Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors

被引：0
|
作者：
V. M. Troyanov
A. F. Grachev
L. M. Zabud’ko
M. V. Skupov
D. V. Zozulya
机构：
[1] Innovative Technological Center for the Proryv Project,
[2] Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM),undefined
[3] Siberian Chemical Combine (SKhK),undefined
来源：
Atomic Energy | 2015年 / 118卷
关键词：
Fuel Element; Fuel Assembly; Uranium Dioxide; Fuel Kernel; Experimental Fuel;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
In the Proryv project, mixed uranium-plutonium nitride fuel is to be used in the future nuclear power with fast reactors with sodium coolant (BN-1200) and with lead coolant (BREST). At present, experimental fuel elements and fuel assemblies with mixed nitride fuel are fabricated by means of a technology developed at the Bochvar All-Russia Research Institute for Inorganic Materials for testing in the BN-600 reactor and the MIR and BOR-60 research reactors. The program of reactor tests of the experimental fuel assemblies and some preliminary results of these tests are presented.
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页码：96 / 100
页数：4
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