基本释义:

展览[反应]堆

网络释义

1)exhibition reactor,展览[反应]堆

2)EER (European Exhibition Reactor),欧洲展览[反应]堆

3)development reactor,研究发展用反应堆

4)research-and-development reactor,研究和发展用(反应)堆

5)PRV head package,反应堆堆顶

6)reactor core,反应堆堆芯

用法和例句

NPIC have finished the design of PRV head package based on the design experience of PRV head package of naval ships and the advanced design technology used in the nuclear power plants in the world.

中国核动力研究设计院(NPIC)在吸取过去的设计经验和跟踪国外核电站先进技术的基础上,成功地完成了秦山核电二期工程反应堆堆顶的设计。

reactor core radiation detector

反应堆堆芯辐射检测仪

reactor core isolation cooling system

反应堆堆芯隔离冷却系统

Neutron flux distributions in the reactor core are measured.

测量了反应堆堆芯里的中子通量分布。

Heat Balance Test for Determined Reactor Core Power

计算核反应堆堆芯功率的热平衡试验

A Mechanism Investigation of Core Melting in Nuclear Reactor Using Molecular Dynamics Method

用分子动力学方法研究反应堆堆芯熔化机理

A Measurement Method Regarding Reactor Core Thermal Power and Error Analysis

反应堆堆芯热功率测量方法及其误差分析

Research on Online Data Processing Method for Nuclear Monitoring of Reactor Core

反应堆堆芯核测量数据在线处理方法研究

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

A REWETTING MODEL DURING CORE BOTTOM UP REFLOOD PROCESS AFTER PWR LOCA;

失水事故中反应堆堆芯再淹没数学模型

Preliminary Design of Sub-critical Reactor Core for Accelerator Driven System with Three Proton Beams

三束流驱动ADS次临界反应堆堆芯初步设计

In this paper, the genetic algorithm( GA) has been used in reactor fuel management of core arrangement optimal calculation.

应用遗传算法编制了核反应堆堆芯燃料管理优化计算程序。

Analysis of Stress in Reactor Core Vessel under Effect of Pressure Lose Shock Wave

反应堆堆芯容器在泄压冲击波作用下的应力分析

The method is used to measure the neutron flux distribution in the reactor core.

这种方法被用来测量反应堆堆芯的中子通量分布。

NUMERICALLY SOLVING DYNAMICS EQUATIONS OF PLASMAIN FUSION-FISSION HYBRID REACTOR CORE

聚变－裂变混合反应堆堆芯等离子体动力学方程组数值求解

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

it had a graphite core and no containment structure.

这些反应堆有一个石墨堆芯，没有外壳结构。

In-core instrumentation for neutron fluence rate measurements in nuclear reactors

GB/T8995-1988核反应堆中子注量率测量堆芯仪表

Study on Core Fuel Management of Slightly Enriched Uranium Fuel for CANDU6 Reactor;

CANDU6反应堆提高燃料富集度的堆芯燃料管理研究