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
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
light water cooled heavy water reactor
轻水冷却重水反应堆
primary reactor coolant system
反应堆一次冷却系统
graphite moderated sodium cooled reactor
石墨慢化钠冷却反应堆
BGR (Bismuth-Graphite Reactor)
石墨慢化铋冷却反应堆
SCHWR (Steam-Cooled Heavy Water Reactor)
蒸汽冷却式重水反应堆
high temperature gas cooled reactor
高温气体冷却式反应堆
ganic moderated reactor
有机冷却型原子反应堆
experimental organic cooled reactor
实验性有机冷却反应堆
lithium cooled reactor experiment
锂冷却式实验性反应堆
Analysis of Candidate Core Materials in SCWR Based on Boiler Materials of SCU
基于超临界火电站锅炉用材的超临界水冷却反应堆堆芯候选材料分析