nuclear cooling

基本解释核冷却

网络释义

1)nuclear cooling,核冷却2)nuclear reactor coolant,核反应堆冷却剂3)nuclear fuel cooling installation,核燃料冷却装置4)CEFR nuclear-related equipments cooling water system,CEFR核级循环冷却水系统5)short cooled fuel,短期冷却[的核]燃料6)primary component cooling water system,核岛设备冷却水系统

用法和例句

Numerical Simulation of Three-Dimensional Flow Through Full Passage and Performance Prediction of Nuclear Reactor Coolant Pump

核反应堆冷却剂循环泵全流道三维数值模拟及性能预估

a nuclear reactor using gas as a coolant.

用气体做冷却剂的核子反应堆。

reactor coolant leakage calculatio

反应堆冷却剂泄漏计算

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

reactor coolant system dose equivalent

反应堆冷却剂系统剂量当量

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。

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

charging/make-up flow [reactor coolant system]

上充/补给水流量〔反应堆冷却剂系统〕

reactor coolant circuit integrity

反应堆冷却剂回路完整性

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

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

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