U-PuO2, U-PuC, U-PuN cermet fuel for fast reactor
| Autor: | Joydipta Banerjee, Santu Kaity, K.B. Khan, G.K. Dey, Chiranjeet Nandi, Sudhir Mishra |
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| Rok vydání: | 2018 |
| Předmět: |
Nuclear and High Energy Physics
Materials science 020209 energy Metallurgy 02 engineering and technology Cermet Solidus 01 natural sciences Thermal expansion 010305 fluids & plasmas Nuclear Energy and Engineering visual_art Powder metallurgy Differential thermal analysis 0103 physical sciences 0202 electrical engineering electronic engineering information engineering visual_art.visual_art_medium General Materials Science Dilatometer Ceramic Diffractometer |
| Zdroj: | Journal of Nuclear Materials. 499:272-283 |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/j.jnucmat.2017.11.010 |
| Popis: | Cermet fuel combines beneficial properties of both ceramic and metal and attracts global interest for research as a candidate fuel for nuclear reactors. In the present study, U matrix PuC/PuN/PuO2 cermet for fast reactor have been fabricated on laboratory scale by the powder metallurgy route. Characterization of the fuel has been carried out using Dilatometer, Differential Thermal analysis (DTA), X-ray diffractometer and Optical microscope. X ray diffraction study of the fuel reveals presence of different phases. The PuN dispersed cermet was observed to have high solidus temperature as compared to PuC and PuO2 dispersed cermet. Swelling was observed in U matrix PuO2 cermet which also showed higher thermal expansion. Among the three cermets studied, U matrix PuC cermet showed maximum thermal conductivity. |
| Databáze: | OpenAIRE |
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