基本释义:

应急堆芯冷却

网络释义

1)Emergency Core Cooling Systems,应急堆芯冷却

2)Emergency core cooling system,堆芯应急冷却系统

3)Emergency Core Cooling System,应急堆芯冷却系统

4)emergency core-cooling criteria,应急堆芯冷却[设计]准则

5)emergency cooling,紧急堆芯冷却

6)passive emergency core cooling system,非能动堆芯应急冷却系统

用法和例句

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