| 1. | They turned on two additional main coolant pumps .
他们又启动了两台主冷却泵。 |
| 2. | Nuclear reactor and primary coolant system
核反应堆及主冷却剂系统 |
| 3. | Primary coolant system
主冷却剂系统 |
| 4. | Main coolant system
主冷却剂系统 |
| 5. | The primary coolant system of a 900 mw class reactor consists of the reactor pressure vessel and the primary circuit with 3 identical loop top figure
一个900兆瓦的反应堆主冷却剂系统上图是由压力壳及三个相同的环路相连组成即一回路。 |
| 6. | The primary coolant system of a 900 mw class reactor consists of the reactor pressure vessel and the primary circuit with 3 identical loop ( top figure )
一个900兆瓦的反应堆主冷却剂系统(上图)是由压力壳及三个相同的环路相连组成(即一回路) 。 |
| 7. | The reactor coolant system is an important system of nuclear power plant , so simulation of reactor coolant system is an important part of nuclear power plant simulation
主冷却剂系统是核动力装置的一个重要系统，对主冷却剂系统的仿真研究是核动力装置仿真研究的一个重要部分，具有非常重要的意义。 |
| 8. | This method is used in a nuclear power station , diagnosis results is better ideality , and it has been shown that it is feasible for fault diagnosis of nuclear power station and fast reactor sodium pump
本文将此方法应用于某核电厂主冷却剂泵，诊断结果比较理想，证明此方法在核电厂的故障诊断中是可行的，对快堆钠泵的诊断也是可取的。 |
| 9. | At the main content of the thesis , the author collect the main fault ' s character information of primary loop systems , and those systems include main coolant system and pressure safety system and redundant heat discharging system and safety injection system and so on , the author also compare those faults whose character information is similar
在论文的主要工作内容中，本文收集整理了船用核动力装置一回路各系统的主要故障的特征信息，其中包括一回路主系统主冷却剂系统以及主要辅助系统如压力安全系统、余热排出系统、安全注射系统等，并对特征信息类似的故障进行了对比。 |
| 10. | Based on adequate survey to faults of sodium pump for the china experiment fast reactor , in order that the advanced diagnosis methods are used in the sodium pump which is under fabrication , different methods of fault diagnosis system of sodium pump are designed and programmed ; and the principal component analysis ( pca ) is used to fault diagnosis system of main coolant pump in a nuclear power station . the feasibility of fault diagnosis systems developed have been proved by simulation results
本课题对中国实验快堆钠泵的故障进行了研究，把先进的诊断方法应用到正在制造中的钠泵上，设计和开发了不同方法的钠泵的故障诊断系统；同时也应用主元分析方法，建立了某核电厂的主冷却剂泵的故障诊断系统，仿真实验证明了以上三个系统的可行性。 |
