Temperature effect of irradiation hardening behavior of 316L stainless steel by additive manufacturing

被引：0
|
作者：
Fu C. [1 ,2 ]
Li J. [1 ]
Bai J. [1 ,2 ]
Lin J. [1 ]
机构：
[1] Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai
[2] University of Chinese Academy of Sciences, Beijing
来源：
He Jishu/Nuclear Techniques | 2022年 / 45卷 / 09期
基金：
中国国家自然科学基金; 上海市自然科学基金;
关键词：
316L stainless steel; Additive manufacturing; Dislocation loops; Helium bubbles; Irradiation hardening;
D O I：
10.11889/j.0253-3219.2022.hjs.45.090203
中图分类号：
学科分类号：
摘要：
[Background] The additive manufacturing (AM) technology is expected to apply to the field of advanced nuclear energy because of its unrivalled design freedom and short lead times. However, the irradiation resistance of the AM materials needs to be studied. One of the key scientific problems is the irradiation hardening behavior of the AM materials under irradiation environment. As a candidate nuclear material, 316L stainless steel (SS) produced by selective laser melting (SLM, a very important AM technology of metals) is selected as the study object. [Purpose] This study aims to investigate the irradiation hardening behavior and the irradiation defects evolution of the SLM 316L SS as function of temperature. [Methods] The SLM 316L SS was irradiated by 500 keV helium ions at different irradiation temperatures (from 350 ° C to 800 ° C) to explore the temperature effect of hardening behavior. The irradiation dose of each sample was 1.5×1016 ions·cm−2. The irradiation hardening and irradiation defects were characterized by nanoindentation and transmission electron microscopy (TEM) respectively. The contribution of helium bubbles and dislocation loops to irradiation hardening was calculated using the dispersed barrier hardening (DBH) model. [Results] The results of the nanoindentation test show that the irradiation hardening degree of SLM 316L SS decreases from 71.65% at 350 ° C to 23.62% at the highest temperature, suggesting an obvious irradiation hardening recovery with the temperatures increasing. The observation of TEM indicates that helium bubbles and dislocation loops are the main micro defects caused by the ion irradiation. The evolution trend of the two types of irradiation defects with temperature is the same whilst the helium bubble's contribution to the irradiation hardening is slightly higher than that of dislocation loops except at the highest temperature. With the increase of temperature, the average number density of the two defects decreases steadily with the increase of diameter, but the helium bubbles have the higher temperature sensitivity. The calculated values by the DBH model are in agreement with the experimental values obtained by nanoindentation testing. [Conclusions] The irradiation hardening of SLM 316L SS decreases with increasing temperature, and helium bubbles and dislocation loops are closely related to the irradiation hardening behavior. The higher temperature sensitivity of helium bubbles may be a very important reason for the high temperature recovery of irradiation hardening. With the increase of temperature, the decrease of irradiation defects induced by the enhancement of defects' diffusion ability is the main mechanism of the recovery of the hardening behavior of SLM 316L SS at high temperature. © 2022 Science Press. All rights reserved.
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  • [1] Herzog D, Seyda V, Wycisk E, Et al., Additive manufacturing of metals[J], Acta Materialia, 117, pp. 371-392, (2016)
  • [2] Ngo T D, Kashani A, Imbalzano G, Et al., Additive manufacturing (3D printing): a review of materials, methods, applications and challenges[J], Composites Part B: Engineering, 143, pp. 172-196, (2018)
  • [3] Wang Y M, Voisin T, McKeown J T, Et al., Additively manufactured hierarchical stainless steels with high strength and ductility[J], Nature Materials, 17, 1, pp. 63-71, (2018)
  • [4] Huang B, Zhai Y T, Liu S J, Et al., Microstructure anisotropy and its effect on mechanical properties of reduced activation ferritic/martensitic steel fabricated by selective laser melting[J], Journal of Nuclear Materials, 500, pp. 33-41, (2018)
  • [5] Zhong Y, Rannar L E, Wikman S, Et al., Additive manufacturing of ITER first wall panel parts by two approaches: selective laser melting and electron beam melting[J], Fusion Engineering and Design, 116, pp. 24-33, (2017)
  • [6] Song M, Wang M, Lou X Y, Et al., Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels[J], Journal of Nuclear Materials, 513, pp. 33-44, (2019)
  • [7] Maziasz P J., Some effects of increased helium content on void formation and solute segregation in neutron irradiated type 316 stainless steel[J], Journal of Nuclear Materials, 108, pp. 359-384, (1982)
  • [8] Odette G R, Alinger M J, Wirth B D., Recent developments in irradiation-resistant steels[J], Annual Review of Materials Research, 38, pp. 471-503, (2008)
  • [9] Zinkle S J, Was G S., Materials challenges in nuclear energy[J], Acta Materialia, 61, 3, pp. 735-758, (2013)
  • [10] Murr L E, Gaytan S M, Ramirez D A, Et al., Metal fabrication by additive manufacturing using laser and electron beam melting technologies[J], Journal of Materials Science & Technology, 28, 1, pp. 1-14, (2012)
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