基本释义:

再次冷却，再冷,[停堆]后冷却

网络释义

1)aftercooling,再次冷却，再冷;[停堆]后冷却

2)aftercooling,(停堆)后冷却

3)shutdown cooling,停堆后冷却，停炉冷却，停机冷却，停堆冷却

4)cooling at reactor shutdown mode,停堆冷却

5)recooler,再冷却，二次冷却器

6)regenerative cooling,再生冷却

用法和例句

Numerical study on coupled heat transfer of thrust chamber with regenerative cooling;

再生冷却推力室耦合传热数值模拟

The failure of regenerative cooling due to propellant coking in a liquid rocket engine was investigated by numerically analyzing the flow and heat transfer in a mini cooling channel with artificial roughness.

针对液体火箭发动机再生冷却中的结焦问题,对含粗糙元微小冷却通道内的流动和换热进行数值研究。

To understand and compare different heat transfer characteristics of regenerative cooling in axi-symmetrical nozzle and round to square nozzle(RS nozzle),computational models of axi-symmetrical nozzle(thrust chamber) and RS nozzle(thrust chamber) were established.

为了解和比较轴对称喷管与圆转方喷管不同的再生冷却换热特性,分别对轴对称喷管(推力室)与圆转方喷管(推力室)建立计算模型,通过数值模拟的方法重点研究和比较了轴对称喷管与圆转方喷管的流场、壁面热流密度和温度分布、冷却剂温升和冷却通道压降等换热特性。

Measures and Characteristics of Cooling at Shutdown Mode for China Advanced Research Reactor

中国先进研究堆停堆冷却措施及其主要特点

The Measurements of the Dynamic State Thermal Parameters of HFETR Fuel Element:the Loss-of-Power Accident,the Shutdown Cooling and the Decay Heat Experiment

高通量工程试验堆燃料元件动态热工参数测量——全厂断电、停堆冷却与剩余发热实验

reactor building cooling unit

反应堆建筑物冷却装置

granular graphite cooled reactor

颗粒状石墨冷却反应堆

liquid metal cooled reactor

液态金属冷却反应堆

reactor coolant leakage calculatio

反应堆冷却剂泄漏计算

boiling heavy water cooled and moderated reactor

沸腾重水冷却慢化堆

light water cooled heavy water reactor

轻水冷却重水反应堆

primary reactor coolant system

反应堆一次冷却系统

graphite moderated sodium cooled reactor

石墨慢化钠冷却反应堆

BGR (Bismuth-Graphite Reactor)

石墨慢化铋冷却反应堆

SCHWR (Steam-Cooled Heavy Water Reactor)

蒸汽冷却式重水反应堆

high temperature gas cooled reactor

高温气体冷却式反应堆

ganic moderated reactor

有机冷却型原子反应堆

experimental organic cooled reactor

实验性有机冷却反应堆

lithium cooled reactor experiment

锂冷却式实验性反应堆

reactor core isolation cooling system

反应堆堆芯隔离冷却系统

TRANSIENT BEHAVIOR OF THE LOSS OF HEAT SINK WITHOUT SCRAM AND INHERENT SAFETY OF SODIUM COOLED FAST REACTOR

钠冷快堆无停堆保护失热阱固有安全特性