Reliability Analyse and Test Frequency Optimization of Motorized Isolation Valves of Emergency Core Cooling System;
应急堆芯冷却系统电动阀的可靠性分析及试验频率优化
The effect of different break size at cold leg , different pressure balance line and automatic depressurize system on transient behavior of passive emergency core cooling system was investigated on the AC600CMT test facility.
在改造后的AC6 0 0全压堆芯补水箱实验装置上 ,实验研究了不同尺寸的冷段破口 ,不同的堆芯补水箱压力平衡管以及自动卸压系统对非能动堆芯应急冷却系统瞬态特性的影响 ,描述了实验过程及实验结果。
Reliability Analyse and Test Frequency Optimization of Motorized Isolation Valves of Emergency Core Cooling System;
应急堆芯冷却系统电动阀的可靠性分析及试验频率优化
reactor core isolation cooling system
反应堆堆芯隔离冷却系统
primary reactor coolant system
反应堆一次冷却系统
charging/make-up flow [reactor coolant system]
上充／补给水流量〔反应堆冷却剂系统〕
reactor building cooling water system
反应堆建筑物冷却水系统
reactor coolant system dose equivalent
反应堆冷却剂系统剂量当量
Investigation on Piezo-pump Used in Water-cooling-system for Computer CPU Chip
压电泵在CPU芯片液体冷却系统中的应用研究
Improvement and practice of speed measurement system for reactor coolant pump
反应堆冷却剂泵转速测量系统改进设计及实践
Source Terms Calculation Analysis for the Reactor and Primary Coolant System of Qinshan Phase II NPP Project
秦山核电二期工程反应堆及反应堆冷却剂系统源项计算分析
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
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
The Online Simulation System Research of Reactor Physics in Nuclear Power Plant;
核电厂反应堆堆芯物理在线仿真系统研究
Measurements for monitoring adequate cooling within the core of pressurized light water reactors
GB/T13632-1992监督压水堆堆芯充分冷却的测量要求
A soft-measuring method to measure the core coolant temperature at the outlet of a nuclear heating reactor
核供热堆堆芯冷却剂出口温度的软测量方法
reactor building cooling unit
反应堆建筑物冷却装置
granular graphite cooled reactor
颗粒状石墨冷却反应堆
liquid metal cooled reactor
液态金属冷却反应堆
reactor coolant leakage calculatio
反应堆冷却剂泄漏计算