核电工程核岛焊接综合管理

核电工程的焊接管理离不开前期的策划.针对核电核岛工程,从焊接工程的组织管理、技术管理、施工管理、信息化管理方面提出基本设想,以供进入核电建设,特别是核岛焊接的承包商参考.     

Cladding and duct materials for advanced nuclear recycle reactors

The expanded use of nuclear energy without risk of nuclear weapons proliferation and with safe nuclear waste disposal is a primary goal of the Global Nuclear Energy Partnership (GNEP). To achieve that goal the GNEP is exploring advanced technologies for recycling spent nuclear fuel that do not separate pure plutonium, and advanced reactors that consume transuranic elements from recycled spent fuel. The GNEP’s objectives will place high demands on reactor clad and structural materials. This article discusses the materials requirements of the GNEP’s advanced nuclear recycle reactors program.     

民用核安全设备焊接材料验收

民用核安全设备焊接材料的验收是指民用核安全机械设备制造和安装阶段RCC-M规范级设备用焊接材料的验收,焊接材料验收的目的是为了保证核岛机械设备在制造和安装过中所用的成批焊材具有稳定的质量,并保证其质量符合订货技术条件的要求。主要探讨了民用核安全设备焊接材料验收的内容以及焊接材料验收的步骤,为民用核安全设备焊接材料的验收提供参考。     

Mo-Re合金研究进展

“Re效应”使得Mo的理化、热电、力学、加工焊接性能得到全面改善。Mo-Re合金由于具有良好的综合性能，被广泛应用于先进核能、航空航天、电子工业、生物医用等领域。尤其是优异的抗辐照性能、与核燃料及碱金属冷却剂的相容性、中子特性等核物理性能，使其成为核反应堆堆芯结构材料的首选。本文从晶体结构、组织性能、制备加工及应用4个方面系统综述了Mo-Re合金的研究现状，并对其发展前景进行了展望。     

核电工业的发展及其对腐蚀防护技术的需求

从能源需求的角度，概述了世界各国以及我国核电工业的发展趋势，并针对压水堆，重水堆，快堆，高温气冷堆，聚变堆等的各自特点，并以压水堆为重点，简介了它们对腐蚀科学和防护技术的研究与开发的特殊要求。     

Nuclear production research expands materials knowledge

Several advances in materials technology have resulted from the operation of the Savannah River nuclear materials production facility in Aiken, South Carolina. Among the research contributions of the Savannah River Site (SRS) to materials science and engineering are a greater understanding of stress-corrosion cracking and hydrogen embrittlement, and the development of technologies utilizing nuclear sources for heat and radiation. These advances arose from the technologies developed at SRS for the production, separation and packaging of nuclear materials.     

Advances in nuclear fuel elements

More than 500 nuclear scientists and engineers from 22 nations gathered at Columbia University for the First International Symposium on Nuclear Fuel Elements, sponsored jointly by Columbia and Sylvania-Corning Nuclear Corp. Their conclusion: better materials will be needed before economic nuclear power becomes a fact of everyday life.     

锆材在核电站的应用及前景

锆合金因其优良的核性能和适宜的机械性能，在核电反应堆中作为包壳材料和结构材料得到了广泛应用。介绍了锆合金包壳管材在核电站中所起的重要作用，具体用途、用量，以及我国锆合金材料的研制和生产现状。指出随着我国核电事业的发展，对锆合金材料的需求仅更换的包壳管到2010年将达到120t，我国应加速核电用锆合金材料的国产化进程，这样才能自主地发展我国的核电事业。     

Nuclear resonance reflection of synchrotron radiation from thin dysprosium films with different types of magnetic ordering

Epitaxial thin films of dysprosium have been successfully synthesized by the method of high-vacuum magnetron sputtering and their structure and magnetic properties have been investigated. The opportunity of the nuclear resonance scattering for the investigation of nanostructures containing ¹⁶¹Dy has been considered; the specific features of the spectra of nuclear resonance reflectivity from the films have been analyzed on the energy and time scales at different orientations of the magnetic hyperfine field. The simulation of the angular dependences of nuclear resonance reflectivity for the case of spiral ordering in periodic structures containing ¹⁶¹Dy has been carried out. It has been shown that these dependences make it possible to uniquely determine the period of magnetic ordering.     

Materials in Nuclear Waste Disposition

Commercial nuclear energy has been used for over 6 decades; however, to date, none of the 30+ countries with nuclear power has opened a repository for high-level waste (HLW). All countries with nuclear waste plan to dispose of it in metallic containers located in underground geologically stable repositories. Some countries also have liquid nuclear waste that needs to be reduced and vitrified before disposition. The five articles included in this topic offer a cross section of the importance of alloy selection to handle nuclear waste at the different stages of waste processing and disposal.     

ECT benchmark results for 3D defect signatures in industrial applications

This paper is focused on the Eddy Current Testing (ECT) method applied to important industrial applications such as the inspection of tubes in nuclear power plants and the inspection of planar surface from aeronautical industry. Specifically, we consider the prediction of the signatures produced by small defects through two fully three-dimensional numerical models developed for ECT. In particular we consider the responses to small defects described in two experimental benchmarks from nuclear power industry and one experimental benchmark from aeronautical applications. Despite of the small size of the defects that, in some cases, is of the order of few millimetres, the numerical models reproduce correctly the experimental responses provided in the benchmarks, including the challenging case of a defect (in a tube) close to the support plate.     

我国核电站老化与寿命管理数据质量的表征

老化与寿命管理技术研究是进行核电站寿命与安全分析的重要手段。数据是开展具体研究的核心纽带,而数据质量的问题严重制约了相关研究技术的推进与发展。本文从我国核电站老化与寿命管理的起因及相关技术研究的现状出发,系统地梳理了核电站老化数据的来源与特点,利用层次分析的观点,引入数据全生命周期的概念,提出影响数据质量的主要因素以及数据表征的体系结构,为开展核电站老化与寿命管理数据质量问题的研究提供重要参考。     

核废料中裂变产生的铂族金属（FPs）的开发、应用和发展

在核废料中存在大量的由核裂变反应产生的铂族金属（FPs：包括Ru，Rh和Pd）。目前全世界的核废料中FPs的总量可以和自然界储量相比拟。并且随时间推移FPs的总量还会增加。未来FPs将是铂族金属的一个重要资源。本文介绍了FPs在核废料中的存在形式以及常见提取方法。详细给出了FPs中各种核素的放射性质，阐述了开发和利用FPs的基本观点、方法和思路。介绍了FPs在核工业和高纯氢气制造上的应用，以及其它潜在的FPs应用领域。     

压水堆核电站在役检查用无损检测技术发展概况

核电站在役检查是核电站安全运行的重要保证手段之一,核安全法规和导则对核电站核安全设备的役前和在役检查提出了明确的要求。介绍了压水堆核电站在役检查用无损检测技术的发展历程、相应的在役检查标准和规范的使用状况。总结了当前国内外核电站在役检查技术能力验证的实施现状,对我国自主开展核电站在役检查和能力验证工作提供借鉴。     

我国核电用无缝钢管国产化的新进展

目前我国核电工业正处于发展高峰期,核电装备及制造材料的国产化势在必行.实践表明,我国核电用无缝钢管国产化成效显著.介绍了核电站建设和核电设备制造对无缝钢管提出的质量要求,分析了我国核电用无缝钢管在国产化进程中取得的成绩和存在的主要问题,提出了进一步加速核电用无缝钢管国产化进程的建议.     

铀材料制备与铀部件成形技术发展综述

金属铀作为一种战略核材料,在人类历史上起着举足轻重的作用。在核工业需求的牵引下,铀及其合金部件的成形制造技术也在不断发展。本文从工程角度梳理了铀材料制备及铀部件成形技术的发展,具体介绍了铀合金制备和铀材料纯化技术,并主要从塑性成形和铸造成形两方面说明了铀部件的制造方法。针对铀部件制造的特殊性,指出面向未来其技术更加关注于安全性、环保性和智能化的发展趋势。     

核电厂倾翻机水液压技术研究

倾翻机是核电厂装换料系统的关键设备之一,它基于水液压传动,实现燃料篮在屏蔽水层下的平稳翻转到位,是核电厂中的一种特殊机械设备.介绍核电厂倾翻机的功能和结构,并分析倾翻机的材料要求、水液压系统设计、质量保证、安装调试及载荷试验等多项关键技术,为核电厂其他设备的设计、制造、安装及调试提供了参考.     

DR与传统胶片技术在核电检测中的能效对比

从人员投入、占用时间、现场实施、成本投入等方面对数字射线成像(DR)技术和胶片射线检测技术在核电厂大修检测的实际应用情况进行了能效对比,为数字射线成像技术在核电领域的进一步应用提供支撑.通过数据分析可知,DR检测技术的应用还有较大的提升空间,但是在很长的一段时间内,DR检测技术和胶片检测技术仍将并行存在,相辅相成.     

核电用管现状及国产化进展

随着我国大型核电站建设的快速发展,核电站设备国产化进程明显加快,对核电用无缝钢管的国产化要求也日益迫切。简介了核电用管的特点及质量要求,分析了核电站管道系统用无缝钢管的国产化进展和存在的问题,提出了核电用无缝钢管全部国产化的建议和改进思路。