advanced thermal reactor
改进型热中子反应堆
STR (submarine thermal reactor)
潜艇用热中子反应堆
thermal cross section reactor physics computer code
反应堆物理热中子截面计算机代码
space thermionic auxiliary reactor
空间热离子辅助反应堆
FRTC (Fast Reactor Training Center)
快中子反应堆培训中心
submarine intermediate reactor
潜艇用中能中子反应堆
fast burst reactor facility
快中子脉冲反应堆装置
GCFBR (Gas Cooled Fast Breeder Reactor)
气冷快中子增殖反应堆
variable flux reactor
可变中子通量反应堆
SCFBR (Steam-Cooled Fast-Breeder Reactor)
汽冷快中子增殖反应堆
fast zero power reactor
快中子零功率反应堆
slow fast reactor
慢快中子双区反应堆
FARET (Fast Reactor Experiment Test)
快中子反应堆实验测试
Neutron flux distributions in the reactor core are measured.
测量了反应堆堆芯里的中子通量分布。
The atom reactor could run wild with too many neutrons.
倘若中子太多，原子反应堆就会失控。
In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T8995-1988核反应堆中子注量率测量堆芯仪表
laser controlled thermonuclear reactor
激光受控热核反应堆
advanced epithermal thorium reactor
改进型超热钍反应堆