density in the fuel of a typical high flux reactor after the targeted nuclear burn-up. XRD analysis of irradiated U8Mo showed a change of the lattice parameters as well as the creation of UO2 in the superficial sample regions; however, a phase change by irradiation was not observed. The determination of the electron based part of the thermal conductivity of the irradiated samples failed due to high measurement errors which are caused by the low thickness of the damage region in the ion irradiated samples.
- Subjects :
- Nuclear and High Energy Physics
Chemistry
Analytical chemistry
Atmospheric temperature range
Thermal diffusivity
Heat capacity
Laser flash analysis
Differential scanning calorimetry
Thermal conductivity
Nuclear Energy and Engineering
Electrical resistivity and conductivity
General Materials Science
Irradiation
Nuclear chemistry
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 402
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........c9ac26f1a2890861ad8d35e085934455
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2010.04.024