钠冷快堆堆容器堆内构件用316型不锈钢及其持久断裂性能

316型不锈钢用于钠冷快堆堆容器堆内构件的制造已成为各发展快堆国家的共识,如何提高持久断裂性能成为快堆用316型不锈钢的研究重点。概述了316型不锈钢在国外快堆中的应用现状,总结了成分(C、N、Mo、P)、组织(晶粒度和铁素体)及环境介质(中子辐照环境和高温钠介质)等因素对其持久强度和持久伸长率的影响规律和机理,介绍了目前中国示范快堆用316不锈钢的发展现状,最后提出了快堆用316不锈钢的发展建议。     

中国铅基堆冷却剂技术取得重大突破

正中科院核能安全技术研究所先进核能研究团队(FDS团队)牵头的"麒麟一号"中国铅基快中子反应堆研发工作取得重大突破,权威专家组一致认为:铅基堆冷却剂技术综合实验回路的实验能力和运行参数处于国际领先水平,突破了氧测量与控制等多项关键技术,打破了国际垄断,实现了核心技术自主化,对促进我国第四代核能铅基反应堆的工程化具有重要意义。铅基堆被"第四代核能系统国际论坛"组织评定为有望首个实现工业示范和商业应用的第四代核裂变     

世界最大的铅铋回路试验装置建成

正中科院核能安全技术研究所成功建成世界最大的铅铋回路试验装置,多项技术处于国际领先水平,为提升中国在先进核能领域的国际竞争力起到重要作用。据悉,中科院核能安全技术研究所建成"多功能铅铋堆技术综合实验回路KYLIN-II"已通过包括中国核动力研究设计院、中国原子能科学研究院在内的专家评审。评审专家组一致认为:"该装置是世界最大的多功能液态铅铋综合实验平台,回路规模、设计与综合实     

粉末冶金技术在新能源材料中的应用

新能源的开发和利用是解决人类能源问题的唯一办法,新能源材料是发展和利用新能源的关键所在.粉末冶金作为一门先进的新材料制备与合成技术,在新能源材料的发展过程中起到了关键性的作用.本文详细介绍了粉末冶金技术在核能材料、风能材料、太阳能材料、锂离子电池材料、储氢材料、燃料电池材料中的应用.     

镁及镁合金材料的应用及其加工技术的发展

本文较全面地介绍了镁及镁合金材料在交通运输、航空航天、电子工业、核能工业、化工、冶金等部门的应用方向与实例；简扼地论述了镁合金材料的加工技术。重点介绍了镁合金新材料的研发、熔炼铸造工艺、压铸成型工艺、挤压技术、锻压技术与轧制技术的进展。指出镁合金是一种很有发展前景的新型金属材料，其加工技术将获得进一步的快速发展。     

快中子反应堆核心结构材料的辐照损伤

快中子反应堆(快堆)的核心结构材料(如燃料包壳等)在服役过程中将承受长期的高通量的中子辐照、高温和嬗变反应产生的He的作用,引起的合金微观结构的改变,导致材料力学性能的严重恶化.高性能抗辐照材料成为快堆发展的关键前提条件之一.本文介绍快堆中辐照引起的金属材料微观结构的变化.     

快中子堆用碳化硼材料的成分和性能设计

快中子堆在最终解决世界能源问题中占有十分重要的地位,碳化硼是快中子堆国际普遍接受的中子吸收材料,作者综述了快堆对材料的要求以及碳化硼的优点和限制,评述了碳化硼芯块密度、硼碳比、晶粒度、热传导率、杂质铁含量等对作为寿命限制参数的氦释放率和肿胀率的影响,提出了材料设计的观点。     

鞍钢攻克中国核电装备材料“卡脖子”难题

正日前,鞍钢成功实现四代核电600 MW示范快堆项目316H奥氏体不锈钢产品开发,并完成首批合同供货,解决了该产品从无到有的"卡脖子"难题。鞍钢因此成为全球唯一一家全部依靠自身装备生产该产品的企业。随着世界各国经济发展和环境恶化压力,建造核电、利用核能已成为未来10至20年的重点。中国在核电开发、建设方面已取得了重大进展,三代核电技术达到世界先进水平,四代核电技术达到国际     

鞍钢集团钢铁研究院获国家核电赞誉

正近日,鞍钢集团钢铁研究院清洁能源用钢团队收到了来自国家核电技术有限公司的感谢信——"在过去的一年里,我们全面落实国家电投与鞍钢集团加强合作要求,聚焦核电材料自主技术创新,携手推进核能产业高质量发展。2021年,希望双方在新型核电材料开发、核电用钢质量提升研究等领域精诚合作,推动我国核电材料国产化研发取得新成就。"2020年以来,该院在关键核心技术攻关、重点产品研发、     

中国能源工业发展对钢铁材料技术的挑战

简要介绍了中国能源工业的现状、发展趋势以及能源工业发展对关键钢铁材料技术的挑战性需求。重点介绍了我国超超临界火电机组建设、大型先进压水堆核电站建设、核聚变堆预研工程对关键钢铁材料技术的需求和推动。也介绍了石化工业发展对钢铁材料技术的需求。能源工业是国民经济快速、持续发展的动力所在，钢铁材料技术是支撑能源工业发展的最重要基础。     

Materials R & D for sodium-cooled fast reactor in China

The study gives a brief introduction on development of innovated nuclear system in China,mainly focus on the materials R&D status for the sodium cooled fast reactor.With the high speed development of economy,China needs a huge energy supply;at same time a more cleaning energy to reduce the carbon release is demanded.The nuclear energy is the most cleaning energy at present time,especially the innovated nuclear system which is so-called GenerationⅣpower plants has got its prior development due to its safety, economical and little fission production produced.Fast breeder reactor,as the priority development reactor type in the Gen-Ⅳnuclear system,is the key to the advanced closed fuel cycle technologies.China experimental fast reactor(CEFR ) has been completed the design,construction the synthesis system commissioning and reached its physical criticality on July 21,2010.At China Institute of Atomic Energy,the CEFR and other research facilities have been established,and extensive studies are planning to carry out in the areas of fuel and materials development.This will laid the foundation for the design and development of the future’s CFR—900(China Demonstration Fast Reactor) and CCFR(China Commercial Fast Reactor). Highlights of some of materials R&D studies are discussed in this paper.     

A perspective on creep and fatigue issues in sodium cooled fast reactors

Development of advanced materials alongwith improved high temperature mechanical properties, particularly creep and fatigue are important and play a major role for the successful development of robust, safe and economical sodium cooled fast reactor (SFR) technology. The components of SFRs operate in demanding environments at high temperatures under complex creep, fatigue and creep-fatigue loading conditions. Based upon the service requirements in terms of different environments, temperature and loading conditions, different materials are chosen for different components. Ti modified 15Cr-15Ni austenitic stainless steel is chosen for clad and wrapper tubes in the reactor core, which experience high fast neutron flux of ～ 10¹⁵ ncm^?2s^?1 along with high temperatures. Type 316L(N) SS is used for out-of-core structural components like main and inner vessels, and sodium pipelines. For steam generators, modified 9Cr-1Mo steel is chosen for all the components, where liquid sodium and steam/water coexist. Some of the important experiences and exciting achievements in the areas of in-house materials development and its characterization in terms of creep, low cycle fatigue and creep-fatigue properties important to design of reactor components for core, out-of-core and steam generator applications are described in the paper. Future directions for materials research and development activities involving critical issues like radiation damage resistance along with improved mechanical properties for advanced clad and wrapper materials necessary for achieving high fuel burnup and design life up to 60 years for out-of-core structural components leading to economical nuclear energy have been highlighted.     

Cr和Si元素对奥氏体不锈钢组织构成及凝固路线的影响

以316Ti奥氏体不锈钢为基础,设计不同Cr和Si元素含量的合金成分,结合Thermal-Calc热力学模拟计算与合金铸锭凝固组织形貌、成分分析,研究了Cr和Si元素对合金凝固组织构成的影响。研究结果表明,热力学计算能够获得奥氏体不锈钢中析出δ相的临界Cr和Si含量。合金凝固时的元素偏析和冷却过程中的“δ→γ”相变可对δ相析出预测产生一定影响。此外,本工作还针对δ相析出评价了两种凝固路线判据。      

金属增材制造技术在核工业领域的应用与发展

增材制造能够制备任意复杂形状的零件,具有快速、高效、经济、全智能化和全柔性化制造的优势.本文总结了国内外典型的金属增材制造技术,介绍了金属增材制造技术在核工业领域的应用,梳理了增材制造核材料产品的性能表现,并以实际案例证明了金属增材制造技术在核工业领域的优势.本文结合革新性反应堆技术在核材料中的应用背景,展望了增材制造...     

钢铁材料技术国产化是实现核电产业自主化的基础

未来20年中国将迎来核电建设的高潮,钢铁材料技术是核电站建设最关键的支撑技术之一。中国的冶金与机械行业在遭遇巨大发展机遇的同时也面临着严峻的挑战。分析了目前中国民用核电用关键钢铁材料技术的现状和存在的问题,思考了国产化过程中的相关问题。     

UNITED STATES EXPERIENCE IN POWDER METALLURGY FOR NUCLEAR APPLICATIONS

Abstract

The types of problems encountered in the use of powder components for nuclear reactor cores are discussed. Examples are given of processes and experience related to the application of standard powder techniques to nuclear materials, use of novel methods for the production of nuclear materials, adaptation of commercial powder products for in-reactor use, and development of unique materials.     

核反应堆堆芯用HEA304电渣锭的试制

HEA304为低碳奥氏体不锈钢,具有优良的高温性能、抗腐蚀性及抗辐射性,主要用于核反应堆堆芯材料,该钢种电渣重熔后易出现碳、氮、晶粒度超标,经过对电渣重熔渣系及电渣工艺的摸索试验,确定电渣重熔渣系及工艺要点,并经锻造、热处理工艺处理,可以生产出优质的核材用HEA304锻件,满足标准要求。     

我国核电承压设备用钢的发展现状与研究方向

分析了我国核电承压设备（反应堆压力容器、主管道、蒸发器、稳压器和安全壳等）用钢的发展现状与发展方向,并指出某些元素在核电承压设备用钢中的作用及对其辐照脆化的影响。分析认为,为了确保核电承压设备用钢的使用性能和安全性能,必须严格控制残余元素水平、组织形态等,保证锻压比和后期退火工艺参数。     

Ti–5Ta–1.8Nb: An Advanced Structural Material for High Performance Application in Aggressive Oxidising Environments

It is well known that Ti and Zr based alloys are best suitable for oxidizing environments due to their superior corrosion resistance. This has been exploited in the development of the ternary Ti?CTa?CNb alloy, for the dissolver in a fast reactor fuel reprocessing plant, the efforts of which are summarized in the present overview. Closing of fuel cycle is a priority for the three stage nuclear power program of India, towards which, indigenous development of reprocessing technology and materials is an important milestone. Corrosion resistance of structural materials controls the operating life of the dissolver in a nuclear reprocessing plant, where the spent nuclear fuel is dissolved in highly oxidizing boiling nitric acid. A complete physical metallurgy database of the alloy has been generated to understand the various phase transformations and the resultant microstructures. Corrosion control in different phases of nitric acid is achieved through microstructural optimization and the mechanisms of corrosion are understood using a detailed study of passive oxide film. The dependence of transformation texture on the mode of deformation and the role of severe plastic deformation on mechanical properties have been elucidated. These extensive R&D efforts resulted in a complete understanding of the metallurgy the alloy, which is discussed in this overview.     

钢铁工业“十二五”发展规划对科技发展的新要求

对我国钢铁工业“十一五”进行了基本的概括总结,结合“十二五”发展规划的编制对“十二五”期间我国钢铁工业面临的主要问题、发展环境、市场消费预测、主要目标、重点领域和任务进行了全面阐述,分析了“规划”对科技发展的新要求。