Materials Reports  2019, Vol. 33 Issue (z1): 382-385 |
| METALS AND METAL MATRIX COMPOSITES |
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| Research Progress on SA-508 Gr.4N Pressure Vessel Steel |
| LI Jinzhao, CHEN Liang, HUANG Tengfei, KUANG Yanjun, QIU Zhensheng
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| China Nuclear Power Design Company, Ltd , Shenzhen 518172 |
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Abstract 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.
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Published: 05 July 2019
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| About author:: Jinzhao Li received his M.S. degree in June 2016 from Wuhan University of Technology in material processing engineering. He is currently an assistant engineer in China Nuclear Power Design Company (CGNPC), focusing on the research of welding process and design of nuclear equipments. |
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1 王小彬, 李玉光, 罗英, 等. 一重技术,2015(3),18.
2 Min-Chul Kim, Sang-Gyu Park, Ki-Hyoung Lee, et al. International Journal of Pressure Vessels and Piping,2015,131,60.
3 ASME锅炉及压力容器材料委员会,ASME锅炉及压力容器规范第II卷材料A篇铁基材料,中国石化出版社,2014.
4 Lee B S, Kim M C, Yoon J H, et al. International Journal of Pressure Vessels and Piping,2009,87(1),74.
5 Sang-Gyu Park, Ki-Hyoung Lee, Ki-Deuk Min, et al. Metals and Mate-rials International,2013,19(1),49.
6 Sang-Gyu Park, Ki-Hyoung Lee, Ki-Deuk Min, et al. Journal of Nuclear Materials,2012,426(1-3),1.
7 Sang-Gyu Park, Min-Chul Kim, Bong-Sang Lee, et al. Journal of Nuc-lear Materials,2010,407(2),126.
8 刘玉环. 核电厂压力容器用钢的组织与力学性能研究. 硕士学位论文, 天津大学,2014.
9 Ki-Hyoung Lee, Sang-Gyu Park, Min-Chul Kim, et al. Materials Science and Engineering A,2011,529,156.
10 Ki-Hyoung Lee, Min-Chul Kim, Bong-Sang Lee, et al. Journal of Nuc-lear Materials,2010,403(1),68.
11 闫善福,周国强.一重技术,2002(4),30.
12 李昌义, 刘正东, 林肇杰, 等.材料热处理学报,2011(6),68.
13 周超. 核电厂反应堆压力容器用SA508-4Ni-Cr-Mo钢的组织和性能研究. 硕士学位论文, 天津大学,2012.
14 Grossbeck M L, Allen T R, Lott R G, et al. ASTM STP 1447: Effects of Radiation on Materials,2004.
15 吴运祥.压力容器,2010,27(6),1.
16 白庆伟. 核压力容器SA508Gr4钢焊接质量控制研究. 硕士学位论文, 内蒙古科技大学,2015.
17 白庆伟, 麻永林, 邢淑清, 等. 材料热处理学报,2017,38(4),200.
18 Narrow groove gas tungsten arc welding of ASTM A508 Class 4 steel for improved toughness properties. Michael A. Penik, Jr. |
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