反应堆冷却的英文

• reactor cooling

• "反应堆"英文翻译    pile; reactor
• "冷却"英文翻译    cool off
• "反应堆冷却池" 英文翻译 :    stillpot
• "反应堆冷却剂" 英文翻译 :    reactor coolant
• "反应堆冷却剂泵" 英文翻译 :    reactor coolant pump
• "反应堆冷却剂出口" 英文翻译 :    reactor coolant outlet
• "反应堆冷却剂管" 英文翻译 :    reactor coolant pipe
• "反应堆冷却剂系统" 英文翻译 :    reactor coolant system
• "反应堆冷却系统" 英文翻译 :    reactor coolant system; reactor cooling system
• "核反应堆冷却剂" 英文翻译 :    nuclear reactor coolant
• "反应堆冷却剂回路完整性" 英文翻译 :    reactor coolant circuit integrity
• "反应堆冷却剂泄漏计算" 英文翻译 :    reactor coolant leakage calculation
• "反应堆冷却剂压力界" 英文翻译 :    reactor coolant pressure boundary
• "反应堆冷却净化系统" 英文翻译 :    clean-uwater system
• "反应堆冷却剂系统剂量当量" 英文翻译 :    reactor coolant system dose equivalent
• "汞冷却反应堆" 英文翻译 :    mercury cooled reactor
• "钠冷却反应堆" 英文翻译 :    sodium cooled reactor
• "停堆冷却" 英文翻译 :    residual heat removal; shutdown cooling
• "停堆冷却泵" 英文翻译 :    shutdown cooling pump
• "停堆冷却器" 英文翻译 :    shutdown cooler
• "表面冷却反应堆" 英文翻译 :    surface cooled reactor
• "粉尘冷却反应堆" 英文翻译 :    dust cooled reactor
• "加压水冷却反应堆" 英文翻译 :    pressure water cooled reactor; pressurized water cooled reactor
• "空气冷却反应堆" 英文翻译 :    air cooled reactor; air-cooled reactor
• "气体冷却反应堆" 英文翻译 :    gas-cooled reactor

• Cooldown criteria for light water reactors
  轻水反应堆冷却准则
• 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。
• 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
• 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
• 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。
• 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。
• 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。