Skip Ribbon Commands
Skip to main content

Researcher

Profile Picture

Michael McMurtrey, Ph.D.

Materials Scientist

Research Areas:
Materials Science and Engineering

Biography:
Dr. Michael D. McMurtrey is a materials scientist at Idaho National Laboratory with a research focus on qualification of Alloy 617 time-dependent deformation properties for use in high-temperature nuclear reactors, also in analysis of creep-fatigue results for alloys 709 and grade 92 FM steel. He earned his doctorate in nuclear engineering from University of Michigan and his bachelor’s in chemical engineering from Brigham Young University. His postdoctoral research was with Dr. James Burns at the University of Virginia’s Center for Electromechanical Science and Engineering. His honors include an Innovations in Fuel Cycle Research Award, first place in open competition for advanced materials (2011), and the INL top nuclear materials presentation at the American Nuclear Society 2010 Student Conference.

Education:

​Ph.D., Nuclear Engineering - University of Michigan

B.S., Chemical Engineering - Brigham Young University

Publications:

​Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel. M. McMurtrey, B. Cui, I. Robertson, D. Farkas, G. Was; Current Opinion in Solid State and Materials Science, 2015.

 

Strain localization at dislocation channel-grain boundary intersections in irradiated stainless steel. M. McMurtrey, G. Was, B. Cui, I. Robertson, L. Smith, D. Farkas; International Journal of Plasticity, vol. 56, pp 219-231, 2014.


 
Micromechanistic origin of irradiation-assisted stress corrosion cracking. B. Cui, M. McMurtrey, G. Was, I. Robertson; Philosophical Magazine, 2014.

 

Influence of irradiation damage on slip transfer across grain boundaries. B. Cui, J. Kacher, M. McMurtrey, G. Was, I. Robertson; Acta Materialia, vol. 65, pp 150-160, 2014.

 

Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy. M. McMurtrey, G. Was, L. Patrick, D. Farkas; Mater. Sci. Eng. A, vol. 528, pp 3730-3740, 2011.

 

Role of localized deformation in IASCC initiation. E. West, M. McMurtrey, Z. Jiao, G. Was; Mat. Trans. A, vol. 43, pp 136-146, 2012.

 

Strain-induced precipitate dissolution in an irradiated austenitic alloy. Z. Jaio, M. McMurtrey, G. Was; Scripta Materialia, vol. 65, no. 2, pp 159-162, 2011.

 

Conference Proceedings

Effect of High Altitude (Low Temperature and Water Vapor Pressure) Environments on Fatigue Crack Propagation Rates in Aerospace Aluminum Alloys. M. McMurtrey, J. Burns; Department of Defense – Allied Nations Technical Corrosion Conference, 2015.

 

Fracture Mechanics Modeling of Fatigue Crack Propagation from Field Corrosion Damage in Aluminum Alloys. M. McMurtrey, J. Burns; Department of Defense – Allied Nations Technical Corrosion Conference, 2015.

 

Relation between Irradiation Assisted Stress Corrosion Cracking and Discontinuous Slip at Grain Boundaries. M. McMurtrey, G. Was; Proceedings of the seventeenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2015.

 

Progression of local strain states at dislocation channel-grain boundary intersections and their relation to IASCC in austenitic steels. M. McMurtrey, G. Was; Proceedings of the sixteenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2013.

 

Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy. M. McMurtrey, G. Was, L. Patrick, D. Farkas, Transactions of the American Nuclear Society, 2011.

 

Role of slip behavior in the irradiation assisted stress corrosion cracking in austenitic steels. M. McMurtrey, G. Was, Proceedings of the fifteenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2011.

Presentations:

​Effect of High Altitude (Low Temperature and Water Vapor Pressure) Environments on Fatigue Crack Propagation Rates in Aerospace Aluminum Alloys. M. McMurtrey, J. Burns; Department of Defense – Allied Nations Technical Corrosion Conference, 2015.

 

Fracture Mechanics Modeling of Fatigue Crack Propagation from Field Corrosion Damage in Aluminum Alloys. M. McMurtrey, J. Burns; Department of Defense – Allied Nations Technical Corrosion Conference, 2015.

 

Relation between Irradiation Assisted Stress Corrosion Cracking and Discontinuous Slip at Grain Boundaries. M. McMurtrey, G. Was; Seventeenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2015.

 

Quantification of stress and strain states at dislocation channel-grain boundary intersections and their relation to IASCC in austenitic steels. M. McMurtrey, G. Was; Sixteenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2013.

 

Using EBSD to understand irradiation assisted stress corrosion cracking (Poster). M. McMurtrey, G. Was; Microanalysis Society EBSD conference, 2012.


 
Relationship between localized strain and irradiation assisted stress corrosion cracking in an austenitic alloy. M. McMurtrey, G. Was, L. Patrick, D. Farkas; 2011 ANS winter meeting and nuclear technology expo, 2011.

 

Role of slip behavior in the irradiation assisted stress corrosion cracking in austenitic steels. M. McMurtrey, G. Was, Fifteenth international conference on environmental degradation of materials in nuclear power systems water reactors, 2011.

 

Grain boundary characteristics influence on intergranular cracking of irradiated stainless steel. M. McMurtrey, E. West, G. Was; ANS student conference, 2010.

Version: 2.0
Created at 10/7/2016 11:01 AM by Phyllis L. King
Last modified at 10/7/2016 11:06 AM by Phyllis L. King