Imitators of plutonium and americium in a mixed uranium- plutonium nitride fuel
| Autor: | D P Shornikov, B A Tarasov, S N Nikitin, V. G. Baranov, M A Burlakova |
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| Rok vydání: | 2016 |
| Předmět: |
Materials science
Nuclear fuel Metallurgy Radiochemistry chemistry.chemical_element Americium Uranium Nitride 010502 geochemistry & geophysics 01 natural sciences Plutonium chemistry.chemical_compound Nuclear reprocessing chemistry 010503 geology Uranium nitride MOX fuel 0105 earth and related environmental sciences |
| Zdroj: | IOP Conference Series: Materials Science and Engineering. 130:012036 |
| ISSN: | 1757-899X 1757-8981 |
| DOI: | 10.1088/1757-899x/130/1/012036 |
| Popis: | Uranium nitride and mix uranium nitride (U-Pu)N is most popular nuclear fuel for Russian Fast Breeder Reactor. The works in hot cells associated with the radiation exposure of personnel and methodological difficulties. To know the main physical-chemical properties of uranium-plutonium nitride it necessary research to hot cells. In this paper, based on an assessment of physicochemical and thermodynamic properties of selected simulators Pu and Am. Analogues of Pu is are Ce and Y, and analogues Am - Dy. The technique of obtaining a model nitride fuel based on lanthanides nitrides and UN. Hydrogenation-dehydrogenation- nitration method of derived powders nitrides uranium, cerium, yttrium and dysprosium, held their mixing, pressing and sintering, the samples obtained model nitride fuel with plutonium and americium imitation. According to the results of structural studies have shown that all the samples are solid solution nitrides rare earth (REE) elements in UN. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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