U-PuO^sub 2^, U-PuC, U-PuN cermet fuel for fast reactor
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. Charac...
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| Veröffentlicht in: | Journal of nuclear materials 2018-02, Vol.499, p.272 |
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| container_title | Journal of nuclear materials |
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| creator | Mishra, Sudhir Kaity, Santu Banerjee, Joydipta Nandi, Chiranjeet Dey, GK Khan, KB |
| description | 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 diffractorneter 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, Ii matrix PuC cermet showed maximum thermal conductivity. |
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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 diffractorneter 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. 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| identifier | ISSN: 0022-3115 |
| ispartof | Journal of nuclear materials, 2018-02, Vol.499, p.272 |
| issn | 0022-3115 1873-4820 |
| language | eng |
| recordid | cdi_proquest_journals_2018028085 |
| source | Elsevier ScienceDirect Journals |
| subjects | Cermets Differential thermal analysis Dispersion Fast nuclear reactors Fuels Heat conductivity Metallurgy Nuclear fuels Nuclear reactors Powder Powder metallurgy Reactors Solidus Thermal analysis Thermal conductivity Thermal expansion |
| title | U-PuO^sub 2^, U-PuC, U-PuN cermet fuel for fast reactor |
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