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Philosophical Magazine A Volume 67, 1993 - Issue 4
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Original Articles

Self-consistent calculation of steady-state creep and growth in textured zirconium

C. N. Tomé Reactor Materials Research Branch, Whiteshell Laboratories, Pinawa, Manitoba, Canada, ROE 1LO
,
C. B. So Reactor Materials Research Branch, Whiteshell Laboratories, Pinawa, Manitoba, Canada, ROE 1LO
&
C. H. Woo Reactor Materials Research Branch, Whiteshell Laboratories, Pinawa, Manitoba, Canada, ROE 1LO
Pages 917-930 | Received 22 Sep 1992, Accepted 05 Oct 1992, Published online: 13 Sep 2006

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J. E. Ramos Nervi, J. W. Signorelli & M. I. Idiart. (2022) A constitutive framework for steady-state creep in coarse-grained zirconium alloys under irradiation. Philosophical Magazine 102:7, pages 589-617.
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Anirban Patra, Carlos N. Tomé & Stanislav I. Golubov. (2017) Crystal plasticity modeling of irradiation growth in Zircaloy-2. Philosophical Magazine 97:23, pages 2018-2051.
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C.N. Tomé & N. Christodoulou. (2000) Analysis of accelerated irradiation growth in Zr-2.5% Nb pressure tubes. Philosophical Magazine A 80:6, pages 1407-1424.
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P.A. Turner, C.N. Tomé, N. Christodoulou & C.H. Woo. (1999) A self-consistent model for polycrystals undergoing simultaneous irradiation and thermal creep. Philosophical Magazine A 79:10, pages 2505-2524.
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C.H. Woo, A.R. Causey & R.A. Holt. (1999) Methods of analysis and measurement of irradiation creep in non-cubic metals. Philosophical Magazine A 79:1, pages 59-84.
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P.A. Turner, C.N. Tomé & C.H. Woo. (1994) Self-consistent modelling of nonlinear visco-elastic polycrystals: An approximate scheme. Philosophical Magazine A 70:4, pages 689-711.
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Articles from other publishers (33)

Cécilia Gicquel, Fabien Onimus, Renald Brenner, Thomas Helfer & Renaud Masson. 2023. Zirconium in the Nuclear Industry: 20th International Symposium. Zirconium in the Nuclear Industry: 20th International Symposium 118 148 .
Carlos N. Tomé & Ricardo A. Lebensohn. 2023. Material Modeling with the Visco-Plastic Self-Consistent (VPSC) Approach. Material Modeling with the Visco-Plastic Self-Consistent (VPSC) Approach 109 209 .
F. Onimus, L. Gélébart & R. Brenner. (2022) Polycrystalline simulations of in-reactor deformation of recrystallized Zircaloy-4 tubes: Fast Fourier Transform computations and mean-field self-consistent model. International Journal of Plasticity 153, pages 103272.
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Nicolas Christodoulou. 2022. Pressurized Heavy Water Reactors. Pressurized Heavy Water Reactors 69 133 .
Fabien Onimus, Sylvie Doriot & J.-L. Béchade. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 1 56 .
Malcolm Griffiths. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 367 405 .
Fabien Onimus, Thomas Jourdan, Cheng Xu, Anne A. Campbell & Malcolm Griffiths. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 310 366 .
Ronald B. Adamson, Christopher E. Coleman & Malcolm Griffiths. (2019) Irradiation creep and growth of zirconium alloys: A critical review. Journal of Nuclear Materials 521, pages 167-244.
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Anirban Patra & Carlos N. Tomé. (2017) Finite element simulation of gap opening between cladding tube and spacer grid in a fuel rod assembly using crystallographic models of irradiation growth and creep. Nuclear Engineering and Design 315, pages 155-169.
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R.W.L. Fong. (2013) Anisotropy factors from texture and mechanical strain in Zircaloy-4 fuel sheaths. Journal of Nuclear Materials 440:1-3, pages 288-297.
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Randy Fong, Sven Vogel, Ron Miller & Henry Saari. 2013. PRICM. PRICM 71 78 .
Randy Fong, Sven Vogel, Ron Miller & Henry Saari. 2016. Proceedings of the 8th Pacific Rim International Congress on Advanced Materials and Processing. Proceedings of the 8th Pacific Rim International Congress on Advanced Materials and Processing 71 78 .
W. LiR. A. HoltS. Tracy. 2012. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 298 326 .
Magnus Limbäck & Pierre BarbérisW. Li, R. A. Holt & S. Tracy. 2012. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 298 326 .
W. Li, R. A. Holt & S. Tracy. 2011. Zirconium in the Nuclear Industry: 16th International Symposium. Zirconium in the Nuclear Industry: 16th International Symposium 298 326 .
W. Li, R.A. Holt, M.R. Daymond & F. Xu. (2011) Influence of prior dislocation structure on anisotropy of thermal creep of cold-worked Zr–2.5Nb tubes. Journal of Nuclear Materials 412:1, pages 138-144.
Crossref
W. Li, R. A. Holt & S. Tracy. (2011) Polycrystalline Modeling of the Effect of Texture and Dislocation Microstructure on Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes. Journal of ASTM International 8:2, pages 1-19.
Crossref
Ronald B. AdamsonR. A. Holt. 2010. Zirconium Production and Technology: The Kroll Medal Papers 1975–2010. Zirconium Production and Technology: The Kroll Medal Papers 1975–2010 411 426 .
Bruce Kammenzind & Magnus LimbäckR. A. Holt. 2009. Zirconium in the Nuclear Industry: 15th International Symposium. Zirconium in the Nuclear Industry: 15th International Symposium 3 18 .
R. A. Holt. (2008) In-Reactor Deformation of Zirconium Alloy Components. Journal of ASTM International 5:6, pages 1-16.
Crossref
R.A. Holt, G.A. Bickel & N. Christodoulou. (2008) Effect of fast neutron fluence on the creep anisotropy of Zr–2.5Nb tubes. Journal of Nuclear Materials 373:1-3, pages 130-136.
Crossref
R.A. Holt. (2008) In-reactor deformation of cold-worked Zr–2.5Nb pressure tubes. Journal of Nuclear Materials 372:2-3, pages 182-214.
Crossref
P Rudling & B KammenzindL Gélébart, J Crépin, M Dexet, M Sauzay & A Roos. 2005. Zirconium in the Nuclear Industry: Fourteenth International Symposium. Zirconium in the Nuclear Industry: Fourteenth International Symposium 585 603 .
L Gélébart, J Crépin, M Dexet, M Sauzay & A Roos. (2004) Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys. Journal of ASTM International 1:9, pages 1-17.
Crossref
R.A. Holt, N. Christodoulou & A.R. Causey. (2003) Anisotropy of in-reactor deformation of Zr–2.5Nb pressure tubes. Journal of Nuclear Materials 317:2-3, pages 256-260.
Crossref
D.X. Du & C.H. Woo. (2002) Effect of grain-structure topology in modelling aggregate irradiation creep behaviour of two-phase alloys. Computational Materials Science 23:1-4, pages 260-269.
Crossref
N. Christodoulou, M. Resta Levi, P. A. Turner, E. T. C. Ho & C. K. Chow. (2000) Anisotropy of yielding in a Zr-2.5Nb pressure tube material. Metallurgical and Materials Transactions A 31:2, pages 409-420.
Crossref
GP Sabol & GD MoanAR Causey, RA Holt, N Christodoulou & ETC Ho. 2000. Zirconium in the Nuclear Industry: Twelfth International Symposium. Zirconium in the Nuclear Industry: Twelfth International Symposium 74 85 .
R A Lebensohn, P A Turner, J W Signorelli, G R Canova & C N Tomé. (1998) Calculation of intergranular stresses based on a large-strain viscoplastic self-consistent polycrystal model. Modelling and Simulation in Materials Science and Engineering 6:4, pages 447-465.
Crossref
ER Bradley & GP SabolN Christodoulou, AR Causey, RA Holt, CN Tomé, N Badie, RJ Klassen, R Sauvé & CH Woo. 1996. Zirconium in the Nuclear Industry: Eleventh International Symposium. Zirconium in the Nuclear Industry: Eleventh International Symposium 518 537 .
C.N. Tomé, N. Christodoulou, P.A. Turner, M.A. Miller, C.H. Woo, J. Root & T.M. Holden. (1996) Role of internal stresses in the transient of irradiation growth of Zircaloy-2. Journal of Nuclear Materials 227:3, pages 237-250.
Crossref
J.R. Fernández, A.M. Monti, A. Sarce & N.Smetniansky-De Grande. (1994) Pressure tube deformations predicted via a microstructural evolution description. Journal of Nuclear Materials 210:3, pages 282-289.
Crossref
AM Garde & ER BradleyAR Causey, JE Elder, RA Holt & RG Fleck. 1994. Zirconium in the Nuclear Industry: Tenth International Symposium. Zirconium in the Nuclear Industry: Tenth International Symposium 202 220 .

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