Rick Holt P.Eng

Areas of Interest 

• Nuclear materials/zirconium alloys 
• Crystallographic texture/anisotropy 
• Modelling materials behaviour 

Planned Research 

• Control of microstructure and texture of zirconium alloy tubes. 
• Experimental study of anisotropy and deformation of zirconium alloys. 
• Modelling anisotropy and deformation of zirconium alloys. 
• Effects of deformation characteristics on the development of plastic instability and failure. 
• Mechanical properties of corrosion resistant nickel alloys. 
• Improved X-ray diffraction techniques for the measurement of crystallographic texture and the evaluation of dislocation substructure. 
• Improved techniques for microstructural characterization and quantification by analytical and scanning electron microscopy. 
• Macro- and microscopic stress and strain states of materials using neutron and X-ray diffraction, development during manufacture, evolution during service, effects on in-service performance. 
• Modelling evolution of crystallographic texture during metal forming. 
• Analysis and interpretation of power reactor data. 
• Theory of radiation damage and in-reactor deformation 

Links 

• Canadian Nuclear Society 
• Canadian Nuclear Association 
• Canadian Nuclear Safety Commission 
• Kinectrics Inc. 
• American Nuclear Society 

Refereed Journals 

• Deformation of Zirconium Irradiated by 4.4MeV Protons at 340K, C.K. Chow, R.A. Holt, C.H. Woo and C.B. So, accepted for publication in J. Nucl. Mater., 2003. 
• Anisotropy of In-reactor Deformation of Zr-2.5Nb Pressure Tubes, R.A. Holt, N. Christodoulou and A.R. Causey, J. Nucl. Mater., Vol. 317, 2002, pp 256-260. 
• Thermally and Plastically Induced Residual Strains in Textured Zircaloy-2 Plate, T.M Holden, J.H. Root, R.A. Holt and P.A. Turner, Journal of Nuclear Materials, Vol. 304 (2002) pp73-82. 
• Life Management of CANDU Fuel Channels, R.A. Holt and H.W. Wong, Nuclear Energy, Vol. 40 (2002) pp 69-74 see also refereed conference proceedings, # 17). 
• Determination of Dislocation densities in HCP metals from XRD Line-Broadening Analysis, M. Griffiths, D. Sage, R.A. Holt and C.N. Tome, Metallurgical and Materials Transactions, Vol. 33A (2002) pp. 859-865. 
• Intergranular Stresses in Zircaloy-2, T.M Holden, R.A. Holt and J.W.L. Pang, Metallurgical and Materials Transactions, Vol. 33A (2002), pp. 749-755. 
• Intergranular Strains in Inconel 600, T.M Holden, R.A. Holt and C.N. Tome, Mater. Sci. and Eng., A282 (2000) pp 131-136. 
• Measurement and Analysis of Irradiation Creep in Non-cubic Metals, C.H. Woo, A.R. Causey and R.A. Holt, Philosophical Magazine A, Vol. 79, No. 1 (1999) 59-84. 
• Micro-texture Analysis of Zr-2.5Nb Pressure Tubes, M. Griffiths, R.A. Holt, J. Li and S. Saimoto, Microstructural Science, ASM International, Vol. 26 (1999) 293-302. 
• Measurement and Analysis of Irradiation Creep in Non-cubic Metals, C.H. Woo, A.R. Causey and R.A. Holt, Philosophical Magazine A, Vol. 79, No. 1 (1999) 59-84. 
• Experimental and Theoretical Studies of the Superposition of Intergranular and Macroscopic Strains in Ni-Based Industrial Alloys, T.M. Holden, C.N. Tome and R.A. Holt, Metallurgical and Materials Transactions A, Vol. 29 (1998) pp 2968-2974. 
• Intergranular Strains in Inconel 600 and their Impact on the Interpretation of Stress Fields in Bent Steam-Generator Tubes , T.M. Holden, R.A. Holt and A.P. Clarke, Materials Science and Engineering, A246 (1998) 180-198. 
• Intergranular Strains in Inconel-600 Steam Generator Materials, T.M. Holden, R.A. Holt and C.N. Tome, Physica B 241-243 (1998) pp1246-1248. 
• Intergranular Stresses in Incoloy-800, T.M. Holden, A.P. Clarke and R.A. Holt, J. Neutron Research, 5 (1997) p 241. 
• Neutron Diffraction Measurements of Intergranular Strains in Monel 400, T.M. Holden, R.A. Holt and A.P Clarke, Metall. Trans. A, 28A (1997) p 2565. 
• Neutron Diffraction Measurements of Stress, T.M. Holden, J.H. Root, R.A. Holt and M. Hayashi, Physica B (Condensed Matter) vol. 213&214 (1995) pp793-796. 
• Microstructural Aspects of Accelerated Deformation of Zircaloy Nuclear Reactor Components During Service, M. Griffiths, R.A. Holt and A. Rogerson, Journal of Nuclear Materials, 225 (1995) pp245-258 
• Microstructure and Microchemical studies of Zr-Nb Pressure Tube Alloy, V. Perovic, A. Perovic, G.C. Weatherly, L.M. Brown, G.R. Purdy, R.G. Fleck and R.A. Holt, J. Nucl. Mat. 205(1993)251. 
• Production Bias - a Potential Driving Force for Irradiation Growth, R.A. Holt, C.H. Woo and C.K. Chow, J. Nucl. Mat. 205 (1993) 293-300. 
• Industrial Research and Development and the Role of Neutron Diffraction, T.M. Holden, J.H. Root, D.C. Tenant, R.R. Hosbons, R.A. Holt, K.W. Mahin and D. Legget, Physica B, Vol. 180 & 181 (1992) 1014-1020. 
• Determination of Dislocation Densities in HCP Metals using X-Ray Diffraction and Transmission Electron Microscopy, M. Griffiths, J.E. Winegar, J.F. Mecke and R.A. Holt, Advances in X-Ray Analysis, Vol. 35 (1992) 593-599. 
• A Comparison of X-Ray and Neutron Diffraction Measurement of Lattice Parameters for the Determination of Residual Stress and Chemical Compositio in Zr Alloys, M. Griffiths, J.E. winegar, J.F. Mecke, T.M. Holden and R.A. Holt, Advances in X-Ray Analysis, Vol. 35 (1992) 475-480. 

Refereed Conference Proceedings 

• Irradiation Growth of Zirconium at Low Temperatures by Displacement Cascade Anisotropy, accepted for publication in Proc. 11th International Symposium on Reactor Dosimetry, American Society for Testing and Materials, Brussels, August 2002. 
• Variability of in-reactor Diametral Deformation for Zr-2.5Nb Pressure Tubing, M. Griffiths, W.G. Davies, G.D. Moan, R.A. Holt, A.R. Causey and S.A. Aldridge, submitted to ASTM for Publication in Proc. 13th International Symposium on Zirconium in the Nuclear Industry, Annecy, France, 2001 June. 
• Life Management of CANDU Fuel Channels, R.A. Holt and H.W. Wong, Structural Integrity in the 21st Century, Proc. 5th International Conference on Structural Integrity Assessment, J.H. Edwards, P.E.J. Flewitt, B.C. Gasper, K.A. McLarty, R.A. Smith, P. Stanley, J.A.G. Temple and B. Tomkins, EMAS Publishing (2000) pp 459-468. 
• Irradiation-Enhanced Creep of Zr-2.5Nb Tubes at High Neutron Fluence, A.R. Causey, R.A. Holt, N. Christodoulou and E.T.C. Ho, Proc. 12th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1354 (2000) pp 74-85. 
• High Fluence Irradiation Growth of Cold-Worked Zr-2.5Nb, R.A. Holt, A.R. Causey, M. Griffiths and E.T.C. Ho, Proc. 12th International Symposium on Zirconium in the Nuclear Industry, ASTM STP 1354 (2000) pp 86-104. 
• Research and Development in Support of CANDU Plant Life Management, R.L. Tapping and R.A. Holt, Proc. SIEN 99, Bucharest, Romania, 1999 Oct. 
• The Impact of Intergranular Strains on Interpreting Stress Fields in Inconel-600 Steam Generator Tubes, T.M. Holden, A.P. Clarke and R.A. Holt, Proc. Fifth International Conference on Residual Stress, Linkoping University, 1997 Vol. 2, pp 1066-1071. 
• The Impact of Intergranular Strains on Interpreting Stress Fields in Inconel-600 Steam Generator Tubes, T.M. Holden, A.P. Clarke and R.A. Holt, Proc. Fifth International Conference on Residual Stress, Linkoping University, 1997 Vol. 2, pp 1066-1071. 
• Modelling In-reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors, N. Christodoulou, A.R. Causey, R.A. Holt, C.N. Tome, N. Badie, R.J. Klassen, R. Sauve and C.H. Woo, proc. 11th International Conference on Zirconium in the Nuclear Industry, ASTM STP 1295 (1996) pp 518-537. 
• Non-linear Irradiation Growth of Cold-worked Zircaloy-2, R.A. Holt, A.R. Causey, N. Christodoulou, M. Griffiths, E.T.C. Ho and C.H. Woo, proceedings of the 11th International Conference on Zirconium in the Nuclear Industry, ASTM-STP 1295 (1996) pp 623-637. 
• Non-linear Irradiation Growth of Cold-worked Zircaloy-2, R.A. Holt, A.R. Causey, N. Christodoulou, M. Griffiths, E.T.C. Ho and C.H. Woo, proceedings of the 11th International Conference on Zirconium in the Nuclear Industry, ASTM-STP 1295 (1996) pp 623-637. 
• Modelling In-reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors, N. Christodoulou, A.R. Causey, R.A. Holt, C.N. Tome, N. Badie, R.J. Klassen, R. Sauve and C.H. Woo, proc. 11th International Conference on Zirconium in the Nuclear Industry, ASTM STP 1295 (1996) pp 518-537. 
• Variability of Irradiation Growth in Zr-2.5Nb Pressure Tubes, R.G. Fleck, J.E. Elder, A.R. Causey and R.A. Holt, Proc. Zirconium in the Nuclear Industry - 9th Conference, ASTM-STP 1245 (1994) pp 168-182. 
• On the Anisotropy of In-Reactor Creep of Zr-2.5Nb, A.R. Causey, J.E. Elder, R.A. Holt and R.G. Fleck, Proc. Zirconium in the Nuclear Industry - 9th Conference, ASTM STP 1245 (1994) pp 202-220. 
• Deconvolution of Experimental Data of Aggregates using Self-consistent Polycrystal Models, N. Christodoulou, R.A, Holt, C.H. Woo, R.A. Lebensohn and P.A. Turner, Proc. 15th Riso Conference on Material Science, 1994. 
• Irradiation Creep due to SIPA under Cascade Damage Conditions, C.H. Woo, F.A. Garner and R.A. Holt, Proc. Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175 (1993) 27-37. 
• Modelling the Effect of Texture and Dislocation Structure on Irradiation Creep of Zirconium Alloys, N. Christodoulou, A.R. Causey, C.H. Woo, C.N. Tome, R.J. Klassen and R.A. Holt, Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175 (1993) 1111-1128. 
• Evolution of Microstructure in Zr Alloy Core Components of Nuclear Reactors during Service, M. Griffiths, C.K. Chow, C.E. Coleman, R.A. Holt, S. Sagat and V.F. Urbanic, Proc. Effects of Radiation on Materials: 16th International Symposium, ASTM STP 1175 (1993) 1077-1110. 
• Anisotropic Diffusion of Point Defects: Effects on Irradiation-Induced Deformation and Microstructure, C.H. Woo, R.A. Holt and M. Griffiths, Proc. International Conference on Materials Modelling: from Theory to Technology, the Institute of Physics, London (1992) 55-60. 

Funding 

• NSERC  
• Industrial Research Chair in Nuclear Materials 
• Discovery Grant - Corrosion Resistant Nickel Alloys 
• Ontario Power Generation Inc. (OPG) 
• CANDU Owners Group (COG)  
• OPG 
• Bruce Power 
• Atomic Energy of Canada Ltd. (AECL) 
• New Brunswick Power (NBP) 
• Hydro Quebec(HQ) 
• Nu-Tech Precision Metals Inc. 

Awards 

1994: ASTM Russ Ogden Award for Outstanding Contributions to the Science and Technology of Reactive and Refractory Metals 

Graduate Student Incentives 

The Industrial Research Chair in Nuclear Materials has been established at the initiative of the Canadian Nuclear Industry. This is the first in a series of five chairs being established as part of the new Universities' Centre of Excellence in Nuclear Engineering (UNENE) sponsored by Ontario Power, Bruce Power, COG and the Canadian Nuclear Safety Commission. The main thrusts are to supplement the R&D capabilities of AECL and Kinectrics Inc. (formerly Ontario Hydro Research) and to train new highly qualified staff to work in engineering or research and development, both to manage and extend the life of existing plants, and to develop the Advanced CANDU Reactor (ACR). In addition to support of graduate students through the R&D budget of the Chair, UNENE offers research scholarships. The Chair program also offers the opportunity for part or all of a student's research to be carried out at the industrial nuclear R&D laboratories, co-supervised by the staff of those laboratories, either during a paid work term, or as a full time employee. 

Research Group