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- In order to adapt to real time simulation, the nodes of system and the predigestion was made according to the characteristic of reactor coolant system which will be simulated. 本论文针对要仿真的冷却剂系统的特点，对系统进行了节点划分，并做了适当简化，以使其适应实时仿真的需要。
- The reactor coolant system(RCS)is one of the most important systems of China Advanced Research Reactor(CARR),which is used to cool the core when the reactor is running. 反应堆冷却剂系统(RCS)是中国先进研究堆(CARR)的重要系统之一,反应堆运行时,通过其将堆芯的热量带出,该系统的安全有效运行是反应堆安全运行的必要保证。
- Reactor coolant system dose equivalent 反应堆冷却剂系统剂量当量
- Low temperature overpressure analysis of reactor coolant system 反应堆冷却剂系统低温超压分析
- Reactor Coolant System (RCS) depressurization strategy 一回路卸压策略
- Seismic Resistant Analysis of Coupled Model of Reactor Coolant System and Reactor Building 土建结构与主回路耦联模型抗震分析研究
- Mechanical Analysis of Reactor Coolant System for Qinshan Phase II NPP Project Main Coolant System and Auxiliary System 秦山核电二期工程反应堆主冷却剂系统与辅助系统力学分析
- Real-Time Simulation Calculation of Reactor Coolant System 反应堆主冷却剂系统实时仿真计算
- Design of the Reactor and Reactor Coolant System for Qingshan Phase II NPP Project 秦山核电二期工程反应堆及反应堆冷却剂系统设计
- primary reactor coolant system 反应堆一次冷却系统
- Determination of an optimum reactor coolant system average temperature within the licensed operating window 在许可的操作窗下最佳反应堆冷却剂系统平均温度的确定
- The test is designed to determine the flow rate of the reactor coolant pump. 试验是设计用来确定反应堆冷冻剂泵的流速。
- Reactor coolant system 冷却剂系统
- Possessing high technology reactor coolant pump is the pride of a nuclear power plant. 拥有技术上先进的反应堆冷却剂泵,是核电厂的骄傲。
- The nuclear reactor coolant pump (RCP) is one of the core equipments in PWR Nuclear Power Plant. 摘要核主泵是压水型反应堆核电站中的核心设备之一。
- Integral spindle coolant system decreases the high temperature and ensures running accuracy after long time working. 采用内藏式主轴油冷却系统,有效降低头部温升,确保长时间加工的运转精度。
- Abstract The seismic analysis for reactor coolant piping (RCP) primary loop is one of the very important work in design of nuclear power plants. 摘要 核电站反应堆冷却剂系统地震分析是核电设计中一项十分重要的工作。
- Nuclear reactor and primary coolant system 核反应堆及主冷却剂系统
- The metohd for analysing the dynamic process of auxiliary bus voltage, frequency and coastdown of reactor coolant pump at the time of power supply failure was suggested. 通过秦山核电厂在电源事故情况下,厂用母线电压,频率的动态过程研究和主泵惰走的分析研究,阐述了这一问题分析研究的方法,给出计算结果并通过动态模拟试验进行验证。
- The analytical method and the method in RELAP5/MOD1 computer code for reactor coolant coastdown flow calculation in loss of flow accident in PWR are briefly described. 简要介绍解析法和RELAP5/MOD1计算机程序中计算压水堆失流事故下冷却剂惯性流量的方法.
