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research reactor是什么意思

中文翻译研究用堆

网络释义

1)research reactor,研究用堆2)medical research reactor,医用研究反应堆3)naval research reactor,船用研究反应堆4)multipurpose research reactor,多用研究[反应]堆5)research-and-development reactor,研究和发展用堆6)Research reactor,研究堆

用法例句

    Computing worth of thin slab control rod in thermal research reactor;

    热中子研究堆薄板型控制棒价值计算

    This paper summarizes the regulations,safety guides and guidance documents for ageing management of research reactors,introduces the present status(lifetime assessment,periodic safety re- view and its effects)of aging management for research reactors in China,and put forward some sugges- tions on strengthening and promoting the ageing management of research reactors in China.

    本文概述了国内外有关研究堆老化管理的法规、导则及系列指南文件,介绍了目前我国研究堆老化管理工作(寿期论证、定期安全审查等)的开展情况及取得的成效,并从加强法规建设、推进系统老化管理、加强老化技术研究、推进相互合作等几方面对加强我国研究堆老化管理工作提出了若干建议。

    This paper presents the recent activities of IAEA on the research reactor safety,and the trends in the future.

    简要介绍了国际原子能机构(IAEA)近年来在研究堆开发与安全管理方面的重要举措,以及未来发展的趋势。

    Design of Core Vessel and Core Structure in China Advanced Research Reactor

    中国先进研究堆堆芯容器及堆内构件设计研究

    The Study on 80 Fuel Assemblies Core for HFETR

    高通量工程试验堆80盒元件堆芯研究

    fast reactor thermal engineering facility

    快堆热工程研究设施

    high performance research reactor

    高性能研究用反应堆

    health physics research reactor

    保健物理研究用反应堆

    direct conversion reactor study

    直接转换反应堆研究

    argonaut type research reactor

    阿贡诺型研究反应堆

    low-flux research reactor

    低通量研究性反应堆

    TRR (Teaching and Research Reactor)

    教学与研究用的反应堆

    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

    Study on method of piling up heap leaching and CIP tailings in order to make them consolidated and dewatered

    堆浸尾渣和炭浆尾矿排水固结堆排方法的研究

    Preliminary study on thorium-uranium fuel cycle in the equilibrium core of PWR

    压水堆平衡堆芯钍铀燃料循环初步研究

    CONCEPTUAL RESEARCH ON REACTOR CORE PHYSICS FOR ACCELERATOR DRIVEN SUB CRITICAL REACTOR

    加速器驱动次临界堆堆芯物理概念研究

    The fast reactor safety analysis is the foundation and key of FBR research work.

    快堆安全分析是快堆研究工作的基础和重点。

    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

    Study on Strip Surfacing Technologies and Mechanical and Property of Surfacing Deposit for 2.25Cr1Mo Steel;

    2.25CrlMo钢带极堆焊工艺及堆焊层组织、性能研究

    Study on the Overlaying Property and Hot Corrosion Resistance of Fe_3Al Alloy Overlayer;

    Fe_3Al合金堆焊及堆焊层的耐热腐蚀性能研究

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