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1)  large break loss of coolant accident
大破口失水事故
1.
2 and taking US Westinghouse corporation Surry nuclear power plant as the reference object, a typical three-loop pressurized water reactor severe accident calculation model was established and 25cm large break loss of coolant accident(LBLOCA)in cold and hot leg of primary loop induced core melt accident was analyzed.
2,以美国西屋公司Surry核电站为参考对象,建立了1个典型的3环路压水堆核电站的严重事故分析模型,分别对主回路冷段和热段发生25cm大破口失水事故(LBLOCA)导致的堆芯熔化事故进行研究分析。
2.
The analysis of large break loss of coolant accident(LBLOCA) which occured at nominal power of nuclear power plant is given.
针对核电站额定运行工况下发生冷段大破口失水事故进行了分析。
3.
The characteristics of large break loss of coolant accident(LOCA) for Xi\'an Pulsed Reactor were analyzed.
分析了西安脉冲堆大破口失水事故的特点,建立了适用的数学模型,编制了计算程序。
2)  large break LOCA
大破口冷却剂丧失事故,大破口失水事故
3)  SBLOCA
小破口失水事故
1.
By using the real-time simulation,the un-separated SBLOCA(small-break loss-of-coolant accident) which occurred in primary loop circuit system of a marine nuclear power plant was studied.
利用建模仿真的方法,对船舶核动力装置一回路系统发生无法隔离的小破口失水事故进行研究。
4)  Large break loss-of-coolant accident
大破口冷却剂丧失事故
5)  Coolant Pipeline Small LOCA
冷却剂管道小破口失水事故
6)  loss of coolant accident
破口事故
1.
The safety analysis was calculated using the RELAP5 code,which focused on the loss of coolant accident(LOCA) and loss of flow accident(LOFA).
基于此,一种多用途的一体化轻水堆设计概念被提出,包括不同设备的初步设计方案和参数;根据其特点,利用最佳估算程序RELAP5对其中一个设计方案进行了稳压器汽腔破口事故和主泵断电引起的丧失流量事故的确定论安全分析。
补充资料:失水

  
  失水
  dehydration

  过多水分排出体外,使机体内水低于生理需要的一种状态。可由各种原因所引起,例如剧烈呕吐,严重腹泻、高热、大量出汗及进食和饮水减少,都可引起体内水的丢失。表现为口渴、口干舌燥、软弱、少尿、发热等症状,严重者引起虚脱,甚至休克、昏迷而死亡。此时应尽快补液治疗。
  
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