核燃料元件

宽频超声无损检测核燃料元件及复合结构技术研究

Development of New Broadband Ultrasonic Testing Technique for Nuclear Fuel Elements and Composites The Design of the Wide Frequency Multiple Dimensional Snubber

本文讨论了核燃料元件中，氦气通过不同标称泄漏率所等效的不同直径的漏孔向大气进行自然泄漏时，其氦气压强随时间变化的规律。

This paper is to discuss the rules by which the helium pressure varies with time when the helium is leaking out into the atmospher from nuclear fuel elements through the different holes equivalent to rated leak rate .

建立从核燃料元件中真空抽提H2并进行气相色谱法测定的真空抽提-气相色谱法。

S : H 2 in nuclear components was extracted in the vacuum glass extraction system and determined by gas chromatography .

文章介绍在宜宾核燃料元件厂（YFP）生产线上进行（U，Gd）O2芯块工业规模的生产试验及产品合格性鉴定，对试验结果进行讨论和评价。

The paper introduces ( U. Gd ) O2 pellet commercial production tests and product qualification on production line of Yibin nuclear fuel element plant ( YFP ) .

核燃料元件生产线区段闭合衡算试验研究报告

Part Close Balance Test Report of Nuclear Fuel Element Production Line

一种用于退役核燃料元件包壳的破裂检测技术

A safety check-up method for decommissioned reactor fuel element cladding

核燃料元件棒包壳管自动切管机的研制

Development of automatic tube cutting machine for cladding tube of nuclear fuel element

核燃料元件单棒焊缝的射线探伤

Radiography inspection of weld for nuclear fuel rod

核燃料元件运输的辐射环境影响

Radiological environmental impacts from transportation of nuclear materials

板形核燃料元件无损检测技术

Nondestructive testing techniques for plate-type nuclear fuel element

研究和建立载铀样品球法，是为了对核燃料元件破损探测系统进行灵敏度标定和稳定性考验。

A Uranium-Carrying Ball method used for the determination of sensitivity , stability of the fuel element failure detecting systems is developed .

本实用新型涉及核燃料元件领域，具体涉及一种压水堆燃料组件上管座。

The utility model relates to the field of nuclear fuel components , in particular to an upper tube seat of a pressure water reactor fuel element .

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 .

本系统集数据采集、数据实时分析、状态监控、统计汇总、生成质检报表于一体，为核燃料元件制造提供了一套数据采集→数据分析→监控→报表的质量管理平台。

Fabrication of Spherical Fuel Element for 10 MW High Temperature Gas-cooled Reactor This system is integrated with the data gathering and real-time analysis , the status monitoring , the statistical summing-up and the generating of quality control .

宜宾核燃料元件厂在AFA3G燃料棒首次产品合格性鉴定中发现，大批下端环缝焊产生了气胀的焊接缺陷。

A number of undercut defects appeared on the electron beam welding ( EBW ) girth welds of bottom end plugs during product qualification of the first lot of AFA 3G fuel rod in Yibin Nuclear Fuel Element Plant .

此装置能使核燃料元件生产中的机械压机单冲模等容压制方式改变为多冲模的等压压制。能提高核燃料及粉末陶瓷产品的质量和产量，具有较好的经济社会效益。

Such device changes the equi-volume pressing mode of single mechanical die to equi-pressure pressing mode of multiple die in nuclear fuel element production , thus improves the quality and raises the quantity of nuclear fuel and powder ceramic products , giving a better economic benefit .

介绍了核电站燃料元件UO2芯块的间隙无损检查仪。

The tester for nondestructive testing the gap between the UO2 pellets of fuel rods is described .

锆合金作为轻水核反应堆燃料元件的包壳材料已得到了广泛的应用并积累了丰富的经验，因而仍被列为SCWR潜在的应用材料。

As a light water nuclear reactor fuel cladding material , Zr alloy has been wide used and its application experience accumulated , hence it is the potential materials for SCWR .

在第二代核电站燃料元件~（235）U丰度无损检查仪中，用微机多道代替了硬件多道，由能谱分析板和计算机多道仿真软件（PHA软件）组成能谱测量系统；

The hardware multichannel is replaced by a computer multichannel analyzer in the second generation of nondestructive testing device for determining 235U enrichment of fuel element in nuclear power plant . The spectrometric analyzer system consists of the spectrometric analysis board and the multichannel emulator software ( PHA ) .

核反应堆燃料元件铝包壳温度测量

Temperature measurements of the aluminium claddings of fuel elements in nuclear reactor

核动力堆燃料元件溶解过程中碘的去除

The removal of iodine in the dissolution process of nuclear power fuel

核动力堆辐照后的核燃料元件中铀和钚的测定方法

A Review of the Metnods for the Determination of the Uranium and Plutonium in the Post-irradiated Nuclear Fuel Elements of Power Reactor

本文概述了核动力堆辐照后的核燃料元件分析样品的特点、样品的溶解和样品中铀和钚的测定方法。

In this review the characteristics and dissolutions of the Samples and the methods for the determination of the uranium and plutonium in the post-irradiated nuclear fuel elements of power reactors are presented .