Research Progress on Properties and Composition of Ferritic/Martensitic Heat-resistant Steels for Nuclear Power
NIU Ben1, WANG Zhenhua1, PAN Qianfu2, LIU Chaohong2, WANG Qing1, DONG Chuang1
1 Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of Education) & School of Material Science and Engineering, Dalian University of Technology, Dalian 116024, China 2 Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
Abstract: Recently, with the continuous development of nuclear power systems, the main stack type lead-cooled fast neutron reactor(LFR) as the fourth-generation nuclear reactor system has become a hot research topic due to its good thermal conductivity and neutron economy. In order to improve the corrosion and irradiation properties of the cladding material in lead-bismuth coolant, 9%—12% Cr ferritic/martensitic (F/M) steels, as an important high-temperature structural material for thermal power generation, have become a candidate cladding material for lead-cooled fast neutron reactors due to their good resistance to corrosion and radiation-resistant swelling properties. However, as a candidate cladding material, the corrosion of ferritic/martensitic heat-resistant steels will increase due to the high temperature and irradiation caused by fission of nuclear fuel during service. Under irradiation conditions, the high temperature structural instability of the mate-rial is further aggravated to affect the high temperature mechanical properties of the material. As regards the above problems, researchers have mainly designed two different F/M steels systems (Cr-Mo and Cr-W) from the perspective of composition and process to satisfy the service requirements by adjusting the addition of trace elements on the basis of 9%—12% Cr F/M steels and changing the heat treatment method. The results show that the addition of trace elements plays a key role in improving the microstructural stability and mechanical properties of F/M steels. A change in the heat treatment process can achieve a good commbination between strength and ductility. The present work summarizes the research progress on various properties of F/M steels systematically, including mechanical properties, corrosion and irradiation-resistance properties, as well as microstructural stabilities. Then, the relationship between alloy properties and composition of F/M steels was generalized. Finally, a cluster formula approach for compositional design for multi-component alloys was used to explore the variation tendency of alloy compositions of existing F/M steels. And this approach was proposed in light of the chemical short-range orders of solute atoms in solid solution. The cluster formula of the improved low-activation F/M steels was then proposed, which will give a new design method to develop high-performance F/M steels combined with thermodynamics calculations.
牛犇, 王镇华, 潘钱付, 刘超红, 王清, 董闯. 核电用铁素体/马氏体耐热钢的性能与成分研究进展[J]. 材料导报, 2020, 34(19): 19141-19151.
NIU Ben, WANG Zhenhua, PAN Qianfu, LIU Chaohong, WANG Qing, DONG Chuang. Research Progress on Properties and Composition of Ferritic/Martensitic Heat-resistant Steels for Nuclear Power. Materials Reports, 2020, 34(19): 19141-19151.
1 Wu Y C, Wang M H, Huang Q Y, et al. Nuclear Science and Enginee-ring,2015,35(2),213(in Chinese). 吴宜灿,王明煌,黄群英,等.核科学与工程,2015,35(2),213. 2 Lorusso P, Bassini S, Nevo A D, et al. Progress in Nuclear Energy,2018,105,318. 3 Smith C F, Halsey W G, Brown N W, et al. Journal of Nuclear Mate-rials,2008,376(3),255. 4 A Technology Roadmap for Generation IV Nuclear Energy Systems-GIF-002-00, United States,2002. 5 Maloy S A, Natesan K, Holcomb D E, et al. Structural alloys for nuclear energy applications, Elsevier, United States,2019. 6 Lv L L, Li Y M, Zhou Y, et al. Nuclear Power Engineering,2016,37(S1),30(in Chinese). 吕亮亮,李垣明,周毅,等.核动力工程,2016,37(S1),30. 7 Klueh R L, Nelson A T. Journal of Nuclear Materials,2007,371(1-3),37. 8 Allen T, Busby J, Meyer M, et al. Materials Today,2010,13(12),14. 9 Müller G, Heinzel A, Konys J, et al. Journal of Nuclear Materials,2002,301(1),40. 10 Schroer C, Wedemeyer O, Novotny J, et al. Corrosion Science,2014,84,113. 11 Anderoglu O A B T. Metallurgical and Materials Transactions A,2013,44(1),70. 12 Yvon P, Le Flem M, Cabet C, et al. Nuclear Engineering and Design,2015,294,161. 13 Song L, Yang X, Zhao Y, et al. Journal of Nuclear Materials,2019,519,22. 14 Klueh R L. International Materials Reviews,2005,50(5),287. 15 Allen T R, Crawford D C. Science and Technology of Nuclear Installations,2007,2007,1. 16 Gong X, Li R, Sun M, et al. Journal of Nuclear Materials,2016,482,218. 17 Swindeman R W, Santella M L, Maziasz P J, et al. International Journal of Pressure Vessels and Piping,2004,81(6),507. 18 Dai Y, Fazio C, Gorse D, et al. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment,2006,562(2),698. 19 Viswanathan R, Bakker W. Journal of Materials Engineering and Performance,2001,10(1),81. 20 Dvoriashin A M, Porollo S I, Konobeev Y V, et al. Journal of Nuclear Materials,2004,329-333,319. 21 Barbier F, Benamati G, Fazio C, et al. Journal of Nuclear Materials,2001,295(2),149. 22 Shiba K, Klueh R L, Miwa Y, et al. Journal of Nuclear Materials,2000,283-287(1),358. 23 Van Der Schaaf B, Tavassoli F, Fazio C, et al. Fusion Engineering and Design,2003,69(1),197. 24 Hashimoto N, Klueh R L. Journal of Nuclear Materials,2002,305(2),153. 25 Huang Q Y, Yu J N, Wan F R, et al. Journal of Nuclear Science and Engineering,2004,24(1),56(in Chinese). 黄群英,郁金南,万发荣,等.核科学与工程,2004,24(1),56. 26 Zumrat Eliniyaz. Design and characterization of ferretic/martensitic steel for nuclear applications. Master's Thesis, Shanghai Jiao Tong University, China,2013(in Chinese). 艾力尼牙孜祖木热提.核反应堆用铁素体/马氏体耐热钢成分设计及性能研究.硕士学位论文,上海交通大学,2013. 27 Huang L X. Study on evolution of microstructure and mechanical properties at elevated temperature for CLAM steel. Ph.D. Thesis, Yanshan University, China,2014(in Chinese). 黄礼新.CLAM钢高温组织演变与力学性能研究.博士学位论文,燕山大学,2014. 28 Li Y F, Huang Q Y, Wu Y C, et al. Nuclear Physics Review,2006,23(2),151(in Chinese). 李艳芬,黄群英,吴宜灿,等.原子核物理评论,2006,23(2),151. 29 Wang W G, Yang Z G, Yan W, et al. Heat Treatment of Metals,2013,38(4),6(in Chinese). 王望根,杨振国,严伟,等.金属热处理,2013,38(4),6. 30 Keller C, Margulies M M, Hadjem-Hamouche Z, et al. Materials Science and Engineering: A,2010,527(24),6758. 31 Cottrell A H. Philosophical Magazine,1953,44(355),829. 32 Chaouadi R. Journal of Nuclear Materials,2008,372(2-3),379. 33 Fan Z Q, Hao T, Zhao S X, et al. Journal of Nuclear Materials,2013,434(1),417. 34 Song M, Zhu R, Foley D C, et al. Journal of Materials Science,2013,48(21),7360. 35 Shang Z, Ding J, Fan C, et al. Acta Materialia,2019,169,209. 36 Bai P W. The preparation and corrosion resistance in Pb-Bi alloy of SiC films on 15-15Ti steel. Master's Thesis, Hefei University of Technology, China,2017(in Chinese). 柏佩文.15-15Ti钢上SiC薄膜的制备及其耐铅铋合金腐蚀性能的研究.硕士学位论文,合肥工业大学,2017. 37 Tian S J. Corrosion behavior and mechanism of T91 and 15-15Ti steels in liquid lead-bismuth eutectic under oxygen control at 500 ℃. Ph.D. Thesis, University of Science and Technology of China, China,2016(in Chinese). 田书建.T91和15-15Ti钢在500 ℃液态铅铋合金氧控条件下腐蚀行为与机理研究.博士学位论文,中国科学技术大学,2016. 38 Frazer D, Qvist S, Parker S, et al. Journal of Nuclear Materials,2016,479,382. 39 Huntz A M, Bague V, Beauplé G, et al. Applied Surface Science,2003,207(1-4),255. 40 Barbier F, Rusanov A. Journal of Nuclear Materials,2001,296(1),231. 41 Shen T L. Irradiation damage in reduced activation ferritic/martenitic steels induced by energetic ions. Ph.D. Thesis, University of Chinese Academy of Science, China,2012(in Chinese). 申铁龙.低活化铁素体/马氏体钢中载能离子辐照损伤研究.博士学位论文,中国科学院大学,2012. 42 Peng L, Huang Q, Ohnuki S, et al. Fusion Engineering and Design,2011,86(9),2624. 43 Hao J K. Fusion reactor material, Chemical Industry Press, China,2007(in Chinese). 郝嘉琨.聚变堆材料,化学工业出版社,2007. 44 Rowcliffe A F, Grossbeck M L. Journal of Nuclear Materials,1984,122(1),181. 45 Du A B, Feng W, Ma H L, et al. Acta Metallurgica Sinica (English Letters),2017,30(11),1049. 46 Zheng Z C, Guo L P, Tang R. Nuclear Physics Review,2017,34(2),211(in Chinese). 郑中成,郭立平,唐睿.原子核物理评论,2017,34(2),211. 47 Krsjak V, Degmova J, Veternikova J S, et al. Journal of Nuclear Mate-rials,2019,523,51. 48 Li X G, Yan Q Z, Ge C C. Journal of Iron and Steel Research,2009,21(6),6 (in Chinese). 黎兴刚,燕青芝,葛昌纯.钢铁研究学报,2009,21(6),6. 49 Xiao X, Song D, Chu H, et al. Advances in Mechanics,2015,45(1),141. 50 Beyerlein I J, Caro A, Demkowicz M J, et al. Materials Today,2013,16(11),443. 51 Klueh R L, Vitek J M. Journal of Nuclear Materials,1985,132(1),27. 52 Chen Y. Nuclear Engineering and Technology,2013,45(3),311. 53 Wakai E, Miwa Y, Hashimoto N, et al. Journal of Nuclear Materials,2002,307-311,203. 54 Schneider H C, Petersen C, Povstyanko A V, et al. Fusion Engineering and Design,2017,124,1019. 55 Sacksteder I, Schneider H C, Materna-Morris E. Journal of Nuclear Materials,2011,417(1-3),127. 56 Gaganidze E, Petersen C, Materna-Morris E, et al. Journal of Nuclear Materials,2011,417(1-3),93. 57 Feng W, Huang C, Du A B, et al. Nuclear Science and Engineering,2014,34(3),302(in Chinese). 冯伟,黄晨,杜爱兵,等.核科学与工程,2014,34(3),302. 58 Prat O, Garcia J, Rojas D, et al. Acta Materialia,2010,58(18),6142. 59 Xu Y, Li W, Wang M, et al. Acta Materialia,2019,175,148. 60 Hald J, Korcakova L. ISIJ International,2003,43(3),420. 61 Hald J. International Journal of Pressure Vessels and Piping,2008,85(1-2),30. 62 Aghajani A, Somsen C, Eggeler G. Acta Materialia,2009,57(17),5093. 63 Abe F, Taneike M, Sawada K. International Journal of Pressure Vessels and Piping,2007,84(1-2),3. 64 Raj B, Vijayalakshmi M. Comprehensive Nuclear Materials,2012,4,97. 65 Zhou X, Liu C, Yu L, et al. Journal of Materials Science & Technology,2015,31(3),235. 66 Yang K, Yan W, Wang Z, et al. Jinshu Xuebao/Acta Metallurgica Sinica,2016,52(10),1207. 67 Chen L, Zeng Z, Zhao Y, et al. Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science,2014,45(3),1498. 68 Lee J S, Armaki H G, Maruyama K, et al. Materials Science and Engineering: A,2006,428(1),270. 69 Sawada K, Kushima H, Kimura K, et al. ISIJ International,2007,47(5),733. 70 Kohyama A, Hishinuma A, Gelles D S, et al. Journal of Nuclear Mate-rials,1996,233-237,138. 71 Karlsson L, Nordén H. Acta Metallurgica,1988,36(1),13. 72 Gelles D S. Journal of Nuclear Materials,1996,239,99. 73 Klueh R L,Alexander D J, Sokolov M A. Journal of Nuclear Materials,2002,304(2),139. 74 Klueh R L. High-chromium ferritic and martensitic steels for nuclear applications. S.l.: ASTM International:2001. 75 Nanstad R, et al. Effects of radiation on materials: 18th international symposium, ASTM, USA,1999. 76 Yamamoto Y, Yang Y, Field K G, et al. Letter report documenting progress of second generation ATF FeCrAl alloy fabrication, Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States),2014. 77 Wang Q, Zha Q F, Li Q, et al. Journal of Dalian University of Technology,2013,53(6),831(in Chinese). 王清,查钱锋,李群,等.大连理工大学学报,2013,53(6),831. 78 Lincoln Electric Company. The procedure handbook of arc welding-14thed, The Lincoln Electric Company, USA,2000. 79 Jiang B B, Wang Q, Dong C. Acta Physica Sinica,2017,66(2),281(in Chinese). 姜贝贝,王清,董闯.物理学报,2017,66(2),281. 80 Dong C, Wang Q, Qiang J B, et al. Journal of Physics D: Applied Phy-sics,2007,40(15),273. 81 Wang Q. Metallurgical and Materials Transactions A,2013,44(4),1872. 82 Dong C, Qiang J B, Yuan L, et al. Chinese Journal of Nonferrous Metals,2011,21(10),2502(in Chinese). 董闯,羌建兵,袁亮,等.中国有色金属学报,2011,21(10),2502. 83 Wang Q, Guo X L, Zhang R Q, et al. Transactions of Materials and Heat Treatment,2014,35(4),72(in Chinese). 王清,郭晓雷,张瑞谦,等.材料热处理学报,2014,35(4),72. 84 Wang Q, Wang Y M, Qiang J B, et al. Acta Metallurgica Sinica,2004,40(11),1183(in Chinese). 王清,王英敏,羌建兵,等.金属学报,2004,40(11),1183. 85 Zhang J Z, Wen D H, Jiang B B, et al. Chinese Journal of Materials Research,2017,31(5),336(in Chinese). 张军政,温冬辉,姜贝贝,等.材料研究学报,2017,31(5),336. 86 Shi Y, Wang Q, Li Q, et al. Chinese Journal of Materials Research,2014,28(8),594(in Chinese). 石尧,王清,李群,等.材料研究学报,2014,28(8),594. 87 Zhou D Q, Xu X Q, Mao H H, et al. Materials Science & Engineering A,2014,594,246. 88 Zhou D Q, Zhao W X, Mao H H, et al. Materials Science & Engineering A,2015,622,91. 89 Zhao B, Fan J, Chen Z, et al. Materials Characterization,2017,125,37. 90 Shen Y, Zhou X, Shi T, et al. Materials Characterization,2016,122,113.
渝公网安备50019002502923号 版权所有：《材料导报》编辑部
2020, Vol. 34 
