English translation for "反应堆冷却"

reactor cooling

Related Translations:

反应堆正面:  pile face

平板反应堆:  slab reactor

前驱反应堆:  precursor reactor

轻水反应堆:  light water reactor (lwr)light-water reactorlwr

反应堆心:  core

冶金反应堆:  metallurgical reactor

反应堆计算:  reactor calculation

反应堆原型:  reactor prototype

燃烧反应堆:  burner reactor

反应堆外:  out-of-core

Example Sentences:

	1.	Cooldown criteria for light water reactors 轻水反应堆冷却准则
	2.	The real - time simulation of reactor coolant system was studies in the dissertation 本论文对反应堆冷却剂系统进行了实时仿真计算研究。
	3.	Simulation study of internal model control system of refrigerant average temperature of nuclear reactor 核电站反应堆冷却剂平均温度内模控制系统仿真
	4.	E standard practice for calculation of average energy per disintegration for a mixture of radionuclides in reactor coolant 反应堆冷却剂中放射性核素混合物每次蜕变的平均能量
	5.	When the reactor cooled down , the longer - lived xenon precursors ( those that would later spawn xenon 132 , 131 and 129 , which we found in relative abundance ) were preferentially incorporated into growing grains of aluminum phosphate 当反应堆冷却下来，氙的放射性母核中生命期较长的，则被选择性的包纳进正在成长的磷酸铝颗粒中，例如那些可以生成我们所见的大量氙132 、氙131 、氙129的物质。
	6.	Obviously , it is very helpful to prevent first side outline from overpressure and overheating through the way of discharging the heat generated by cooling system ; and prevent the core of the reactor from being too cooled by limiting the discharge amount of steam 这有助于：一通过排出反应堆冷却系统产生的能量来防止一回路侧超压和过热；二通过限制蒸汽向大气的释放量来防止反应堆堆芯过冷。
	7.	In the thesis , the relap5 code is made use of simulating and calculating the passive core makeup tank ( cmt ) of the next generation reactor ac - 600 of our country . and the calculative results based on the comparative character of the system are compared with the experimental results in the corresponding experimental devices of ac - 600 makeup water tank in nuclear power institute of china ( npic ) . finally the thesis conclusion summarized is that the makeup water passively injected to the reactor coolant system by the core makeup tank depending on the gravity is viable in the middle and small locas 本论文利用relap5程序对我国下一代先进堆ac - 600的一个具有非能动性能的堆芯补水箱分系统进行了仿真计算，根据系统之间的可比性，把计算的结果和与之相对应的中国核动力研究设计院堆芯补水箱补水实验装置的实验结果进行了定性的比较分析，得到了论文的结论：在中、小破口失水事故的工况下，堆芯补水箱依靠重力向反应堆冷却剂系统实现非能动的补水是可行的。

Similar Words：

"反应堆控制" English translation, "反应堆控制棒" English translation, "反应堆控制材料" English translation, "反应堆控制台" English translation, "反应堆控制系统" English translation, "反应堆冷却池" English translation, "反应堆冷却剂" English translation, "反应堆冷却剂泵" English translation, "反应堆冷却剂出口" English translation, "反应堆冷却剂管" English translation