核燃料组件

核燃料组件变形的评价及其实现

The Evaluation to the Nuclear Fuel Assembly Distortion and Its Realization

介绍了核燃料组件中锆管自动TIG焊的工艺过程，设计了PC的接口电路和控制程序。

Auto - TIG welding process of zirconium tube for nuclear fuel package is introduced . The interface circuit and control program are designed .

利用ADAMS软件建立了核燃料组件铁路运输容器系统的仿真模型。

The simulation model of the railway conveying vessel system of nuclear fuel assemblies is established by using ADAMS dynamic simulation software .

核燃料组件运输容器隔振系统的振动分析

Vibration Isolation Analysis for Conveying Vessel System of Nuclear Fuel Assemblies

反应堆核燃料组件定位格架的两相流动压降计算

The Calculation of Two-Phase Flow Pressure Drop in Reactor Fuel Elements'Spacer Grid

法国先进核燃料组件在中国应用前景浅析

Application Perspective of French Advanced Nuclear Fuel Assemblies in China

GB/T15147-1994核燃料组件零部件的渗透检验方法

Liquid penetrant examination for component parts of nuclear fuel assemblies

核燃料组件骨架点焊装置点焊机器人焊接系统

Spot welding device for framework of nuclear fuel set

核燃料组件铁路运输容器系统在纵向冲击下的安全性分析

Safety Analysis for Railway Conveying Vessel System of Nuclear Fuel Assemblies Subject to Longitudinal Impact

因此，对核燃料组件的变形进行定期的检测和评价具有十分重要的意义。

Therefore , the periodic survey and evaluation to the subassembly distortion is very important .

中子照相技术已较为广泛的应用于飞机（机翼、油箱、发动机等）、航天飞行器元件、火工品、电子线路、冶金部件、有机粘合件、核燃料组件的无损检测和氢化物的检测。

Neutron radiography has been more widely used in aircraft ( wing , fuel tank , engine , etc. ), spacecraft components , electronic circuits , metallurgical parts , pieces of organic adhesive , non-destructive testing of nuclear fuel components and the hydride testing .

苏联压水堆核电站燃料组件的科研与生产概况

Research and Production for Nuclear Fuel Assemblies of PWR in USSR

核电站燃料组件生产线通风措施

Ventilating measures of the fuel assembly line in nuclear power plants

用激光扫描投影法检测核燃料模拟组件变形

Measuring Simulated Nucleus Fuel Modules ' Distortions with Laser Scan and Projection Method

本文介绍了核电站和燃料组件，特别对烧结UO2芯块的特性和YFP制造UO2芯块的情况进行了详细的介绍。

Especially , the characteristic of sintered UO_2 pellets and the statue of UO_2 pelletization in YFP are described in detail .

核供热堆燃料组件均匀化参数的计算

Calculation of homogeneous parameters in an in core assembly for NHRs

核燃料元件及其组件作为核电厂的一个关键部件和第一道安全屏障，其寿命和可靠性是保证和提高核电安全性和经济性的一个重要因素。

Fuel rods and fuel assembly are key components in a reactor , serving as the first safety protection , the life and reliability of which are important factors to improve safety and economization in nuclear power industry .

叙述了5MW核供热试验堆燃料组件入口和主换热器一次侧阻力系数测定实验。

The experimental determination of the inlet resistance coefficients of fuel assembly as well as the primary side resistance of primary heat exchanger for5MW heating test reactor is described .

PMC核燃料装卸贮存系统直接吊装核燃料组件，即直接面对核电站三道屏障中的第一道屏障&燃料包壳，其安全性是核电站核安全的重要保障。

Nuclear fuel handling and storage system ( PMC ) is a system which directly handles nuclear fuel assemblies , namely , it directly faces to nuclear fuel cladding which is the first of the three barriers of nuclear safety for nuclear power station .

大亚湾核电站及岭澳核电站核燃料组件供应国产化和堆芯燃料管理自主化

Localization of Nuclear Fuel Supply and Fuel Management in Guangdong Nuclear Power Stations