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

被引：3

作者：

Nikitin, S. N. ^{[1
]}

Shornikov, D. P. ^{[1
]}

Tarasov, B. A. ^{[1
]}

Baranov, V. G. ^{[1
]}

Burlakova, M. A. ^{[1
]}

机构：

[1] Natl Res Nucl Univ MEPhI Moscow Engn Phys Inst, Kashirskoye Highway 31, Moscow 115409, Russia

来源：

10TH INTERNATIONAL SCHOOL-CONFERENCE ON MATERIALS FOR EXTREME ENVIRONMENT: DEVELOPMENT, PRODUCTION AND APPLICATION (MEEDPA10) | 2016年 / 130卷

关键词：

D O I：

10.1088/1757-899X/130/1/012036

中图分类号：

T [工业技术];

学科分类号：

08 ;

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.

引用

页数：5

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