Status of the development and production of uranium-plutonium fuel for fast reactors

被引:7
作者
Reshetnikov, FG
机构
[1] State Science Center of the Russian Federation, Russia Scientific-Research Institute of Standardization
关键词
Oxide; Uranium; Nitride; Plutonium; Fast Reactor;
D O I
10.1023/A:1014811604126
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A comparative assessment is given of the status of the technology for producing uranium-plutonium oxide and nitride fuel and reactor tests and postreactor studies. The additional investigations of nitride fuel required to substantiate a possible reactor core design with such fuel are noted.
引用
收藏
页码:998 / 1002
页数:5
相关论文
共 11 条
[1]  
BAUER AA, 1972, REACT TECHNOL, V15, P87
[2]   URANIUM NITRIDES [J].
EVANS, PE ;
DAVIES, TJ .
JOURNAL OF NUCLEAR MATERIALS, 1963, 10 (01) :43-55
[3]  
GOODYEAR M, 1967, BMI1809 USAEC
[4]  
Kotelnikov R.B., 1978, High-Temperature Nuclear Fuel
[5]   SINTERING OF URANIUM MONONITRIDE [J].
MCLAREN, JR ;
ATKINSON, PW .
JOURNAL OF NUCLEAR MATERIALS, 1965, 17 (02) :142-&
[6]  
MENSHIKOVA TS, 1971, 4 INT C UN PEAC US A
[7]  
PARDUE W, 1965, 3 INT C PLUT LOND NO
[8]  
RESHETNIKOV FG, 1991, ATOM ENERG, V70, P104
[9]  
RESHETNIKOV FG, 1974, T AM NUCL SOC, V19
[10]  
RESHETNIKOV FG, 1973, ATOM ENERG, V70, P377