thermal neutron chain reaction

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