Program and Some Results of Pre-Reactor Studies of Mixed Uranium-Plutonium Nitride Fuel for Fast Reactors

被引：0
|
作者：
V. M. Troyanov
A. F. Grachev
L. M. Zabud’ko
M. V. Skupov
G. A. Kireev
机构：
[1] Innovation and Technology Center for Proryv Project,
[2] Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM),undefined
来源：
Atomic Energy | 2015年 / 117卷
关键词：
Plutonium; Fuel Element; Fuel Assembly; Closed Fuel Cycle; Nitride Fuel;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
For future nuclear power with fast reactors with sodium (BN-1200) and lead (BREST) as coolants, plans are being made to use mixed uranium-plutonium nitride fuel as part of the Proryv project. A technology for carbothermal synthesis of mixed uranium-plutonium mononitride fuel and fabrication of pellets from it has now been developed. A program of comprehensive computational and experimental research on fuel to study the initial properties and their change under irradiation in reactor experiments is being implemented. Some results of pre-reactor studies of the properties of fuel and a program for future research are presented.
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页码：236 / 242
页数：6
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