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Philosophical Magazine A Volume 63, 1991 - Issue 5
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Original Articles

Microstructure evolution in h.c.p. metals during irradiation

M. Griffiths Chalk River Laboratories, Chalk River, Ontario, Canada, K0J 1J0
Pages 835-847 | Published online: 13 Sep 2006

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Aruna Devi, R. Menon, S. K. Sharma, S. Saini, A. P. Srivastava, S. Neogy & R. Tewari. (2023) Microstructural and mechanical property evolution of Ar9+ ion irradiated Zr-based alloys – effect of initial microstructure and alloying addition. Radiation Effects and Defects in Solids 178:5-6, pages 553-574.
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Md Imran Khan, Sterling St Lawrence & Robert J. Klassen. (2021) Effect of Zr+ irradiation damage and crystal orientation on the uniaxial deformation of Zr–2.5%Nb micro-pillars: part 1, deformation of single-phase αZr micro-pillars. Canadian Metallurgical Quarterly 60:1, pages 28-40.
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J. Geng, M.F. Chisholm, R.K. Mishra & K.S. Kumar. (2015) An electron microscopy study of dislocation structures in Mg single crystals compressed along [0 0 0 1] at room temperature. Philosophical Magazine 95:35, pages 3910-3932.
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A.K. Khan, Z. Yao & M.R. Daymond. (2014) Microstructure evolution during electron and ion irradiation in commercial purity magnesium. Philosophical Magazine 94:17, pages 1909-1923.
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J. Geng, M.F. Chisholm, R.K. Mishra & K.S. Kumar. (2014) The structure of 〈c + a〉 type dislocation loops in magnesium. Philosophical Magazine Letters 94:6, pages 377-386.
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A. Serra & D.J. Bacon. (2010) Interaction of a moving { } twin boundary with perfect dislocations and loops in a hcp metal. Philosophical Magazine 90:7-8, pages 845-861.
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Haruo NAKAMICHI, Chiken KINOSHITA, Kazuhiro YASUDA & Shinya FUKADA. (1997) Formation and Growth Process of Dislocation Loops in Zircaloys under Electron Irradiation. Journal of Nuclear Science and Technology 34:11, pages 1079-1086.
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S.J. Wooding, D.J. Bacon & W.J. Phythian. (1995) A computer simulation study of displacement cascades in α-titanium. Philosophical Magazine A 72:5, pages 1261-1279.
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GraemeJ. Ackland. (1992) Theoretical study of titanium surfaces and defects with a new many-body potential. Philosophical Magazine A 66:6, pages 917-932.
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A. Amroussia, C.J. Boehlert, F. Pellemoine, D. Grummon, W. Mittig, T.R. Bieler, M. Li & W.-Y. Chen. (2024) MICROSTRUCTURAL EVOLUTION OF ION IRRADIATED COMMERCIALLY PURE TITANIUM. Journal of Nuclear Materials, pages 155105.
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Dewang Cui, Ziqi Cao, Yifan Ding, Yipeng Li & Guang Ran. (2023) Effect of dose rate on the characteristics of dislocation loops in palladium: In-situ TEM analysis during 30 keV H2+ irradiation. Journal of Materials Science & Technology 150, pages 86-95.
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Yan Liu, Chuanlong Xu, Xiaobao Tian, Wentao Jiang, Qingyuan Wang & Haidong Fan. (2022) Formation of stacking fault pyramid in zirconium. Computational Materials Science 212, pages 111591.
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Cheng Chen & Jun Song. (2022) A Combined Atomistic-Continuum Study on the Unfaulting of Single and Multi-layer Interstitial Dislocation Loops in Irradiated FCC and HCP Metals. International Journal of Plasticity 152, pages 103231.
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Malcolm Griffiths, Juan Ramos-Nervi & Larry Greenwood. (2021) A Rate Theory Model of Radiation-Induced Swelling in an Austenitic Stainless Steel. Journal of Nuclear Engineering 2:4, pages 484-515.
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Liang Xia, Ding Chen, Yucheng Cao, Xiazi Xiao & Chao Jiang. (2021) High temperature nano-indentation on the mechanical properties of Zr and Zr–Fe alloys: Experimental and theoretical analysis. Mechanics of Materials 162, pages 104053.
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Lu Wu, Vasyl O. Kharchenko, Xianggang Kong & Dmitrii O. Kharchenko. (2021) First-principle calculations of vacancy clustering in zirconium-based alloys. Journal of Nuclear Materials 554, pages 153079.
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Hongbing Yu, Phani Karamched, Suchandrima Das, Junliang Liu, Kenichiro Mizohata & Felix Hofmann. (2021) New perspectives on collision cascade damage in self-ion irradiated tungsten from HR-EBSD and ECCI. Journal of Nuclear Materials 554, pages 153074.
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Cong Dai, Céline Varvenne, Peyman Saidi, Zhongwen Yao, Mark R. Daymond & Laurent Karim Béland. (2021) Stability of vacancy and interstitial dislocation loops in -zirconium: atomistic calculations and continuum modelling . Journal of Nuclear Materials 554, pages 153059.
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R. Hulse & C.P. Race. (2021) An Atomistic Modelling Study of the Properties of Dislocation Loops in Zirconium. Journal of Nuclear Materials 546, pages 152752.
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Yang Li, Giacomo Po & Nasr Ghoniem. (2020) Coupled cluster-dislocation dynamics of irradiation-induced defects. Materialia 14, pages 100891.
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Yang Li & Nasr Ghoniem. (2020) Cluster dynamics modeling of irradiation growth in single crystal Zr. Journal of Nuclear Materials 540, pages 152312.
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M. Christensen, W. Wolf, C. Freeman, E. Wimmer, R.B. Adamson, M. Griffiths & E.V. Mader. (2020) Vacancy loops in Breakaway Irradiation Growth of zirconium: Insight from atomistic simulations. Journal of Nuclear Materials 529, pages 151946.
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Fabien Onimus, Sylvie Doriot & J.-L. Béchade. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 1 56 .
B.V. Cockeram, P.D. Edmondson, K.J. Leonard, B.F. Kammenzind & J.L. Hollenbeck. (2019) Atom probe examinations of Zircaloy irradiated at nominally 358 °C. Nuclear Materials and Energy 19, pages 416-432.
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Xinghang Zhang, Khalid Hattar, Youxing Chen, Lin Shao, Jin Li, Cheng Sun, Kaiyuan Yu, Nan Li, Mitra L. Taheri, Haiyan Wang, Jian Wang & Michael Nastasi. (2018) Radiation damage in nanostructured materials. Progress in Materials Science 96, pages 217-321.
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Jin Li, Y. Chen, H. Wang & X. Zhang. (2018) In situ study on enhanced heavy ion irradiation tolerance of porous Mg. Scripta Materialia 144, pages 13-17.
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Weizong Xu, Yongfeng Zhang, Guangming Cheng, Suveen N. Mathaudhu, Ronald O. Scattergood, Carl C. Koch, Enrique J. Lavernia & Yuntian Zhu. (2017) On the origin and behavior of irradiation-induced c-component dislocation loops in magnesium. Acta Materialia 131, pages 457-466.
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E. JOUANNY, S. DORIOT, J. MALAPLATE, M. DEHMAS, L. ALLAIS, M. LE THUAUT & T. MILLOT. (2016) Evolution of defects in titanium grade 2 under Ti 2+ ion irradiation . Journal of Microscopy 265:3, pages 275-286.
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Marisol López, Bianca Picchetti & Horacio Taboada. (2017) Influence of temperature and compressive stress on the UMo/Zry-4 interdiffusion layer. Progress in Nuclear Energy 94, pages 101-105.
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Cong Dai, Levente Balogh, Zhongwen Yao & Mark R. Daymond. (2016) Atomistic simulations of the formation of <c>-component dislocation loops in α-zirconium. Journal of Nuclear Materials 478, pages 125-134.
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A. Arjhangmehr & S. A. H. Feghhi. (2016) Irradiation deformation near different atomic grain boundaries in α-Zr: An investigation of thermodynamics and kinetics of point defects. Scientific Reports 6:1.
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B.V. Cockeram, K.J. Leonard, T.S. Byun, L.L. Snead & J.L. Hollenbeck. (2015) The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C. Journal of Nuclear Materials 461, pages 244-264.
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B.V. Cockeram, K.J. Leonard, T.S. Byun, L.L. Snead & J.L. Hollenbeck. (2014) Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C. Journal of Nuclear Materials 449:1-3, pages 69-87.
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A. Boyne, C. Shen, R. Najafabadi & Y. Wang. (2013) Numerical simulation of irradiation hardening in Zirconium. Journal of Nuclear Materials 438:1-3, pages 209-217.
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V. Chabretou, P. B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, V. Rebeyrolle & J. J. Vermoyal. 2012. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 801 826 .
Magnus Limbäck & Pierre BarbérisV. Chabretou, P. B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, V. Rebeyrolle & J. J. Vermoyal. 2012. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 801 826 .
A.K. Khan, Z. Yao, M.R. Daymond & R.A. Holt. (2012) Irradiation damage in commercial purity magnesium. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 272, pages 231-235.
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F. Onimus & J.L. Béchade. 2012. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 1 31 .
V. Chabretou, P. B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, V. Rebeyrolle & J. J. Vermoyal. 2011. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 801 826 .
V. Chabretou, P. B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, V. Rebeyrolle & J. J. Vermoyal. (2011) Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties. Journal of ASTM International 8:5, pages 1-17.
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Ronald B. AdamsonM. Griffiths. 2010. Zirconium Production and Technology: The Kroll Medal Papers 1975–2010. Zirconium Production and Technology: The Kroll Medal Papers 1975–2010 429 436 .
Bruce Kammenzind & Magnus LimbäckM. Griffiths. 2009. Zirconium in the Nuclear Industry: 15th International Symposium. Zirconium in the Nuclear Industry: 15th International Symposium 19 26 .
N. de Diego, Yu.N. Osetsky & D.J. Bacon. (2008) Structure and properties of vacancy and interstitial clusters in α-zirconium. Journal of Nuclear Materials 374:1-2, pages 87-94.
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M. Griffiths. (2008) Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence. Journal of ASTM International 5:1, pages 1-8.
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David J. Bacon. 2006. Materials Science and Technology. Materials Science and Technology.
V Dubinko, A Turkin, A Abyzov & M Griffiths. (2006) Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation. Journal of ASTM International 3:1, pages 1-18.
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ZL Pan, S St Lawrence, PH Davies, M Griffiths & S Sagat. (2005) Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life. Journal of ASTM International 2:9, pages 1-22.
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P Rudling & B KammenzindZL Pan, S St Lawrence, PH Davies, M Griffiths & S Sagat. 2005. Zirconium in the Nuclear Industry: Fourteenth International Symposium. Zirconium in the Nuclear Industry: Fourteenth International Symposium 759 782 .
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V.I. Dubinko, A.S. Abyzov & A.A. Turkin. (2005) Numerical evaluation of the dislocation loop bias. Journal of Nuclear Materials 336:1, pages 11-21.
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D. J. Bacon & V. Vitek. (2002) Atomic-scale modeling of dislocations and related properties in the hexagonal-close-packed metals. Metallurgical and Materials Transactions A 33:3, pages 721-733.
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C.H Woo. (2000) Defect accumulation behaviour in hcp metals and alloys. Journal of Nuclear Materials 276:1-3, pages 90-103.
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S.J Wooding, L.M Howe, F Gao, A.F Calder & D.J Bacon. (1998) A molecular dynamics study of high-energy displacement cascades in α-zirconium. Journal of Nuclear Materials 254:2-3, pages 191-204.
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Th. Klemm & W. Frank. (1996) Void ordering in hexagonal close-packed metals. Applied Physics A Materials Science and Processing 63:1, pages 19-29.
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H. Zou, G.M. Hood, R.J. Schultz & J.A. Roy. (1995) Thermal etching of α-Zr single-crystal surfaces. Applied Surface Science 90:1, pages 59-64.
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L.M. Howe, D. Phillips, H.H. Plattner & J.D. Bonnett. (1995) Collision cascades in Zr2Fe, Zr3Fe and ZrFe2. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 102:1-4, pages 77-80.
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M. Griffiths, R.C. Styles, C.H. Woo, F. Phillipp & W. Frank. (1994) Study of point defect mobilities in zirconium during electron irradiation in a high-voltage electron microscope. Journal of Nuclear Materials 208:3, pages 324-334.
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Malcolm Griffiths, D. Gilbon, C. Regnard & C. Lemaignan. (1993) HVEM study of the effects of alloying elements and impurities on radiation damage in Zr-alloys. Journal of Nuclear Materials 205, pages 273-283.
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L.M. Howe, M.H. Rainville, D. Phillips, H. Plattner & J.D. Bonnett. (1993) Collision cascades in Zr3Fe. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 80-81, pages 73-79.
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