Crystal plasticity modeling of irradiation growth in Zircaloy-2

References

• S.N. Buckley, Irradiation growth, in Proceedings in International Conference: Properties of Reactor Materials and Effects of Irradiation Damage, Butterworths, London, 1962, p. 413.
   Google Scholar
• V. Fidleris, The irradiation creep and growth phenomena, J. Nucl. Mater. 159 (1988), pp. 22–42.10.1016/0022-3115(88)90083-9
   Web of Science ®Google Scholar
• G.J.C. Carpenter, R.H. Zee, and A. Rogerson, Irradiation growth of zirconium single crystals: A review, J. Nucl. Mater. 159 (1988), pp. 86–100.10.1016/0022-3115(88)90087-6
   Web of Science ®Google Scholar
• A. Rogerson, Irradiation growth in zirconium and its alloys, J. Nucl. Mater. 159 (Oct. 1988), pp. 43–61.
   Web of Science ®Google Scholar
• R.A. Holt, In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes, J. Nucl. Mater. 372(2–3) (2008), pp. 182–214.10.1016/j.jnucmat.2007.02.017
   Web of Science ®Google Scholar
• R.A. Holt, In-reactor deformation of Zirconium alloy components, J. ASTM Int. 5(6) (2008), pp. 3–18.
   Google Scholar
• A.R. Causey, C.H. Woo, and R.A. Holt, The effect of intergranular stresses on the texture dependence of irradiation growth in zirconium alloys, J. Nucl. Mater. 159 (1988), pp. 225–236.10.1016/0022-3115(88)90095-5
   Web of Science ®Google Scholar
• G.S. Was, Fundamentals of Radiation Material Science: Metals and Alloys, Springer, Berlin, 2007.
   Google Scholar
• M. Griffiths, R.A. Holt, and A. Rogerson, Microstructural aspects of accelerated deformation of Zircaloy nuclear reactor components during service, J. Nucl. Mater. 225 (1995), pp. 245–258.10.1016/0022-3115(94)00687-3
   Web of Science ®Google Scholar
• R.A. Holt and R.W. Gilbert, 〈c〉 Component dislocations in annealed Zircaloy irradiated at about 570 K, J. Nucl. Mater. 137(3) (1986), pp. 185–189.10.1016/0022-3115(86)90218-7
   Web of Science ®Google Scholar
• M. Griffiths and R.W. Gilbert, The formation of c-component defects in zirconium alloys during neutron irradiation, J. Nucl. Mater. 150(2) (1987), pp. 169–181.10.1016/0022-3115(87)90072-9
   Web of Science ®Google Scholar
• R.A. Murgatroyd and A. Rogerson, An assessment of the influence of microstructure and test conditions on the irradiation growth phenomenon in zirconium alloys, J. Nucl. Mater. 90(1–3) (1980), pp. 240–248.10.1016/0022-3115(80)90261-5
   Web of Science ®Google Scholar
• R.H. Zee, G.J.C. Carpenter, A. Rogerson, and J.F. Watters, Irradiation growth in deformed zirconium, J. Nucl. Mater. 150(3) (1987), pp. 319–330.10.1016/0022-3115(87)90010-9
   Web of Science ®Google Scholar
• R.A. Holt, A.R. Causey, N. Christodoulou, M. Griffiths, E.T.C. Ho, and C.H. Woo, Non-linear irradiation growth of cold-worked Zircaloy-2, presented at the Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E.R. Bradley and G.P. Sabol, eds., American Society for Testing and Materials,1996, pp. 623–637.
   Google Scholar
• M. Griffiths, A review of microstructure evolution in zirconium alloys during irradiation, J. Nucl. Mater. 159 (1988), pp. 190–218.10.1016/0022-3115(88)90093-1
   Web of Science ®Google Scholar
• C. Hellio, C.H. de Novion, and L. Boulanger, Influence of alloying elements on the dislocation loops created by Zr+ ion or by electron irradiation in α-zirconium, J. Nucl. Mater. 159 (1988), pp. 368–378.10.1016/0022-3115(88)90103-1
   Web of Science ®Google Scholar
• M. Griffiths, D. Gilbon, C. Regnard, and C. Lemaignan, HVEM study of the effects of alloying elements and impurities on radiation damage in Zr-alloys, J. Nucl. Mater. 205 (1993), pp. 273–283.10.1016/0022-3115(93)90090-L
   Web of Science ®Google Scholar
• P.A. Turner and C.N. Tomé, Self-consistent modeling of visco-elastic polycrystals: Application to irradiation creep and growth, J. Mech. Phys. Solids 41(7) (1993), pp. 1191–1211.10.1016/0022-5096(93)90090-3
   Web of Science ®Google Scholar
• C.N. Tomé, N. Christodoulou, P. A. Turner, M. A. Miller, C. H. Woo, J. Root, and T. M. Holden, Role of internal stresses in the transient of irradiation growth of Zircaloy-2, J. Nucl. Mater. 227(3) (1996), pp. 237–250.10.1016/0022-3115(95)00140-9
   Web of Science ®Google Scholar
• P.A. Turner, C.N. Tomé, N. Christodoulou, and C.H. Woo, A self-consistent model for polycrystals undergoing simultaneous irradiation and thermal creep, Philos. Mag. A 79(10) (1999), pp. 2505–2524.10.1080/01418619908214296
   Web of Science ®Google Scholar
• C.N. Tomé, C.B. So, and C.H. Woo, Self-consistent calculation of steady-state creep and growth in textured zirconium, Philos. Mag. A 67(4) (1993), pp. 917–930.10.1080/01418619308213968
   Web of Science ®Google Scholar
• R. Bullough and M.H. Wood, Mechanisms of radiation induced creep and growth, J. Nucl. Mater. 90(1–3) (1980), pp. 1–21.10.1016/0022-3115(80)90241-X
   Web of Science ®Google Scholar
• C.H. Woo and U. Gösele, Dislocation bias in an anisotropic diffusive medium and irradiation growth, J. Nucl. Mater. 119(2–3) (1983), pp. 219–228.10.1016/0022-3115(83)90198-8
   Web of Science ®Google Scholar
• C.H. Woo, Theory of irradiation deformation in non-cubic metals: Effects of anisotropic diffusion, J. Nucl. Mater. 159 (1988), pp. 237–256.10.1016/0022-3115(88)90096-7
   Web of Science ®Google Scholar
• R.A. Holt, C.H. Woo, and C.K. Chow, Production bias – A potential driving force for irradiation growth, J. Nucl. Mater. 205 (1993), pp. 293–300.10.1016/0022-3115(93)90092-D
   Web of Science ®Google Scholar
• F. Christien and A. Barbu, Cluster dynamics modelling of irradiation growth of zirconium single crystals, J. Nucl. Mater. 393(1) (2009), pp. 153–161.10.1016/j.jnucmat.2009.05.016
   Web of Science ®Google Scholar
• S.I. Golubov, A.V. Barashev, and R.E. Stoller, On the origin of radiation growth of hcp crystals, ORNL/TM-2011/473, Oak Ridge, TN, ORNL/TM-2011/473, Oak Ridge National Laboratory, 2011.
   Google Scholar
• A.V. Barashev, S.I. Golubov, and R.E. Stoller, Theoretical investigation of microstructure evolution and deformation of zirconium under neutron irradiation, J. Nucl. Mater. 461 (2015), pp. 85–94.10.1016/j.jnucmat.2015.02.001
   Web of Science ®Google Scholar
• S.I. Golubov, A.V. Barashev, R.E. Stoller, and B.N. Singh, Breakthrough in understanding radiation growth of zirconium, in Zirconium in the Nuclear Industry, 17th International Symposium, STP 1543, Robert Comstock and Pierre Barberis, eds., ASTM International, West Conshohocken, PA, 2014, pp. 729–758.
   Google Scholar
• R.A. Lebensohn and C.N. Tomé, A self-consistent anisotropic approach for the simulation of plastic deformation and texture development of polycrystals: Application to zirconium alloys, Acta Metall. Mater. 41(9) (1993), pp. 2611–2624.10.1016/0956-7151(93)90130-K
   Google Scholar
• G.D. Samolyuk, A.V. Barashev, S.I. Golubov, Y.N. Osetsky, and R.E. Stoller, Analysis of the anisotropy of point defect diffusion in hcp Zr, Acta Mater. 78 (2014), pp. 173–180.10.1016/j.actamat.2014.06.024
   Web of Science ®Google Scholar
• S.J. Wooding, L.M. Howe, F. Gao, A.F. Calder, and D.J. Bacon, A molecular dynamics study of high-energy displacement cascades in α-zirconium, J. Nucl. Mater. 254(2–3) (1998), pp. 191–204.10.1016/S0022-3115(97)00365-6
   Web of Science ®Google Scholar
• F. Gao, D.J. Bacon, L.M. Howe, and C.B. So, Temperature-dependence of defect creation and clustering by displacement cascades in α-zirconium, J. Nucl. Mater. 294(3) (2001), pp. 288–298.10.1016/S0022-3115(01)00483-4
   Web of Science ®Google Scholar
• M.J. Norgett, M.T. Robinson, and I.M. Torrens, A proposed method of calculating displacement dose rates, Nucl. Eng. Des 33(1) (1975), pp. 50–54.10.1016/0029-5493(75)90035-7
   Web of Science ®Google Scholar
• S.I. Golubov, A.V. Barashev, and R.E. Stoller, Reaction rate theory, in Reference Module in Materials Science and Materials Engineering, Saleem Hashmi, editor-in-chief, Elsevier, Oxford, 2016, pp. 1–41.
   Google Scholar
• B.N. Singh, M. Eldrup, S.J. Zinkle, and S.I. Golubov, On grain-size-dependent void swelling in pure copper irradiated with fission neutrons, Philos. Mag. A 82(6) (2002), pp. 1137–1158.10.1080/01418610208240021
   Google Scholar
• S.I. Golubov, A.V. Barashev, and R.E. Stoller, 1.13 – Radiation damage theory, in Comprehensive Nuclear Materials, R.J.M. Konings, ed., Elsevier, Oxford, 2012, pp. 357–391.
   Google Scholar
• F. Christien and A. Barbu, Effect of self-interstitial diffusion anisotropy in electron-irradiated zirconium: A cluster dynamics modeling, J. Nucl. Mater. 346(2–3) (2005), pp. 272–281.10.1016/j.jnucmat.2005.06.024
   Web of Science ®Google Scholar
• E. Orowan, Problems of plastic gliding, Proc. Phys. Soc. 52(1) (1940), pp. 8–22.10.1088/0959-5309/52/1/303
   Google Scholar
• D. Fainstein-Pedraza, E.J. Savino, and A.J. Pedraza, Irradiation-growth of zirconium-base alloys, J. Nucl. Mater. 73(2) (1978), pp. 151–168.10.1016/0022-3115(78)90556-1
   Web of Science ®Google Scholar
• J.P. Foster, W.G. Wolfer, A. Biancheria, and A. Boltax, Analysis of irradiation-induced creep of stainless steel in fast spectrum reactors, in Proceedings of the BNES Conference on Irradiation Embrittlement and Creep in Fuel Cladding and Core Components, London, UK, 1972, p. 273.
   Google Scholar
• K. Ehrlich, Irradiation creep and interrelation with swelling in austenitic stainless steels, J. Nucl. Mater. 100(1–3) (1981), pp. 149–166.10.1016/0022-3115(81)90531-6
   Web of Science ®Google Scholar
• L.K. Mansur, Irradiation creep by climb-enabled glide of dislocations resulting from preferred absorption of point defects, Philos. Mag. A 39(4) (1979), pp. 497–506.10.1080/01418617908239286
   Web of Science ®Google Scholar
• S.I. Golubov, A.V. Barashev, and F.A. Garner, A feasible mechanism of irradiation creep explaining its observed cessation at high neutron doses, manuscript in preparation.
   Google Scholar
• M. Griffiths, R.W. Gilbert, V. Fidleris, R.P. Tucker, and R.B. Adamson, Neutron damage in zirconium alloys irradiated at 644 to 710 k, J. Nucl. Mater. 150(2) (1987), pp. 159–168.10.1016/0022-3115(87)90071-7
   Web of Science ®Google Scholar
• M. Griffiths, M.H. Loretto, and R.E. Smallman, Anisotropic distribution of dislocation loops in HVEM-irradiated Zr, Philos. Mag. A 49(5) (1984), pp. 613–624.10.1080/01418618408233290
   Web of Science ®Google Scholar
• M. Griffiths, M.H. Loretto, and R.E. Smallman, Electron damage in zirconium, J. Nucl. Mater. 115(2–3) (1983), pp. 323–330.10.1016/0022-3115(83)90323-9
   Web of Science ®Google Scholar
• M. Griffiths, R.W. Gilbert, and G.J.C. Carpenter, Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation, J. Nucl. Mater. 150(1) (1987), pp. 53–66.10.1016/0022-3115(87)90093-6
   Web of Science ®Google Scholar
• M. Topping, A. Harte, P. Frankel, G. Sundell, M. Thuvander, H. Andren, D. Jadernas, P. Teiland, J. Romero, E. Darby, S. Dumbill, L. Hallstadius, and M. Preuss, The effect of iron on dislocation evolution in model and commercial Zirconium alloys, in 18th International Symposium on Zirconium in the Nuclear Industry, Hilton Head, SC, 2016.
   Google Scholar
• Y. Idrees, E. Francis, Z. Yao, A. Korinek, M.A. Kirk, M. Sattari, M. Preuss, M. Daymond, Effects of alloying elements on the formation of -component loops in Zr alloy Excel under heavy ion irradiation, J. Mater. Res. 30(09) (2015), pp. 1310–1334.10.1557/jmr.2015.89
   Web of Science ®Google Scholar
• B.M. Pande and M.S. Anand, Low temperature (4.6 K) fast neutron irradiation of zirconium and zircaloys 2 and 4: Dose and recovery studies, J. Nucl. Mater. 92(2–3) (1980), pp. 313–317.10.1016/0022-3115(80)90116-6
   Web of Science ®Google Scholar
• H.H. Neely, Damage rate and recovery measurements on zirconium after electron irradiation at low temperatures, Rad. Effect 3(2) (1970), pp. 189–201.10.1080/00337577008236274
   Google Scholar
• L. Tournadre, F. Onimus, J. -L. Béchade, D. Gilbon, J. -M. Cloué, J. -P. Mardon, X. Feaugas, Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys, J. Nucl. Mater. 441(1–3) (2013), pp. 222–231.10.1016/j.jnucmat.2013.05.045
   Web of Science ®Google Scholar
• G.S. Was, Challenges to the use of ion irradiation for emulating reactor irradiation, J. Mater. Res. 30(09) (2015), pp. 1158–1182.10.1557/jmr.2015.73
   Web of Science ®Google Scholar
• R.A. Murgatroyd and A. Rogerson, Irradiation growth in zirconium and its alloys, in BNES Conference on Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys, London, UK, 1984, p. 93.
   Google Scholar
• V. Fidleris, R.P. Tucker, and R.B. Adamson, An overview of microstructural and experimental factors that affect the irradiation growth behavior of zirconium alloys, in Zirconium in the Nuclear Industry: 7th International Symposium vol. 939, R.B. Adamson and L.F.P. Von Swam, eds., ASTM Spec. Techn. Publ, 1987, pp. 49–85.
   Google Scholar
• A. Patra, C.N. Tomé, S.I. Golubov, and A.V. Barashev, Modeling radiation-induced deformation of Zr-based polycrystals with novel mechanisms of radiation growth and creep, manuscript in preparation.
   Google Scholar
• F. Tinti, Uniaxial in-reactor creep of Zircaloy-2: Stress, flux, and temperature dependence, Nucl. Technol. 60(1) (1983), pp. 104–113.
   Web of Science ®Google Scholar