Progress Energy Distinguished Professor of Nuclear Engineering, Director of Nuclear Engineering Graduate Program
- Burlington Laboratory 3143
I have been interested in the deformation, creep, fatigue and fracture behaviors of nuclear core and pressure boundary materials, with particular emphasis on structureproperty relationship and effects of radiation exposure. I am also interested in radiation-enhanced hydrogen transport into steels used for radioactive waste containers and the subsequent embrittlement with reference to their integrity. We are actively pursuing studies on the effects of fabrication processes on crystallographic texture and the resulting anisotropic mechanical properties of Zircaloy cladding, with application to the understanding of pellet-cladding mechanical interaction.
One of the major areas of my research is on the basic deformation mechanisms in materials, and I have been developing model creep equations to predict the in-service materials’ deformation behavior. In addition, I am interested in the micro mechanisms of macroscopic crack propagation. These studies involve mechanical testing, sub structural studies using electron microscopy and basic deformation model development. One of the research areas underway is the effect of crystallographic texture, stacking-fault energy and crystal structure on the anisotropic mechanical deformation and creep of hexagonal close-packed metals.
Other research areas include in-site NMR studies of the dynamical behavior of point and line defects in materials during deformation, ball indentation for non-destructive evaluation of materials’ condition in-service and mechanical integrity of electronic packaging materials.
Dr. Murty is interested in the deformation, creep, fatigue and fracture behaviors of nuclear core and pressure boundary materials, with particular emphasis on structureproperty relationship and effects of radiation exposure.
- Understanding thermally activated plastic deformation behavior of Zircaloy-4
- Kumar, N., Alomari, A., & Murty, K. L. (2018), Journal of Nuclear Materials, 504, 41-49.
- Nanotwins induced by pulsed laser and their hardening effect in a Zr alloy
- Chai, L. J., Chen, K., Zhi, Y., Murty, K. L., Chen, L. Y., & Yang, Z. N. (2018), Journal of Alloys and Compounds, 748, 163-170.
- Formability of a wrought Mg alloy evaluated by impression testing
- Mohamed, W., Gollapudi, S., Charit, I., & Murty, K. L. (2018), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 712, 140-145.
- Evolution of microstructure and second-phase particles in Zr-Sn-Nb-Fe alloy tube during Pilger processing
- Qiu, R. S., Song, Z. L., Luan, B. F., Yue, Q., Wang, L., Yuan, G. H., Murty, K. L., & Liu, Q. (2017), Journal of Nuclear Science and Technology, 54(12), 1321-1329.
- Understanding effect of 3.5 wt.% NaCl on the corrosion of Al0.1CoCrFeNi high-entropy alloy
- Kumar, N., Fusco, M., Komarasamy, M., Mishra, R. S., Bourham, M., & Murty, K. L. (2017), Journal of Nuclear Materials, 495, 154-163.
- Understanding plastic deformation mechanism(s) in recrystallized Zircaloy-4
- Kumar, N., Alomari, A., & Murty, K. L. (2017), (Proceedings of the ASME 12th International Manufacturing Science and Engineering Conference - 2017, vol 2, ).
- alpha ->beta transformation characteristics revealed by pulsed laser-induced non-equilibrium microstructures in duplex-phase Zr alloy
- Chai, L. J., Wang, S. Y., Wu, H., Guo, N., Pan, H. C., Chen, L. Y., Murty, K. L., & Song, B. (2017), Science China-Technological Sciences, 60(8), 1255-1262.
- Fracture behavior and grain boundary sliding during high-temperature low-stress deformation of AZ31 magnesium alloy
- Roodposhti, P. S., & Murty, K. L. (2017), In Mechanical and creep behavior of advanced materials. (Minerals Metals & Materials Series, ) (pp. 279-287).
- Effect of Mo and Bi additions on the microstructure of Zr-Cr-Fe alloy after beta-quenching
- Wang, J. M., Luan, B. F., Murty, K. L., & Liu, Q. (2017), In Mechanical and creep behavior of advanced materials. (Minerals Metals & Materials Series, ) (pp. 183-192).
- Dislocation cross-slip controlled creep at high stresses and transitional creep mechanisms in zircaloy-4
- Kombaiah, B., & Murty, K. L. (2017), In Mechanical and creep behavior of advanced materials. (Minerals Metals & Materials Series, ) (pp. 65-77).
- Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite. Work Scope Identifier: RC-2.
- US Dept. of Energy (DOE)(10/01/17 - 9/30/18)
- Effect of alloying and thermo-mechanical processing on biaxial creep of low c/a-ratio hexagonal closed packed metals (Zr-alloys)
- National Science Foundation (NSF)(7/15/17 - 6/30/20)
- Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing
- US Dept. of Energy (DOE)(10/01/17 - 9/30/18)
- Tribological Damage Mechanisms from Experiments and Validated Simulations of Alloy 800H and Inconel 617 in a Simulated HTGR/VHTR Helium Environment
- US Dept. of Energy (DOE)(10/01/16 - 9/30/19)
- North Carolina State Universityâ€™s Graduate Fellowship in Nuclear Engineering (NCSUâ€“GFINE) - 2016
- US Nuclear Regulatory Commission(7/01/16 - 6/30/20)
- National Academy for Nuclear Training Fellowship Program 2015-2016
- Institute of Nuclear Power Operations (INPO)(1/01/16 - 12/31/16)
- Innovative Approach to SCC Inspection and Evaluation of Canister in Dry Storage
- US Dept. of Energy (DOE)(10/01/15 - 9/30/18)
- Mechanistic and Validated Creep/Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations
- US Dept. of Energy (DOE)(10/01/15 - 9/30/19)
- National Academy for Nuclear Training Fellowship Program 2014-2015
- National Academy for Nuclear Training(1/01/15 - 12/31/15)
- National Academy for Nuclear Training Fellowship Program 2013-2014
- National Academy for Nuclear Training(1/01/14 - 12/31/14)