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
