Abstract: To investigate the grain boundary segregation and hardening of austenitic stainless steel weld joints after helium ion irradiation, three groups of 316L weld joints under different welding parameters were irradiated by He+ at doses of 2×1017 n/cm2 and 100 keV. The hardness, microstructure and grain boundary composition of the welding joints were characterized before and after helium ion irradiation. TEM observation revealed that the characteristic irradiated microstructure of weld joints were dislocation loop, dislocation tangle, dislocation wall, dislocation cell and helium bubble, in the size and density, which were not significantly related to the welding parameters. EDS data of grain boundary indicated that the segregation induced by irradiation showed the appearance of Ni-rich and Cr-poor in the original to Cr-rich and Ni-poor in grain bcoundary of weld joints. The microhardness data before and after helium ion irradiation showed that the increase of hardness decreased with the increment of heat input. Therefore, the grain boundary segregation and microstructure change of the weld joints of austenitic stainless steel after irradiation were similar to that of the base metal. The grain size decreased with the decrement of welding heat input, which improved the dislocation channel density in the grains. As a result, the effect of high density defects produced by irradiation were more obvious on the slip resistance. The irradiation hardening increment decreased with increasing heat input in consequence.
1 Deng P, Sun C, Peng Q J, et al.Journal of Chinese Society for Corrosion and Protection, 2015, 35(6),480(in Chinese). 邓平, 孙晨, 彭群家,等. 中国腐蚀与防护学报, 2015, 35(6),480. 2 Was G S, Allen T. Materials Characterization, 1994, 32(4),239. 3 Allen T, Busby J T, Was G S, et al. Journal of Nuclear Materials, 1998,255(1),44. 4 Lambrecht M, Almazouzi A. Journal of Physics:Conference Series, 2011, 265,012009. 5 Chai M, Lai W S, Li Z C, et al. Acta Metallurgica Sinica-English Letters, 2012, 251(1),29. 6 Jiao Z, Was G S.Journal of Nuclear Materials, 2014, 449(1-3),200. 7 Seeger A K. Annealing, 1959,6. 8 Singh B N, Foreman A J E, Trinkaus H. Journal of Nuclear Materials,1997, 249(2-3),103. 9 Heald P T, Speight M V. Philosophical Magazine Series, 1974, 29(5),6. 10 Brailsford A D, Bullough R. Philosophical Magazine, 1973, 27(1),49. 11 Ding Y G, Feng W Q.Spacecraft Environment Engineering, 2005, 22(5),283(in Chinese). 丁义刚, 冯伟泉.航天器环境工程, 2005, 22(5),283. 12 Li Y,Wei X, Li H.Journal of Nuclear Materials, 2016, 480,75. 13 Shi W, Zeng Q, Li W, et al.Nuclear Techniques, 2016, 39(12),1(in Chinese). 石巍, 曾勤, 李卫,等. 核技术, 2016, 39(12),1. 14 Liao Z, Xiong Z H, Zhang P C, et al. Materials Review B: Research Papers, 2011, 25(9),249(in Chinese). 廖哲, 熊忠华, 张鹏程,等. 材料导报:研究篇, 2011, 25(9),249. 15 Nishi T, Hashimoto N, Ohnuki S, et al. Journal of Nuclear Materials, 2011, 417(1-3),936. 16 Was G S. In:Proc. 11th Int. Conf. Environmental Degradation of Mate-rials in Nuclear Power Systems-Water Reactors. Washington, 2003. 17 Barashev A V, Golubov S, Bacon D, et al.Acta Materialia, 2004, 52(4),877. 18 Was G S, Allen T R, Busby J T, et al.Journal of Nuclear Materials, 1999, 270(1-2),96. 19 Okamoto P R, Wiedersich H. Journal of Nuclear Materials, 1974, 53(1),336. 20 Pan C X, Zhu F Y, Chen Y D.Journal of Wuhan University of Water Transportation Engineering, 1990, 14(4),419(in Chinese). 潘春旭,朱凤艳, 陈雁荡. 武汉水运工程学院学报, 1990, 14(4),419. 21 He M R, Johnson D C, Was G S, et al.Acta Materialia, 2017, 138,63. 22 Bruemmer S M, Simonen E P, Scott P M, et al. Journal of Nuclear Materials, 1999, 274(3),305. 23 Jin H H,Ko E, Lim S, et al.Nuclear Instruments and Methods in Physics Research B, 2015, 359,72. 24 Maziasz P J.Journal of Nuclear Materials, 1993, 205(93),118. 25 Jiao Z, McMurtrey M D, Was G S. Scripta Materialia, 2011, 65(2),159. 26 Byun T S, Hashimoto N.Journal of Nuclear Materials, 2006, 354(1-3),123. 27 Jiao Z, Was G S, Miura T, et al. Journal of Nuclear Materials, 2014, 452(1-3),328.
渝公网安备50019002502923号 版权所有：《材料导报》编辑部
2020, Vol. 34 
