Imitators of plutonium and americium in a mixed uranium- plutonium nitride fuel

10th International School-Conference on Materials for Extreme Environment: Development, Production and Application

Nikitin, S.N.^1 ; Shornikov, D.P.^1 ; Tarasov, B.A.^1 ; Baranov, V.G.^1 ; Burlakova, M.A.^1

National Research Nuclear University MEPhI, Moscow Engineering Physics Institute, Kashirskoye Highway 31, Moscow

115409, Russia^1

关键词: Fast breeder reactors;    Hot Cell;    Nitride fuel;    Physical chemical property;    Radiation Exposure;    Structural studies;    Uranium nitride;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/130/1/012036/pdf
DOI  :  10.1088/1757-899X/130/1/012036

来源: IOP

【 摘 要 】

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.