Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations
Hong Li1 �� Yuan Qin1 �� Wei Cui 1 �� Man Yao 1 �� Xu-dong Wang 1 �� Hai-xuan Xu2 �� Simon R. Phillpot3
1 School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024, Liaoning, China 2 Department of Materials Science and Engineering, University of Tennessee, Knoxville, TN 37996, USA 3 Department of Materials Science and Engineering, University of Florida, Gainesville, FL 32611, USA
Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations
Hong Li1 �� Yuan Qin1 �� Wei Cui 1 �� Man Yao 1 �� Xu-dong Wang 1 �� Hai-xuan Xu2 �� Simon R. Phillpot3
1 School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024, Liaoning, China 2 Department of Materials Science and Engineering, University of Tennessee, Knoxville, TN 37996, USA 3 Department of Materials Science and Engineering, University of Florida, Gainesville, FL 32611, USA
ժҪ The effects of two different symmetric tilt grain boundaries (GBs), ��13[001](230) GB and ��17[001](140) GB, on displacement cascade processes in tungsten were investigated using molecular dynamics simulations. By quantifying the number of interstitials and vacancies surviving after irradiation with the kinetic energy of primary knock-on atom energies of 1, 3 and 5 keV, respectively, in these simulations, it is found that the GBs have dual nature for radiation-induced defects: They absorb interstitials while leaving more vacancies to survive in the grains. The net effect is that the number of total surviving defects in the GB system is not always less than that in the single crystal. These defect behaviors are understood by quantitatively analyzing the recovery fraction of irradiation-induced defects, the time to reach steady state and the mobility of vacancies and interstitials. It is also found that the ��17 GB is a more effective sink of radiation-induced point defects than the ��13 GB. One of the main reasons is that the ��17 GB has a higher GB energy.
Abstract��The effects of two different symmetric tilt grain boundaries (GBs), ��13[001](230) GB and ��17[001](140) GB, on displacement cascade processes in tungsten were investigated using molecular dynamics simulations. By quantifying the number of interstitials and vacancies surviving after irradiation with the kinetic energy of primary knock-on atom energies of 1, 3 and 5 keV, respectively, in these simulations, it is found that the GBs have dual nature for radiation-induced defects: They absorb interstitials while leaving more vacancies to survive in the grains. The net effect is that the number of total surviving defects in the GB system is not always less than that in the single crystal. These defect behaviors are understood by quantitatively analyzing the recovery fraction of irradiation-induced defects, the time to reach steady state and the mobility of vacancies and interstitials. It is also found that the ��17 GB is a more effective sink of radiation-induced point defects than the ��13 GB. One of the main reasons is that the ��17 GB has a higher GB energy.
Hong Li �� Yuan Qin �� Wei Cui �� Man Yao �� Xu-dong Wang �� Hai-xuan Xu �� Simon R. Phillpot. Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations[J].Journal of Iron and Steel Research International, 2018, 25(2): 200-206.
Hong Li �� Yuan Qin �� Wei Cui �� Man Yao �� Xu-dong Wang �� Hai-xuan Xu �� Simon R. Phillpot. Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations. , 2018, 25(2): 200-206.
Borovikov V, Tang X Z, Perez D, et al.Influence of point defects on grain boundary mobility in bcc tungsten[J].Journal of Physics: Condensed Matter, 2012, 25(3):035402-035402
[2]
Rieth M, Dudarev S L, De Vicente S M G, et al.Recent progress in research on tungsten materials for nuclear fusion applications in Europe[J].Journal of Nuclear Materials, 2013, 432(1):482-500
[3]
He X F, Yang W, Fan S.Multi-scale simulation of irradiation damage of FeCr alloy[J].Acta Physica Sinica, 2009, 58(12):8657-8669
[4]
Yamakov V, Saether E, Phillips D R, et al.Dynamics of nanoscale grain-boundary decohesion in aluminum by molecular-dynamics simulation[J].Journal of materials science, 2007, 42(5):1466-1476
[5]
Foxhall H R, Travis K P, Owens S L.Effect of plutonium doping on radiation damage in zirconolite: A computer simulation study[J].Journal of Nuclear Materials, 2014, 444(1):220-228
[6]
Yang Y H, Tang X B, Chen F D, et al.A molecular dynamics-based comparison of defect production in collision cascades during the bombardment of iron with different ions[J].Science China Technological Sciences, 2014, 57(1):29-34
[7]
Domain C, Becquart C S.Ab initio calculations of defects in Fe and dilute Fe-Cu alloys[J].Physical Review B, 2001, 65(2):024103-024103
[8]
Psakhie S G, Zolnikov K P, Kryzhevich D S, et al.Atomic collision cascades in vanadium crystallites with grain boundaries[J].Physical Mesomechanics, 2009, 12(1-2):20-28
[9]
Di Martino S F, Faulkner R G, Smith R.Modelling radiation damage effects on a bcc iron lattice containing phosphorous impurity atoms near symmetrical tilt boundaries[J].Journal of Nuclear Materials, 2011, 417(1):1058-1062
[10]
B��land L K, Osetsky Y N, Stoller R E, et al.Kinetic activation�Crelaxation technique and self-evolving atomistic kinetic monte carlo: Comparison of on-the-fly kinetic monte carlo algorithms[J].Computational Materials Science, 2015, 100:124-134
[11]
Xu H, Stoller R E, B��land L K, et al.Self-evolving atomistic kinetic monte carlo simulations of defects in materials [J][J].Computational Materials Science, 2015, 100:135-143
[12]
Xu H, Stoller R E, Osetsky Y N.Cascade defect evolution processes: Comparison of atomistic methods[J].Journal of Nuclear Materials, 2013, 443(1):66-70
[13]
Xu H, Stoller R E, Osetsky Y N, et al.Solving the Puzzle of? 100? Interstitial Loop Formation in bcc Iron[J].Physical review letters, 2013, 110(26):265503-265503
[14]
Bai X M, Voter A F, Hoagland R G, et al.Efficient annealing of radiation damage near grain boundaries via interstitial emission[J].Science, 2010, 327(5973):1631-1634
[15]
Li M, Cui J, Wang J, et al.Radiation damage of tungsten surfaces by low energy helium atom bombardment�CA molecular dynamics study[J].Journal of Nuclear Materials, 2013, 433(1):17-22
[16]
Barashev A V, Xu H, Stoller R E.The behavior of small helium clusters near free surfaces in tungsten[J].Journal of Nuclear Materials, 2014, 454(1):421-426
[17]
Gilbert M R, Dudarev S L, Derlet P M, et al.Structure and metastability of mesoscopic vacancy and interstitial loop defects in iron and tungsten[J].Journal of Physics: Condensed Matter, 2008, 20(34):345214-345214
[18]
Demkowicz M J, Hoagland R G, Hirth J P.Interface structure and radiation damage resistance in Cu-Nb multilayer nanocomposites[J].Physical review letters, 2008, 100(13):136102-136102
[19]
Singh B N, Foreman A J E.Calculated grain size-dependent vacancy supersaturation and its effect on void formation[J].Philosophical Magazine, 1974, 29(4):847-858
[20]
Rose M, Balogh A G, Hahn H.Instability of irradiation induced defects in nanostructured materials [J][J].Research Section B: Beam Interactions with Materials and Atoms, 1997, 127:119-122
[21]
Shen T D, Feng S, Tang M, et al.Enhanced radiation tolerance in nanocrystalline MgGa2O4[J].Applied Physics Letters, 2007, 90(26):263115-263115
[22]
Samaras M, Derlet P M, Van Swygenhoven H, et al.Stacking fault tetrahedra formation in the neighbourhood of grain boundaries [J][J].Research Section B: Beam Interactions with Materials and Atoms, 2003, 202:51-55
[23]
Chimi Y, Iwase A, Ishikawa N, et al.Accumulation and recovery of defects in ion-irradiated nanocrystalline gold[J].Journal of Nuclear Materials, 2001, 297(3):355-357
[24]
Nita N, Schaeublin R, Victoria M.Impact of irradiation on the microstructure of nanocrystalline materials [J][J].Journal of Nuclear Materials, 2004, 329:953-957
[25]
Stoller R E, Kamenski P J, Osetsky Y N.Length-scale effects in cascade damage production in iron[C]//MRS Proceedings. Cambridge University Press, 2008, 1125: 1125-R05-05.
[26]
Park N Y, Cha P R, Kim Y C, et al.Radiation damage in nano-crystalline tungsten: A molecular dynamics simulation[J].Metals and Materials International, 2009, 15(3):447-452
[27]
Zhang Y, Huang H, Millett P C, et al.Atomistic study of grain boundary sink strength under prolonged electron irradiation[J].Journal of Nuclear Materials, 2012, 422(1):69-76
[28]
Liu F, Li Q, Wang W J, Luo G N, Liu W.Ultra-fine GrainedNanocrystalline Tungsten-Plasma Facing Material for Future Fusion Reactor[J].Material Review A Chin, 2011, 25(10A):43-48
[29]
Lee B J, Baskes M I, Kim H, et al.Second nearest-neighbor modified embedded atom method potentials for bcc transition metals[J].Physical Review B, 2001, 64(18):184102-184102
[30]
Biersack J P, Ziegler J F.Refined universal potentials in atomic collisions[J].Nuclear Instruments and Methods in Physics Research, 1982, 194(1-3):93-100
[31]
Baskes M I.Modified embedded-atom potentials for cubic materials and impurities[J].Physical Review B, 1992, 46(5):2727-2727
[32]
Cui C B, Beom H G.Molecular statics simulations of intergranular fracture along ��11 tilt grain boundaries in copper bicrystals[J].Journal of materials science, 2014, 49(24):8355-8364
[33]
Yoshiya M, Oyama T.Impurity and vacancy segregation at symmetric tilt grain boundaries in Y2O3-doped ZrO2[J].Journal of materials science, 2011, 46(12):4176-4190
[34]
Bhattacharya S K, Tanaka S, Shiihara Y, et al.Ab initio perspective of the symmetrical tilt grain boundaries in bcc Fe: application of local energy and local stress[J].Journal of Materials Science, 2014, 49(11):3980-3995
[35]
Xu H.From electronic structure of point defects to physical properties of complex materials using atomic-level simulations [M]. University of Florida, 2010: 162-163.
[36]
Nguyen-Manh D, Horsfield A P, Dudarev S L.Self-interstitial atom defects in bcc transition metals: Group-specific trends[J].Physical Review B, 2006, 73(2):020101-020101
[37]
Fikar J, Sch?ublin R.Molecular dynamics simulation of radiation damage in bcc tungsten [J][J].Journal of Nuclear Materials, 2009, 386:97-101
[38]
Ahlgren T, Heinola K, Juslin N, et al.Bond-order potential for point and extended defect simulations in tungsten[J].Journal of Applied Physics, 2010, 107(3):033516-033516
[39]
Nguyen-Manh D, Lavrentiev M Y, Muzyk M, et al.First-principles models for phase stability and radiation defects in structural materials for future fusion power-plant applications[J].Journal of Materials Science, 2012, 47(21):7385-7398
[40]
Yao M, Cui W, Wang X D, et al.MOLECULAR DYNAMICS SIMULATION OF INITIAL RADIATION DAMAGE IN TUNGSTEN[J].Acta Metallurgica Sinica, 2015, 51(6):724-732