摘要
随着人类生活水平的不断提高,全球对于能源的需求量也急剧增加,伴随着化石能源的可开采量逐年减少,以及人类对环保的更高要求,核能作为一种高效的清洁能源,已被世界各国作为能源结构的重要组成部分。根据世界核电协会(WNA)日前发布的《2018年版核电行业状况报告》,至2017年底全球共有448台在运核电机组,总装机容量为392GW(比2016年增加2GW),平均容量系数为81%,发电量达到2506TWh(比2016年增长20TWh)。预计2018—2019年将有25台核电机组竣工,核电发展将迎来一个小高潮。目前,我国在建和筹建的核电厂基本都采用压水堆(PWR)堆型,作为反应堆的“心脏”,核反应堆压力容器的设计对整个核电建设项目都至关重要。由于材料在使用中不可避免地会出现老化和降级现象,对于时刻处于辐照环境下的核反应堆压力容器来说,材料的选择更是满足其使用条件的关键一环。最早时期的压力容器采用SA212B板材,后面陆续开始采用SA302.B和SA533B钢,最终被SA508系列锻件所替代。目前,SA508系列锰钼镍低合金钢已被广泛运用于核反应堆压力容器的制造,包括顶盖、筒体、法兰、封头等均可使用。近年来,研究人员通过调整化学成分开发出了新的压力容器备选材料———SA-508Gr.4N钢,强度等级已经从620MPa提升到725MPa,低温冲击性能也有了大幅提高。研究者们针对其力学性能和组织变化进行了大量研究,分析了其性能提升的主要原因,并取得了一定的成果。较目前广泛使用的SA-508Gr.3钢而言,新一代材料SA-508Gr.4N钢具有更好的强度和硬度,且低温韧性优良。本文针对SA-508Gr.4N钢的研制背景、材料性能研究现状、配套焊材开发现状,基于国内外已有研究成果进行了综述。结果表明,SA-508Gr.4N钢可作为未来核反应堆压力容器的推荐用材料。但与其匹配的焊材研制及应用性能研究数据匮乏是制约该材料推广应用的技术短板,基于已有研究基础,本文提出了后续SA-508Gr.4N钢推广应用的重点研究方向:焊材设计指标制定、焊材制造及焊接工艺优化、接头微观组织与性能演变规律研究。
For the continuous improvement of human living standards,the world’s demand for energy has also increased dramatically. With the annual reduction of fossil energy and the higher requirements of human beings for environmental protection,nuclear power,as an efficient and clean energy,has been an important part of the energy structure of many countries. According to the“2018 version of the nuclear power industry status report”released by the World Nuclear Association ( WNA) recently,by the end of 2017 there are 448 nuclear power units in operation,the total installed capacity have been 392 GW ( 2 GW more than 2016),and the average capacity coefficient has been 81%,power generation capacity has reach 2 506 TWh ( 20 TWh more than 2016). It is expected that 25 nuclear power plants will be completed in 2018-2019,and nuclear power development will usher in a small climax. At present,the nuclear power plants under construction and planned construction in China are basically Pressure Water Reactor ( PWR) type. As the“heart”of the reactor,the design of nuclear reactor pressure vessel is very important to the whole nuclear power construction project. Due to the inevitable aging and degradation of materials in use,the selection of materials is the key to satisfy the operating conditions of nuclear reactor pressure vessel under irradiation. The earliest pressure vessels were manufactured by SA 212B sheet,followed by SA302.B and SA533B steel,and eventually was replaced by SA508 series forgings. At present,SA508 series Mn-Mo-Ni low alloy steel has been widely used in the manufacture of nuclear reactor pressure vessel,including the top cover,cylinder, flange,head and other forgings. In recent years,researchers have developed new pressure vessel alternatives by adjusting the chemical composition-SA-508 Gr.4N steel. The strength level has been increased from 620 MPa to 725 MPa,and the low-temperature impact performance has also been greatly improved. Researchers have done a lot of research on the mechanical properties and microstructure changes of SA-508 Gr.4N steel,and analyzed the main reasons for the improvement of mechanical properties,and made some achievements. Compared with SA-508 Gr.3 steel,the new generation material SA-508 Gr.4N steel has better strength and hardness properties,as well as excellent strength and toughness. In this paper,based on the existing research results at home and abroad,the research background,material properties and matching welding materials of SA-508 Gr.4N steel are summarized. The results show that SA-508 Gr.4N steel can be used as a recommended material for future nuclear reactor pressure vessels. However,the lack of research data on the development and application performance of the matching welding material is the technical shortage that restricts the popularization and application of the material. Based on the existing research foundation,this paper puts forward the key research direction of the subsequent popularization and application of SA-508 Gr.4N steel: the design index of welding material,the manufacture of welding material and the optimization of welding process,the microstructure and property evolution of joint.
作者
李今朝
陈亮
黄腾飞
匡艳军
邱振生
LI Jinzhao;CHEN Liang;HUANG Tengfei;KUANG Yanjun;QIU Zhensheng(China Nuclear Power Design Company,Ltd ,Shenzhen 518172)
出处
《材料导报》
EI
CAS
CSCD
北大核心
2019年第A01期382-385,共4页
Materials Reports
基金
国家重点研究发展计划项目(2017YFB0305300)~~
作者简介
李今朝,2016年6月毕业于武汉理工大学,获得材料加工工程硕士学位。同年加入深圳中广核工程设计有限公司,主要从事核电设备的设计及焊接工艺研究。lijinzhao2@cgnpc.com.cn.
