nuclear pressure vessel
英 [ˈnjuːkliə(r) ˈpreʃə(r) ˈvesl]
美 [ˈnuːkliər ˈpreʃər ˈvesl]
网络 核压力容器
双语例句
- Study on Welding Seam Grinding Trajectory Detection System of Nuclear Pressure Vessel in Grinding Efficiency
核电容器高效磨削的焊缝轨迹检测与识别系统的研究 - To inspect the defects on the screw hole surfaces of nuclear reactor pressure vessel in nuclear power station, an automatic moving table was designed to carry sophisticated inspecting devices.
设计了能在高辐射环境下工作的、全自动检查核电站反应堆压力壳连接处法兰面主螺栓孔螺纹表面缺陷的设备，解决了自动小车的设备承载和准确定位问题。 - Research on Heavy Abrasive Belt Grinding and Its Application in Machining of Nuclear Power High Pressure Vessel
核电高压容器强力高效砂带磨削方法及应用研究 - The control rod drive mechanism ( CRDM) housing of nuclear power plant is installed on the reactor pressure vessel head by welding and interference fit.
核电站主设备控制棒驱动机构管座是通过焊接和过盈配合共同作用安装在压力容器顶盖上。 - As the basic safe wall of nuclear reactor, the reactor pressure vessel not only bears high temperature and high pressure, but also contains radioactive working substance.
反应堆压力容器作为反应堆的基本安全屏障，承受高温、高压且内部包含具有放射性的工作介质。 - : This Paper studies the instantaneous process of pressurized thermal shock ( PTS) on the nuclear pressure vessel. The coupling effects of mechanical and the thermal stresses have been analyzed and the influences of PTS events on the pressure vessel strength have been evaluated.
主要研究核压力容器承压热冲击（PTS）的瞬态过程，对热应力和机械应力产生的耦合效应进行分析，评价承压热冲击事件对容器强度的影响。 - A New Method for Improving the Reliability of Fracture Toughness Surveillance of Nuclear Pressure Vessel by Neutron Irradiated Embrittlement
提高核压力容器中子辐射脆化断裂韧性监测可靠性的新方法 - An experimental study of assessment of weld quality on fatigue reliability analysis of a nuclear pressure vessel
核容器焊接质量疲劳可靠性评估的试验研究 - Stress Intensity Factor at Beltline Flaws of Nuclear Reactor Pressure Vessel under Thermal Load
核容器环带区裂缝热荷载下的应力强度因子 - The theory and application of the digital image processing technology used in the nuclear pressure vessel nondestructive test negative image process are discussed in this paper.
本文论述了数字图像处理技术在核压力容器无损检测底片图像处理中的理论和应用。 - Method for Estimating Percent Shear Fracture Appearance of Charpy-V Specimen of Nuclear Pressure Vessel Steel
核压力容器钢冲击断口剪切面积百分比的估算方法 - Present Status and Prospect for Nuclear Pressure Vessel Technology in China
中国核承压设备的现状及展望 - : Percent shear fracture appearance is an important factor to evaluate neutron irradiation embrittlement of nuclear pressure vessel steel.
在核压力容器钢的中子辐照脆化评价中，断口剪切面积百分比是一个重要的参数。 - Mechanical properties of nuclear pressure vessel steel and it's welds
核压力容器钢和焊缝的力学性能研究 - Finite element analysis of large elasto-plastic deformation for sealing ring in nuclear pressure vessel
核压力容器密封环弹塑性大变形有限元分析 - Positioning of Moving Table for Checking Screw Holes of Nuclear Reactor Pressure Vessel
核反应堆压力壳螺栓孔检测自动小车的定位 - Research and measurement on dynamic fracture toughness for nuclear reactor pressure vessel steels
核压力容器钢辐照后动态断裂韧性测试及研究 - The Installation of Radiation Surveillance Capsules for Nuclear Pressure Vessel Materials
核压力容器材料辐照监督管的设置 - Transfer of technology in China for nuclear reactor pressure vessel internals manufacturing
在中国对核反应堆高压容器内部零件生产制造技术转让 - Pre-cracked and side-grooved Charpy-size specimen is an economical and convenient single-specimen method of evaluating the elastic-plastic fracture toughness of nuclear pressure vessel steels.
预制疲劳裂纹侧槽Charpy尺寸试样是一种经济、方便的评价核压力容器用钢弹塑性断裂韧性的单试样方法。 - Research and application of the first nuclear reactor pressure vessel inspection machine of China
我国首台核反应堆压力容器检查机研制及应用 - Influence of Pressurized Thermal Shock on Nuclear Pressure Vessel
承压热冲击对核压力容器强度的影响 - Studying of Toughness Transition Temperature Curve of Nuclear Pressure Vessel Steel by Use of Charpy Specimen
用Charpy试样研究核压力容器钢的韧性转变温度曲线 - The polar crane for nuclear power plant runs on a circular orbit on the top of the reactor plant, lifts the pressure vessel cover and components for reactor, and the positioning accuracy of polar crane must be strictly controlled.
核电站环行起重机运行于核反应堆厂房上方的环形轨道上，用于吊运反应堆压力容器顶盖和堆内构件，对其吊装定位精度要求极高。 - Therefore signal processing for ultrasonic nondestructive detection of nuclear reactor pressure vessel is studied in this paper. Firstly, this paper discusses the development course and explores the frontier of ultrasonic nondestructive detection technology.
为此，本文对核反应堆压力容器超声无损检测信号处理进行了研究。文中首先对超声无损检测技术的发展历程进行了阐述，并对学科前沿进行了探究。 - Nuclear reactor pressure vessel is an extremely important equipment in nuclear power plant. To ensure the quality of nuclear reactor pressure vessel, and further ensure nuclear plant working securely and normally, nuclear reactor pressure vessel must be tested roundly.
核反应堆压力容器是核电站中极其重要的设备，为保障核反应堆压力容器的质量，进一步保证核电厂安全正常的运行，必须对核反应堆压力容器进行全面的检测。 - According to structure and characteristics of the nuclear reactor pressure vessel, identify the objects and contents to be tested, give a specific system design scheme, and analyzed the echo signal.
根据核反应堆压力容器的结构和特点确定了被检对象和内容，给出了具体的系统设计方案，并对回波信号进行了分析。 - This paper reviewed the Water conditions in primary coolant of PWR nuclear power plant, determined that the material corrosion of pressure vessel, piping, steam generator in high temperature and high pressure water was an important factor of affect plant safety.
综述了核电站一回路的水工况，确定了压水堆压力容器、管道、蒸汽发生器等结构材料在高温高压水环境中的腐蚀是影响核电站安全的重要因素。 - Such as the main pipe of nuclear power station, it is large pipe with thick wall, connecting the steam generator and reactor pressure vessel. Its quality affects the safety of nuclear power station.
例如核电站中的主管道是连接蒸汽发生器与反应堆压力容器的大型厚壁弯管，其质量的好坏关系整个核电站的安全。