Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel

被引:8
|
作者
Xu, Chi [1 ,2 ]
Chen, Wei-Ying [2 ]
Zhang, Xuan [2 ]
Wu, Yaqiao [3 ,4 ]
Li, Meimei [2 ]
Yang, Yong [1 ]
机构
[1] Univ Florida, Dept Mat Sci & Engn, Gainesville, FL 32611 USA
[2] Argonne Natl Lab, Nucl Engn Div, Lemont, IL 60439 USA
[3] Boise State Univ, Micron Sch Mat Sci & Engn, Boise, ID 83725 USA
[4] Ctr Adv Energy Studies, Microscopy & Characterizat Suite, Idaho Falls, ID 83401 USA
关键词
HT-UPS steel; Neutron irradiation; Post-irradiation annealing; Dislocation loops; Radiation-induced segregation and precipitation; TEM and APT; RADIATION-INDUCED SEGREGATION; FE-CR-NI; ATOM-PROBE; SWELLING RESISTANCE; DISLOCATION LOOPS; DEFECT STRUCTURE; CREEP-RESISTANT; FRANK LOOPS; PRECIPITATION; EVOLUTION;
D O I
10.1016/j.jnucmat.2018.04.043
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Microstructural changes resulted from neutron irradiation and post-irradiation annealing in a high-temperature ultra-fine precipitate strengthened (HT-UPS) stainless steel were characterized using transmission electron microscopy (TEM) and atom probe tomography (APT). Three HT-UPS samples were neutron-irradiated to 3 dpa at 500 degrees C, and after irradiation, two of them were annealed for 1 hat 600 degrees C and 700 degrees C, respectively. Frank dislocation loops were the dominant defect structure in both the as-irradiated and 600 degrees C post-irradiation-annealed (PIAed) samples, and the loop sizes and densities were similar in these two samples. Unfaulted dislocation loops were observed in the 700 degrees C PIAed sample, and the loop density was greatly reduced in comparison with that in the as-irradiated sample. Nano-sized MX precipitates were observed under TEM in the 700 degrees C PIAed sample, but not in the 600 degrees C PIAed or the as-irradiated samples. The titanium-rich clusters were identified in all three samples using APT. The post-irradiation annealing (PIA) caused the growth of the Ti-rich clusters with a stronger effect at 700 degrees C than at 600 degrees C. The irradiation caused elemental segregations at the grain boundary and the grain interior, and the grain boundary segregation behavior is consistent with observations in other irradiated austenitic steels. APT results showed that PIA reduced the magnitude of irradiation induced segregations. (C) 2018 Elsevier B.V. All rights reserved.
引用
收藏
页码:188 / 197
页数:10
相关论文
共 50 条
  • [1] Post-irradiation annealing effects on microstructure and helium bubbles in neutron irradiated type 304 stainless steel
    Ishiyama, Y
    Kodama, M
    Yokota, N
    Asano, K
    Kato, T
    Fukuya, K
    JOURNAL OF NUCLEAR MATERIALS, 1996, 239 (1-3) : 90 - 94
  • [2] Effect of post-irradiation annealing on the irradiated microstructure of neutron-irradiated 304L stainless steel
    Jiao, Z.
    Hesterberg, J.
    Was, G. S.
    JOURNAL OF NUCLEAR MATERIALS, 2018, 500 : 220 - 234
  • [3] Effects of post-irradiation annealing on the IASCC susceptibility of neutron-irradiated 304L stainless steel
    Hesterberg, Justin
    Jiao, Zhijie
    Was, Gary S.
    JOURNAL OF NUCLEAR MATERIALS, 2019, 526
  • [4] Insights into the sources of irradiation hardening in a neutron irradiated 304L stainless steel following post-irradiation annealing
    Jiao, Z.
    Hesterberg, J.
    Was, G. S.
    JOURNAL OF NUCLEAR MATERIALS, 2019, 526
  • [5] Effect of neutron irradiation and post-irradiation annealing on microstructure and mechanical properties of OFHC-copper
    Singh, BN
    Edwards, DJ
    Toft, P
    JOURNAL OF NUCLEAR MATERIALS, 2001, 299 (03) : 205 - 218
  • [6] Post-irradiation annealing of neutron irradiated CuCrZr
    Edwards, DJ
    Singh, BN
    Xu, Q
    Toft, P
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 439 - 443
  • [7] Microstructure evolution during helium irradiation and post-irradiation annealing in a nanostructured reduced activation steel
    Liu, W. B.
    Ji, Y. Z.
    Tan, P. K.
    Zhang, C.
    He, C. H.
    Yang, Z. G.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 479 : 323 - 330
  • [8] Effects of damage rate on irradiation hardening and post-irradiation annealing characteristics of carbon steel
    Suzuki, M
    Idei, Y
    Kizaki, M
    Onizawa, K
    EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 : 379 - 387
  • [9] Irradiation hardening of stainless steel model alloy after Fe-ion irradiation and post-irradiation annealing treatment
    Fukumoto, K-, I
    Mabuchi, T.
    Yabuuchi, K.
    Fujii, K.
    JOURNAL OF NUCLEAR MATERIALS, 2021, 557
  • [10] Microstructural changes induced by post-irradiation annealing of neutron-irradiated austenitic stainless steels
    Cole, JI
    Allen, TR
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) : 329 - 333