反应堆乏燃料棒的X射线数字成像检测工艺及其应用

X射线数字成像检测技术是一种可实时成像的无损检测技术,为了将该技术应用于燃料棒辐照后的检验中,建立了一套完整地适用于高放射性环境中使用的成像装置。通过对检测对象特点和检验工艺的分析确定了合适的检测参数,经过对人工缺陷模拟件的检测,获得的图像质量满足检测精度的要求。该技术已经成功应用于反应堆燃料性能评价及破损燃料失效分析等工作中。     

射线Ⅲ级人员补充专题讲座（续）

第7专题实时成像检验技术71概述射线实时成像检验技术．是实时地将射线照相的强度分布转换为可见光图像、对检验结果作出评定的技术．这种技术几乎与胶片射线照相检验技术同时发展。主要的实时成像检验技术有：（1）X射线荧光实时成像检验技术；（2）图像增强实时成像检验技术；（3）数字实时成像检验技术。表7－1列出了三种检验技术系统的主要待点。早期的射线实时成像检验系统是X射线荧光检验系统．它采用荧光屏将X射线照相的强度分市转换为可见图像．50年代左右引入了电视系统．通过电视摄像、在监视器上观察图像。荧光屏图像由于存在…     

大型整体复杂精铸构件的X射线检验

大型复杂精铸构件的检测因其腔体结构复杂而成为无损检测所面临的一个难题。X射线照相检验是一种经济实效的检测方法。本文对某复杂构件的X射线照相检验技术进行了研究和具体试验。     

射线实时成象检验技术

射线实时成象检验技术,是实时地将射线照相的强度分布转换为可见光图象、对检验结果作出评定的技术,这种技术儿乎与胶片射线照相检验技术同时发展.主要的射线实时成象检验系统有:(1)X射线荧光实时成象检验系统.(2)图象增强实时成象检验系统.(3)数字实时成象检验系统.表1列出了三种检验技术系统的主要特点.     

第七讲射线实时成象检验技术

1　概述射线实时成象检验技术是随着成象物体的变动图象迅速改变的电子学成象方法 ,它与胶片射线照相检验技术几乎是同时发展的。早期的射线实时成象检验系统是 X射线荧光检验系统 ,它采用荧光屏将 X射线照相的强度分布转换为可见光图象。 50年代左右引入了电视系统 ,通过电视摄象 ,在监视器上观察图象。由于存在图象亮度低 (仅为 0 .3× 1 0 -3cd/m2左右 )、颗粒粗、对比度梯度低等缺点 ,荧光屏图象的细节和灵敏度都低于胶片图象 ,观察这种图象需 30 min的眼睛暗适应时间 ,这限制了该技术的实际应用。这种系统主要应用于轻合金铸件、薄焊…     

第六讲射线照相标准与射线照相检验质量控制

1　射线照相标准概述目前 ,国内外制订的射线检验标准 ,按内容可分为射线照相检验技术 (或方法 )、射线照相检验质量控制、射线照相检验参考底片、射线照相检验的术语和器材等方面的标准。美国材料试验学会 ( ASTM)关于射线照相方面的标准共计 55项 ( 1 998年版 ) ,其中参考底片类标准 1 5项、射线照相检验质量控制方法标准 1项、射线检验试验方法标准 1 4项、射线检验操作方法标准 1 3项以及射线检验导则标准 1 2项。 ASTM是世界上射线检验标准制订得最多的标准体系 ,在试验方法标准、操作方法标准和导则标准中 ,不仅有常规射线照相标…     

CR和DR成像技术

本文对数字化X射线照相检测技术应用中关于计算机射线照相检测(CR)和直接数字化照相(DR)以及胶片扫描数字成像系统(FDR)的基本原理、应用以及设备做了较系统的介绍,有助于无损检测技术人员对目前最新型的数字化X射线照相检测技术的了解。     

第一专题 对比度与半值层

射线照相是一种十分普遍的无损检测方法。随着科学技术的进步,X射线实时成象检验系统在工业中的应用也越来越多。怎样获得优质影象以确保探伤灵敏度,始终是每个射线检测人员关心的课题。 有关文献中虽说射线照相的灵敏度是由影象的对比度和清晰度共同决定的,但只是深入研究了对比度,而清晰度却从来没有被严格定义过,更谈不上有什么数学公式可供计算。即使如此,对比度的研究还是没有完全脱离窄束X射线模式的影响,只是在窄束X射线情况的基础上加些修正后去解释射线照相检验中宽束X射线所得的结果。理论和现实的差距是明显的。 为了研究的需要,把清晰度定义为影象与背景之间的黑度梯度,并为透度计钢丝和测试分辨力用的光栅建立了成象数学模型,编制了计算程序。结合不同的射线源和试件的照相实例,把理论计算结果和实际视觉效果相对照,寻找出适应探伤要求的对     

射线实时成像检验技术与射线照相检验技术的等价性讨论

在分析射线照相检验技术的有关规定的基础上，提出了射线实时成像检验技术在与射线照相检验技术具有同等缺陷检验能力情况下的等价性指标。对射线实时成像检验技术的应用具有重要意义。     

工业射线照相的辐射防护标准 --答读者问

问:关于工业射线照相检验的辐射防护我国制订了哪些标准?对X和γ射线照相检验的辐射防护有些什么规定?(张玉明)1　我国有关辐射防护的标准目录我国已制订了一系列有关辐射防护的标准,2002年国家标准目录中给出的与工业射线检测有关的辐射防护标准目录可分为如下四个部分。1.1　辐射防护总规定标准目录GB4792—1984　放射卫生防护基本标准GB8703—1988　辐射防护规定1.2　辐射防护管理标准目录GB5294—2001　职业照射个人监测规范　外照射监测GB9662—1988　电离辐射事故干预水平及医学处理原则GB/T11712—1989　用于X,γ线外照射…     

Transient Testing of Nuclear Fuels and Materials in the United States

The United States has established that transient irradiation testing is needed to support advanced light water reactors fuel development. The U.S. Department of Energy (DOE) has initiated an effort to reestablish this capability. Restart of the Transient Testing Reactor (TREAT) facility located at the Idaho National Laboratory (INL) is being considered for this purpose. This effort would also include the development of specialized test vehicles to support stagnant capsule and flowing loop tests as well as the enhancement of postirradiation examination capabilities and remote device assembly capabilities at the Hot Fuel Examination Facility. It is anticipated that the capability will be available to support testing by 2018, as required to meet the DOE goals for the development of accident-tolerant LWR fuel designs.     

Combining impedance and galvanostatic measurements for the study of oxide films formed on zirconium-based E-635 alloy under high-temperature oxidation conditions

Protection of Metals and Physical Chemistry of Surfaces - Impedance measurements for oxide films on zirconium-based E-635 alloy that is used as cladding for fuel rods in nuclear reactors are...     

核电站燃料棒焊缝X射线检测质量监督

在实践的基础上,较全面地介绍了核电站燃料棒焊缝X射线检测质量监督的必要性、监督依据和内容以及监督的实施情况。     

The Influence of Process Equipment on the Properties of Suspension Plasma Sprayed Yttria-Stabilized Zirconia Coatings

Suspension plasma-sprayed YSZ coatings were deposited at lab-scale and production-type facilities to investigate the effect of process equipment on coating properties. The target application for these coatings is solid oxide fuel cell (SOFC) electrolytes; hence, dense microstructures with low permeability values were preferred. Both facilities had the same torch but different suspension feeding systems, torch robots, and substrate holders. The lab-scale facility had higher torch-substrate relative speeds compared with the production-type facility. On porous stainless steel substrates, permeabilities and microstructures were comparable for coatings from both facilities, and no segmentation cracks were observed. Coating permeability was further reduced by increasing substrate temperatures during deposition or reducing suspension feed rates. On SOFC cathode substrates, coatings made in the production-type facility had higher permeabilities and more segmentation cracks compared with coatings made in the lab-scale facility. Increased cracking in coatings from the production-type facility was likely caused mainly by its lower torch-substrate relative speed.     

辐照条件对U10Mo-Al弥散型燃料肿胀性能的影响

通过建立微球燃料元件模型,对U10Mo-Al弥散型燃料在不同辐照条件下的辐照肿胀性能进行模拟计算,结果表明：辐照温度越高,燃料肿胀越明显;随着裂变率的增加,在燃耗拐点以前,燃料的肿胀速率基本相同,在燃耗拐点以后,裂变率大的燃料肿胀较慢;与实验数据点进行比较,在合理的范围内理论值和实验值相一致。     

Advances in Metallic Nuclear Fuel

Metallic nuclear fuels have generated renewed interest for advanced liquid metal reactors (LMRs) due to their physical properties, ease of fabrication, irradiation behavior, and simple reprocessing. Irradiation performance for both steady-state and transient operations is excellent. Ongoing irradiation tests in Argonne-West’s Idaho-based Experimental Breeder Reactor II (EBR-II) have surpassed 100,000 MWd/T burnup and are on their way to a lifetime burnup of 150,000 MWd/T or greater. Metallic fuel also has a unique neutronic characteristic that enables benign reactor responses to loss-of-flow without scram and loss-of-heat-sink without scram accident conditions. This inherent safety potential of metallic fuel was demonstrated in EBR-II just one year ago. Safety tests performed in the reactor have also demonstrated that there is ample margin to fuel element cladding failure under transient overpower conditions. These metallic fuel attributes are key ingredients of the integral fast reactor (IFR) concept being developed at Argonne National Laboratory.     

铝制散热器焊接工艺对防腐涂料附着力的影响

目前绝大多数铝制散热器厂家均采用钎焊工艺焊接使用的铝硅合金焊丝，导致钎缝处的硅量很高.因此在漆前表面处理过程中，钎缝处会发生选择性腐蚀，从而析出大量的、疏松乱堆的硅微粒；这种微粒会极大的恶化钎缝处漆膜附着力下降.与钎焊不同，氩弧焊焊缝性质与母材性质十分接近，完全不存在上述问题.      

Lochfraß- und Kontaktkorrosion an magnesiumumhülten Spaltstoffelementen

Pitting and contact corrosion in magnesium-canned fuel rods When nuclear fuel elements — containing Mg, graphite and Zircaloy — are stored in water there is the danger of contact corrosion of Mg in contact wit graphite; in partcular when cholorides are present (even in traces) there exists the danger of pitting corrosion. Only at pH values > 11,5 a bydroxide layer is formed which yields a certain protection. The pitting potential in alkaline waters is shifted to more negative values with incrasing chloride contents; this displacement can be prevented by inhiitors. Most efficient is the addition of sodium carbonate which gives rise to the formation of a protective hydromagnesite layer.     

Possible ways for protecting fuel claddings from corrosion on the side of the heat-transfer lead sublayer

Analysis of corrosion processes in fuel element claddings under the action of neutron irradiation in the presence of the heat-transfer lead sublayer is performed. Threshold values of oxygen content in the lead are computed. The corrosion behavior of steel components is considered for an operating reactor. Results of tests of cladding material at 700°C under various conditions (in the presence and absence of UN fuel, in pure lead, and in lead alloyed with steel components, etc.) are presented. Methods for protecting the internal surface of fuel claddings from corrosion are suggested.     

A review of TRISO-coated particle nuclear fuel performance models

The success of high temperature gas cooled reactor depends upon the safety and quality of the coated particle fuel. The understanding and evaluation of this fuel requires the development of an integrated mechanistic fuel performance model that fully describes the mechanical and physicochemical behavior of the fuel particle under irradiation. In this paper, a review of the analytical capability of some of the existing computer codes for coated particle fuel was performed. These existing models and codes include FZJ model, JAERI model, Stress3 model, ATLAS model, PARFUME model and TIMCOAT model. The theoretic model, methodology, calculation parameters and benchmark of these codes were classified. Based on the failure mechanism of coated particle, the advantage and limits of the models were compared and discussed. The calculated results of the coated particles for China HTR-10 by using some existing code are shown. Finally, problems and challenges in fuel performance modeling were listed.