燃料组件

研究堆乏燃料组件中~（235）U含量和燃耗的测定

Measurement of ~ ( 235 ) U Mass and Burnup in Fuel Assembly in Research Reactors

PWR燃料组件定位格架夹持力辐照松弛的研究

The Study of Irradiation-Induced Relaxation Behaviour for PWR Fuel Assembly Spacer Grid Clipping Force

中国先进研究堆（CARR）工程燃料组件设计验证试验

Design Validation Test of Fuel Assembly of China Advanced Research Reactor

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 .

300MW燃料组件设计改进的回顾与展望

Review and prospect for 300 MW fuel assembly design improvement

SPRR-300堆乏燃料组件初步测量

Preliminary measuring of spent fuels in SPRR - 300

研究还建议在使用CFD方法进行燃料组件格架热工水力分析前要先进行基准练习以保证分析结果的正确性。

In order to ensure the correctness of prediction results , it suggests to take a benchmark exercise before the analysis of CFD thermal hydraulic analysis for a fuel assem-ble with spacers .

结果表明，CARR燃料组件的设计和加工工艺是合理的，谈组件在反应堆实际运行条件下是稳定和安全的。

The test results indicated the design and manufacture of CARR fuel assembly are reasonable , and the fuel assembly will be stable and safe under CARR operation condition .

乏燃料组件清洗系统的监控系统采用研华公司的ADAM-5000系列产品作为数据采集和控制器，用Labwindows/CVI软件进行开发。

In this system the ADAM-5000 series product is used as the sensor and controller , the system is designed with the software of Lab Windows / CVI .

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 .

在CYBER825计算机上移植了引进的反应堆燃料组件计算程序系统MARIA以后，又将该程序系统推广应用于加浓铀裸球临界装置。

The imported reactor fuel assembly MARIA program system is adapted to CYBER 825 computer in China Institute of Atomic Energy , and extensively used for a series of enriched uranium bare sphere critical assemblies .

AFA2G燃料组件虽已使用了很长时间，并已逐渐被AFA3G燃料组件和Alliance燃料组件所替代，但其燃料棒设计参数不确定性研究结果同样适用于新型燃料组件。

Though the AFA 2G fuel assembly have been used for a long time , and is gradually replaced by AFA 3G and Alliance fuel assemblies , but the researched results from AFA 2G is also suitable for the new type fuel assemblies .

燃料组件截面参数处理程序FITLINK

Treatment Program of Fuel Assembly Cross Section parameter ── FITLINK

本文开展的含绕丝燃料组件阻力特性的初步实验研究，为10MW自然循环铅铋冷却反应堆的热工水力设计验证提供了参考。

The experiment results of the resistance characteristic of a wire-wrapped fuel assembly obtained in this paper can provide preliminary reference for the thermal-hydraulic design verification of reactor .

轻水堆燃料组件计算程序包TPFAP

TPFAP & a Code Package for LWR Fuel Assembly Calculation

在200MW核供热堆（NHR－200）水力学实验回路（HRHTL－200）上完成了NHR－200燃料组件进口阻力特性实验研究。

The Experiment is carried out on the 200 MW heating reactor hydraulic test loop ( HRHTL 200 ) .

本文介绍了法杰马所提供的先进燃料组件（AFA）设计所具有的特点，同时介绍了第二代先进燃料组件的技术改进。

This paper describes design characteristics on Advanced Fuel Assembly ( AFA ) supplied by Fragema , and also describes several new improvements on second generation of Advanced Fuel Assembly .

200MW核供热堆（NHR－200）燃料组件定位格架主要由条带、围带及角部片簧组成。

The spacer grid of the 200 MW nuclear heating reactor ( NHR 200 ) consists of inner strips , outer strips and corner springs .

采用通用大型结构线性、非线性有限元分析程序ADINA，对燃料组件与其外侧的燃料元件盒在地震工况下的相互撞击作用进行了非线性动态响应分析；

The finite element program for automatic dynamic increment nonlinear analysis ( ADINA ) is used to predict the non linear dynamic response due to collisions between the fuel assembly and the fuel channel during seismic events .

叉形探测器可用于后处理和贮存工厂中PWR和BWR型的乏燃料组件的燃耗、冷却时间、总钚和总裂变物质含量的测定。

The detector can been used to determine the burnup , cooling time and the contents of whole plutonium and whole fission material in spent fuel assemblies of the PWR and BWR types at a reprocessing and storage facility .

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 .

采用计算流体力学软件CFX4.4和CFX5.5对中国先进研究堆标准燃料组件流场进行了数值模拟。

Numerical simulation of the flow field of the standard fuel assembly in China Advanced Research Reactor is carried out by using computational fluid dynamics software CFX4.4 and CFX5.5 .

结合大庆200MW低温核供热示范工程，针对有盒组件结构的具体特点，提出了地震工况下燃料组件与燃料元件盒相互作用的动态响应分析模型；

The dynamic response of the fuel assembly and fuel channel interaction during a seismic event is analyzed to study the structural characteristics of the reactor fuel assembly as part of the Daqing NHR 200 project .

介绍了NHR-10组件内钆可燃毒物配置、堆芯燃料组件布置和换料方案的改进设计。

This paper introduces the improved NHR 10 core design which includes the arrangement of the gadolinium burnable poison ( BP ), the fuel assembly arrangement and the fuel assembly reloading scheme .

介绍了目前国外燃料组件高燃耗、长周期、低泄漏的发展方向；阐述了研制高燃耗燃料组件定位格架的必要性和可行性。V.C高；

The current development and tendency for fuel assemblies being of low leakage , high burn-up and long cycle fuel reload in the world are presented , and the necessity and feasibility to develop the spacer grid for high burn-up fuel assembly are elaborated .

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

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

燃料组件在地震和失水工况下的结构动力反应分析

Dynamic Response Analysis for Fuel Assemblies under Earthquake and LOCA Accidents

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