Korukonda Murty
Progress Energy Distinguished Professor of Nuclear Engineering

- 919-515-3657
- murty@eos.ncsu.edu
- 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.
Education
Materials Science
Cornell University
Materials Science
Cornell University
Physics
Andhra University
Physics
Andhra University
Research Description
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.
Publications
- A multi-deformation mechanisms assisted metastable beta-ZrTiAlV alloy exhibits high yield strength and high work hardening rate
- Liao, Z., Luan, B., Zhang, X., Liu, R., Murty, K. L., & Liu, Q. (2020), JOURNAL OF ALLOYS AND COMPOUNDS, 816. https://doi.org/10.1016/j.jallcom.2019.152642
- Accelerated crack growth experiments of SS304H for dry storage canister in substitute ocean water - Effect of temperature
- Tjayadi, L., Kumar, N., & Murty, K. L. (2020), MATERIALS TODAY COMMUNICATIONS, 23. https://doi.org/10.1016/j.mtcomm.2020.100929
- Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing
- Joshi, P., Kombaiah, B., Cinbiz, M. N., & Murty, K. L. (2020), MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 791. https://doi.org/10.1016/j.msea.2020.139753
- Correlation of microstructural, textural characteristics and hardness of Ti-6Al-4V sheet beta-cooled at different rates
- Dai, J., Xia, J., Chai, L., Murty, K. L., Guo, N., & Daymond, M. R. (2020), JOURNAL OF MATERIALS SCIENCE. https://doi.org/10.1007/s10853-020-04603-9
- Effect of hold time on high temperature creep-fatigue behavior of Fe-25Ni-20Cr (wt.%) austenitic stainless steel (Alloy 709)
- Alsmadi, Z. Y., Alomari, A., Kumar, N., & Murty, K. L. (2020), MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 771. https://doi.org/10.1016/j.msea.2019.138591
- Effect of varying a phase fraction on the mechanical properties and deformation mechanisms in a metastable beta-ZrTiAlV alloy
- Liao, Z., Luan, B., Zhang, X., Liu, R., Murty, K. L., & Liu, Q. (2020), MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 772. https://doi.org/10.1016/j.msea.2019.138784
- Microstructural characteristics and hardness of CoNiTi medium-entropy alloy coating on pure Ti substrate prepared by pulsed laser cladding
- Xiang, K., Chai, L., Wang, Y., Wang, H., Guo, N., Ma, Y., & Murty, K. L. (2020), JOURNAL OF ALLOYS AND COMPOUNDS, 849. https://doi.org/10.1016/j.jallcom.2020.156704
- Twinning behaviors and grain refinement mechanisms during friction stir processing of Zr alloy
- Li, S., Luan, B., Chu, L., Zhang, X., Yuan, G., Liu, R., … Liu, Q. (2020), MATERIALS CHARACTERIZATION, 163. https://doi.org/10.1016/j.matchar.2020.110277
- Biaxial Creep Behavior of Nb-Modified Zircaloys
- Joshi, P., Tillman, M., Kumar, N., Murty, K., & Cinbiz, N. (2019), NUCLEAR TECHNOLOGY. https://doi.org/10.1080/00295450.2019.1674581
- Creep Behavior and Microstructural Evolution of a Fe-20Cr-25Ni (Mass Percent) Austenitic Stainless Steel (Alloy 709) at Elevated Temperatures
- Alomari, A. S., Kumar, N., & Murty, K. L. (2019), METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 50A(2), 641–654. https://doi.org/10.1007/s11661-018-5044-y
Grants
- Development of an In-Situ Testing Laboratory for Research and Education of Very High Temperature Reactor Materials
- US Dept. of Energy (DOE)(10/01/20 - 9/30/21)
- Novel Miniature Creep Tester for Virgin and Neutron Irradiated Clad Alloys with Benchmarked Multiscale Modeling and Simulations
- US Dept. of Energy (DOE)(10/01/19 - 9/30/22)
- North Carolina State University's Graduate Fellowship In Nuclear Engineering (NCSU-GFINE)– 2018
- US Nuclear Regulatory Commission(8/30/19 - 8/29/23)
- 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 - 9/30/21)
- 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 - 6/30/21)
- Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing
- US Dept. of Energy (DOE)(10/01/17 - 9/30/19)
- 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 - 9/30/20)
- North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–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 - 9/30/19)