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in core thermionic reactor是什么意思

中文翻译堆芯热离子反应堆

网络释义

1)in core thermionic reactor,堆芯热离子反应堆2)thermionic reactor,热离子反应堆3)ITR (in-core thermionic reactor),堆内热离子[反应]堆4)out-of-core thermionic reactor,堆外热离子[反应]堆5)reactor core,反应堆堆芯6)RCIC (reactor core isolation cooling),反应堆堆芯隔离冷却

用法例句

    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

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