Research Progress of Irradiation Embrittlement Properties of SA508 Gr.4N Steel
ZENG Xiaochuan1,2, LI Xuejun2, DENG Xiaoyun2, HU Qiaodan1, YOU Lei2
1 Advanced Materials and Solidification Laboratory, School of Materials Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China 2 State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment, China Nuclear Power Engineering Co., Ltd, Shenzhen 518172, China
Abstract: The irradiation embrittlement effect of low alloy steel is closely related to the alloy composition. On the basis of steel used in traditional nuc-lear power plant, SA508 Gr.4N steel has outstanding initial mechanical properties by adjusting alloy elements, but it may also bring the risk of deterioration of its radiation property. Under the irradiation condition, the variation in the mechanical properties of SA508 Gr.4N steel has a certain relationship with the alloy elements, and a synergy effect between alloy elements is also found in the changes of micro-features. The latest research progress in the current world on the irradiation properties of SA508 Gr.4N steel is introduced and evaluated in this paper, and furthermore, the future directions worth exploring are presented.
作者简介: 曾小川,2008年7月毕业于武汉科技大学,获得理学学士学位。现为上海交通大学材料科学与工程学院在职博士研究生,同时担任中广核工程有限公司设计院材料主管设计师,目前在胡侨丹老师指导下主要研究核电站用低合金钢的服役性能。胡侨丹,2007年博士毕业于华中科技大学材料加工工程专业,现任上海交通大学材料科学与工程学院先进材料与凝固研究所研究员,博士生导师。主持国家自然科学基金(5项)、973计划子课题、国家重点研发计划子课题、工信部重大专项子课题、上海市自然基金及中国博士后特别资助等20余项国家(省部)级项目。在本领域权威期刊Acta Mater、Sci Rep、Scripta Mater、Metall Mater Trans A等上发表SCI论文63篇,与李建国教授合作翻译出版本领域权威著作《凝固原理》,申请专利11项,2018年获得上海市人才发展资金资助计划,2019年国家优秀青年科学基金获得者。主要研究方向:先进材料合成与凝固理论。
引用本文:
曾小川, 李学军, 邓小云, 胡侨丹, 尤磊. SA508 Gr.4N钢的辐照脆化性能研究进展[J]. 材料导报, 2021, 35(Z1): 438-442.
ZENG Xiaochuan, LI Xuejun, DENG Xiaoyun, HU Qiaodan, YOU Lei. Research Progress of Irradiation Embrittlement Properties of SA508 Gr.4N Steel. Materials Reports, 2021, 35(Z1): 438-442.
1 Little E A.Materials Science and Technology, 2006, 22, 491. 2 Williams T J, Thomas A F, Berrisford R F, et al. In: Effects of Radiation on Materials, 11th International Symposium, ASTM STP 782, Philadelphia, 1982, pp. 343. 3 Fukuya K, Ohno K, Nakata H, et al.Journal of Nuclear Materials, 2003, 312(2-3),163. 4 Akamatsu M, Van Duysen J C, Pareige P, et al.Journal of Nuclear Materials, 1995, 225,192. 5 Nishiyama Y, Onizawa K, Suzuki M, et al. Acta Materialia, 2008, 25(16), 4510. 6 肖厦子, 宋定坤, 楚海建等. 力学进展, 2015, 45(1), 141. 7 李昌义, 刘正东, 林肇杰.特殊钢, 2010, 31(4), 14. 8 ASME boiler and pressure vessel code, Section II-Materials, Part A-Ferrous material specifications, SA-508 Specification for quenched and tempered vacuum-treated carbon and alloy steel forgings for pressure vessels. American Society of Mechanical Engineers, 2015. 9 Kim M C, Park S G, Lee Y S, et al. In: International Conference on Advances in Nuclear Power Plants, ICAPP, Anaheim, 2008. 10 Lee K H, Park S G, Kim M C, et al.Materials Science and Engineering A, 2012, 534, 75. 11 Kim S, Lee S, Im Y, et al.Metallurgical and Materials Transactions A, 2001, 32, 903. 12 Kim M C, Lee K H, Lee B S, et al. In: ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference, PVP2010-26002, Bellevue, 2010, 143. 13 Lee K H, Park S G, Kim M C,et al. Materials Science and Engineering A, 2011, 529, 156. 14 Kim M C, Park S G, Lee K H, et al.International Journal of Pressure Vessels and Piping, 2015, 131, 60. 15 ASME boiler and pressure vessel code, Section XI - Nuclear power plant components in-service inspection rules. American Society of Mechanical Engineers, 2015. 16 刘士峰. 钢的晶界马氏体形成与低温回火脆性. 硕士学位论文, 河北工业大学, 2009. 17 Lea C, Seah M P.Surface Science, 1975, 53(1), 272. 18 Guttmann M, Dumiulin P, Wayman M.Metallurgical Transactions A - Physical Metallurgy and Materials Science, 1982, 13(10), 1693. 19 Park S G, Lee K H, Min K D, et al.Journal of Nuclear Materials, 2012, 426, 1. 20 杨志强. 核压力容器用SA508 Gr.4N钢大锻件的韧脆性研究.博士学位论文, 钢铁研究总院, 2018. 21 杨文斗.核安全, 2012(3), 1. 22 吕铮. 金属学报, 2011, 47(7), 777. 23 李正操, 陈良.金属学报, 2014, 50(11), 1285. 24 黄鹤飞, Bertrand R, Philippe P. 材料导报, 2013, 27(12), 106. 25 Odette G R, Lucas G E.Radiation Effects and Defect in Solids, 1998, 144, 189. 26 Hawthorne J R. In: Proc. 11th Conference on the Effects of Radiation on Materials, ASTM STP 782, Scottsdale, 1982, pp.375. 27 Hawthorne J R.Nuclear Engineering and Design, 1985, 89(1), 223. 28 Nikolaeva A V, Nikalaev Y A. Materials Science and Engineering A, 1997, 234-236, 915. 29 Kryukov A M, Nikolaev Y A, Nikolaeva A V. Nuclear Engineering and Design, 1998,186(3), 353. 30 Stofanak R J, Poskie T J, Li Y, et al. In: International symposium on environmental degradation of materials in nuclear power systems, water reactors, San Diego, 1993. 31 Burke M G, Stofanak R J, Hyde J M, et al. Journal of ASTM Internatio-nal, 2004, 1(5), 1. 32 Wire G L, Beggs W J, Leax T R. In: Effects of Radiation on Materials, 21st International Symposium, ASTM STP 1447, West Conshohocken, 2003, pp. 179. 33 Lee B S, Kim M C, Yoon J H, et al. International Journal of Pressure Vessels and Piping, 2010, 87, 74. 34 Lee C H, Kasada R, Kimura A, et al. Metals and Materials Internatio-nal, 2013, 19(6), 1203. 35 Phythian W J, English C A. Journal of Nuclear Materials,1993, 205(4), 162. 36 Odette G R.Journal of Nuclear Materials, 1994, 212-215(5), 45. 37 Carter R G, Soneda N, Dohi K, et al. Journal of Nuclear Materials, 2001, 298(3), 211. 38 Meslin E, Lambrecht M, Hernandez-Matoral M, et al. Journal of Nuclear Materials, 2010, 406(1), 73. 39 Fukuya K. Journal of Nuclear Science and Technology, 2013, 50(3), 213. 40 Buswell J T, phythian W J, McElroy R J, et al. Journal of Nuclear Materials, 1995, 225(2), 196. 41 Liu C L, Odette G R, Wirth B D, et al. Materials Science and Enginee-ring A, 1997, 238(1), 202. 42 Miller M K, Chernobaeva A A, Shtrombakh Y I, et al.Journal of Nuclear Materials, 2009, 385(3), 615. 43 Bergner F, Ulbricht A, Viehrig H W, et al.Philosophical Magazine Letters, 2009, 89 (12), 795. 44 Wagner A, Ulbricht A, Bergner F, et al. Nuclear Instruments and Met-hods in Physics Research Section B, 2012, 280, 98. 45 Miller M K, Russell K F. Journal of Nuclear Materials, 2007, 371(1-3), 145. 46 Lee G G, Jin H H, Chang K, et al. Journal of Mechanical Science and Technology, 2017, 31(8), 3675. 47 Chaouadi R, Gerard R. Journal of Nuclear Materials, 2005, 345 (1), 65. 48 Malerba L. Journal of Nuclear Materials, 2006, 351(1-3), 28. 49 Terentyev D, Lagerstedt C, Olsson P, et al. Journal of Nuclear Materials, 2006, 351(1-3), 65. 50 Nagai Y, Takadate K, Tang Z, et al. Physical Review B, 2003, 67(22), 224202. 51 Glade S C, Wirth B D, Odette G R, et al. Journal of Nuclear Materials, 2006, 351(1-3), 197. 52 Lambrecht M, Malerba L, Almazouzi A. Journal of Nuclear Materials, 2008, 378(3), 282. 53 Yabuuchi K, Saito M, Kasada R. et al. Journal of Nuclear Materials, 2011, 414(3), 498. 54 Bonny G, Terentyev D, Bakaev A, et al.Journal of Nuclear Materials, 2013, 442(1-3), 282. 55 Ke H, Wells P, Edmondson P D, et al.Acta Materialia, 2017, 138(1), 10.
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2021, Vol. 35 
