Simulation of neutron irradiation-induced recrystallization of tungsten

被引:1
|
作者
Zhang Guo-Shuai [1 ]
Yin Chao [1 ]
Wang Zhao-Fan [1 ]
Chen Ze [1 ]
Mao Shi-Feng [1 ]
Ye Min-You [1 ]
机构
[1] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230026, Peoples R China
基金
中国国家自然科学基金; 中国博士后科学基金;
关键词
tungsten; neutron irradiation; cluster dynamics; irradiation-induced recrystallization; DAMAGE PRODUCTION; RADIATION-DAMAGE; MICROSTRUCTURE; SPECTRA; ALLOYS; MODEL;
D O I
10.7498/aps.72.20230531
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Tungsten is the candidate for divertor target material in future fusion reactors. The tungsten divertor target is expected to long serve in a harsh environment of high temperature and high-energy neutron irradiation. This can lead to neutron irradiation-induced recrystallization of tungsten, thereby increasing the possibility of intergranular brittle failure and compromising the safe operation of the divertor. Thus, clarifying the mechanism of neutron irradiation-induced tungsten recrystallization is important. However, the current model, which only considers the irradiation-enhanced effect on recrystallization driving force, underestimates the irradiation effect on recrystallization compared with the results observed in recent high-temperature neutron irradiation experiments in the HFIR reactor. It indicates that other irradiation effects can also influence the recrystallization process. In this study, we introduce the irradiation-enhanced grain boundary migration factor (R) into the established irradiation-induced recrystallization kinetic model, on the assumption that the grain boundary migration velocity is proportional to the self-diffusion coefficient. The simulation results show that after considering both irradiation-enhanced recrystallization driving force and grain boundary migration effect, the calculated half-recrystallization time (t(X=0.5)) at 850 degrees C from the model matches the one obtained in the neutron irradiation experiment in the HFIR reactor. This result indicates that the irradiation-enhanced grain boundary migration effect is one of the important factors affecting irradiation-induced recrystallization. In addition, the difference between irradiated and unirradiated t(X= 0.5) decreases with temperature increasing. This phenomenon is due to the fact that as the temperature increases, the contribution of irradiation defects to the driving force for recrystallization decreases owing to the irradiation defect recombination. Moreover, the increase of thermal activation diffusion coefficient is more significant than the increase of the irradiation-enhanced diffusion coefficient. These findings suggest that the thermal activation effect eventually dominates the recrystallization process over the irradiation effect as temperature increases.
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页数:10
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共 46 条
  • [11] Modeling Grain Boundary Motion and Dynamic Recrystallization in Pure Metals
    Favre, Julien
    Fabregue, Damien
    Piot, David
    Tang, Ning
    Koizumi, Yuichiro
    Maire, Eric
    Chiba, Akihiko
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2013, 44A (13): : 5861 - 5875
  • [12] Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten
    Fukuda, Makoto
    Kumar, N. A. P. Kiran
    Koyanagi, Takaaki
    Garrison, Lauren M.
    Snead, Lance L.
    Katoh, Yutai
    Hasegawa, Akira
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2016, 479 : 249 - 254
  • [13] Effects of Re Content and Fabrication Process on Microstructural Changes and Hardening in Neutron Irradiated Tungsten
    Fukuda, Makoto
    Tanno, Takashi
    Nogami, Shuhei
    Hasegawa, Akira
    [J]. MATERIALS TRANSACTIONS, 2012, 53 (12) : 2145 - 2150
  • [14] A NUMERICAL-SOLUTION TO THE FOKKER-PLANCK EQUATION DESCRIBING THE EVOLUTION OF THE INTERSTITIAL LOOP MICROSTRUCTURE DURING IRRADIATION
    GHONIEM, NM
    SHARAFAT, S
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1980, 92 (01) : 121 - 135
  • [15] Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys
    Gietl, Hanns
    Koyanagi, Takaaki
    Hu, Xunxiang
    Fukuda, Makoto
    Hasegawa, Akira
    Katoh, Yutai
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 2022, 901
  • [16] Differential dpa calculations with SPECTRA-PKA
    Gilbert, M. R.
    Sublet, J. -Ch.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2018, 504 : 101 - 108
  • [17] Energy spectra of primary knock-on atoms under neutron irradiation
    Gilbert, M. R.
    Marian, J.
    Sublet, J. -Ch.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 467 : 121 - 134
  • [18] Approaches to Modeling of Recrystallization
    Hallberg, Hakan
    [J]. METALS, 2011, 1 (01): : 16 - 48
  • [19] Irradiation hardening of pure tungsten exposed to neutron irradiation
    Hu, Xunxiang
    Koyanagi, Takaaki
    Fukuda, Makoto
    Kumar, N. A. P. Kiran
    Snead, Lance L.
    Wirth, Brian D.
    Katoh, Yutai
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2016, 480 : 235 - 243
  • [20] Simulating irradiation hardening in tungsten under fast neutron irradiation including Re production by transmutation
    Huang, Chen-Hsi
    Gilbert, Mark R.
    Marian, Jaime
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2018, 499 : 204 - 215