core auxiliary cooling water

基本解释堆芯辅助冷却水

网络释义

1)core auxiliary cooling water,堆芯辅助冷却水2)ACC (auxiliary core cooling),堆芯辅助冷却3)core assistant cooling system,堆芯辅助冷却系统4)LOCACS (loss of core auxiliary cooling system accident),堆芯辅助冷却系统丧失事故5)Core cooling,堆芯冷却6)auxiliary cooling water system,辅助冷却水系统

用法和例句

This paper introduces the components of auxiliary cooling water system of power plant,compares open cooling water system with closed cooling water system,and draws the conclusion that closed cooling water system is suitable for Chinese situation.

介绍了电厂辅助冷却水系统的构成,对开式与闭式两种冷却水方式进行了比较,得出了闭式冷却水系统更适合我国国情的结论。

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

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

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

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

boiling heavy water cooled and moderated reactor

沸腾重水冷却慢化堆

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

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