Education

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

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

Experimental and theoretical investigation of crystallography and variant selection during massive transformation in Zr alloy

Wang, J. M., Luan, B. F., Xin, R. L., Xing, Q. F., Murty, K. L., Cayron, C., & Liu, Q. (2019), PHILOSOPHICAL MAGAZINE, 99(10), 1163–1183. https://doi.org/10.1080/14786435.2019.1574408

Serrated yielding in an advanced stainless steel Fe-25Ni-20Cr (wt%)

Alomari, A. S., Kumar, N., & Murty, K. L. (2019), MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 751, 292–302. https://doi.org/10.1016/j.msea.2019.02.023

Study of deformation mechanisms in a metastable beta Zr alloy during compression

Liao, Z., Luan, B., Zhang, X., Xing, Q., Liu, R., Murty, K. L., & Liu, Q. (2019), MATERIALS LETTERS, 237, 172–175. https://doi.org/10.1016/j.matlet.2018.11.043

Anisotropic grain growth kinetics in nanocrystalline nickel

Sarkar, A., & Murty, K. L. (2018), PHILOSOPHICAL MAGAZINE LETTERS, 98(11), 494–501. https://doi.org/10.1080/09500839.2019.1583391

Effect of initial orientation on dynamic recrystallization of a zirconium alloy during hot deformation

Zeng, Q., Luan, B., Wang, Y., Zhang, X., Liu, R., Murty, K. L., & Liu, Q. (2018), MATERIALS CHARACTERIZATION, 145, 444–453. https://doi.org/10.1016/j.matchar.2018.09.008

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. https://doi.org/10.1016/j.msea.2017.11.088

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. https://doi.org/10.1016/j.jallcom.2018.03.126

Understanding thermally activated plastic deformation behavior of Zircaloy-4

Kumar, N., Alomari, A., & Murty, K. L. (2018), Journal of Nuclear Materials, 504, 41–49. https://doi.org/10.1016/j.jnucmat.2018.03.031

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 (pp. 65–77). https://doi.org/10.1007/978-3-319-51097-2_6

View all publications via NC State Libraries

Grants

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 - 9/30/19)

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Mechanisms of Retention and Transport of Fission Products in Virgin and Irradiated Nuclear Graphite. Work Scope Identifier: RC-2.

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/17

End Date: 9/30/19

Abstract

We propose a joint experimental-computational approach to measure the diffusivities of fission products – Iodine (I), Cesium (Cs), Krypton (Kr), Strontium (Sr), Ruthenium (Ru) and Silver (Ag), and Europium (Eu) in four graphite grades – HOPG, NBG-18, PCEA and IG-110, and uncover the mechanisms of transport using multiscale simulations involving electronic structure, atomistic, and phase field methods. By measuring the diffusivities in both virgin and neutron/ion irradiated samples (up to 25 dpa), we will probe the importance of radiation-induced defects and pores in fission product transport and retention. Non-radioactive species will be implanted into the graphite samples for simulating realistic fission product trajectories. We will leverage on our prior NEUP work on nuclear graphite, and will use ion and neutron irradiated samples from this project (NBG/HOPG/IG-110: ion irradiated, 1 and 25 dpa, PCEA: neutron irradiated, 6.61 and 10.16 dpa; in addition, the UoM will test samples from irradiated Gen I and Gen II nuclear graphite grades, some containing fission material.

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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)

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Effect of alloying and thermo-mechanical processing on biaxial creep of low c/a-ratio hexagonal closed packed metals (Zr-alloys)

Sponsor: National Science Foundation (NSF)

Start Date: 7/15/17

End Date: 6/30/20

Abstract

The proposal addresses the influence of thermo-mechanical-treatment (TMT) and alloying on creep anisotropy of Zircaloys that are commonly used in nuclear power reactors. The study involves characterization of anisotropic biaxial creep of Zircaloy-4 and HANA4 alloys with emphasis on the effects of recrystallization and Nb addition using closed-end internally pressurized thin-walled tubing superimposed with axial load. It is proposed here to investigate these behaviors following tube-reduction (Pilger milling), stress-relief anneal and complete recrystallization. Alloying addition of Nb has been shown to exhibit better characteristics particularly for extended use in the light water reactors with some modification of crystallographic texture and the operating slip systems and underlying creep mechanisms.

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Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing

US Dept. of Energy (DOE)(10/01/17 - 9/30/19)

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Advanced Nuclear Materials Laboratory Enhancements for Corrosion and Stress Corrosion Testing

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/17

End Date: 9/30/19

Abstract

Funding is requested, through the DOE NEUP Infrastructure program, to obtain the acquisition of autoclaves and equipment for Corrosion, Stress-assisted Corrosion, and Stress Corrosion Cracking testing of nuclear materials for structural and cladding applications in LWRs, and corrosion studies related to HLW storage packages. The proposed equipment and laboratory enhancements will be used in the performance of research related to existing DOE projects and proposed efforts in the areas of advanced nuclear fuels and materials. The equipment will also be used for the purpose of a laboratory class which is being developed by the PIs for inclusion in the curriculum. The 1 credit Lab is in complement to the 3 credit Nuclear Materials Science class. It will also be of relevance for a class on Corrosion of Nuclear Materials developed by two of the co-PIs at the graduate level which will cover issues related to corrosion and stress corrosion of materials used in nuclear reactors. Henceforward, the requested infrastructure will also enable/enhance the Teaching/Learning Mission of the NE department at NCSU.

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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)

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Tribological Damage Mechanisms from Experiments and Validated Simulations of Alloy 800H and Inconel 617 in a Simulated HTGR/VHTR Helium Environment

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/16

End Date: 9/30/19

Abstract

The purpose of this proposal to develop a mechanistic understanding of accelerated fretting and wear, and bonding between Alloy 800H and Inconel 617 surfaces, we propose a series of tribological experiments in a simulated helium environment with controlled concentrations of gaseous specious, attendant microstructure characterization using electron microscopy, spectroscopy and atom-probe tomography, validated continuum models, and constitutive equations at the macroscale informed by mechanisms at the atomistic level. Our experimental data and insights derived from modeling and simulations will support ASME qualification of Alloy 800H and Inconel 617 in the new ASME Division-5 that provides construction rules for high temperature reactors and liquid metal reactors.

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North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) - 2016

US Nuclear Regulatory Commission(7/01/16 - 6/30/20)

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North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) - 2016

Sponsor: US Nuclear Regulatory Commission

Start Date: 7/01/16

End Date: 6/30/20

Abstract

This proposal is a request for financial support for 2 graduate students in nuclear engineering through the North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) program that helps to develop a highly talented and competent workforce with post-baccalaureate education capable of leading the nation’s charge to reinvigorate its nuclear industry. Every attempt will be made during the recruitment and selection processes to ensure that the sponsored students reflect the diverse groups that make up our nation’s populace. Moreover, the high academic standards inherent to NC State’s Department of Nuclear Engineering and the proposed selection formula will ensure the highest caliber of the sponsored fellows. These individuals will shepherd the design, construction, operation, and regulation of new and innovative nuclear facilities, while maintaining the safety and security of processes for the handling of requisite nuclear materials in the coming decades, a period crucial for the revamping of an industry that has fallen to neglect. Upon graduation the sponsored fellows will be contractually required to complete nuclear-related employment at the rate of six months per year of NCSU–GFINE sponsorship. The commitment by NCSU’s Department of Nuclear Engineering and College of Engineering to the success of NCSU–GFINE is evidenced by a cost-sharing contribution.

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National Academy for Nuclear Training Fellowship Program 2015-2016

Institute of Nuclear Power Operations (INPO)(1/01/16 - 12/31/16)

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National Academy for Nuclear Training Fellowship Program 2015-2016

Sponsor: Institute of Nuclear Power Operations (INPO)

Start Date: 1/01/16

End Date: 12/31/16

Abstract

This proposal is to request the continued participation of NCSU Nuclear Engineering in the National Academy for Nuclear Training Fellowship Program. The support level of one student per year at $25,000 is requested.

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Innovative Approach to SCC Inspection and Evaluation of Canister in Dry Storage

US Dept. of Energy (DOE)(10/01/15 - 9/30/19)

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Innovative Approach to SCC Inspection and Evaluation of Canister in Dry Storage

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/15

End Date: 9/30/19

Abstract

Major effort will be on SCC fracture characterization of SSs along with evaluation of KISCC and crack-growth rates in 304 and 304L stainless steel welds in marine environments. The appropriate materials with welds/HAZs will be provided by CSM and subsize WOL specimens will be fabricated from these steel samples. This is the subsize modified Manjoine fracture test specimen with 20% side-groove for straight growth of the crack as per ASTM standards. Main reason for selecting WOL type specimens is that a value of KISCC can be determined from a single specimen at the arrest condition thereby avoiding dependence on the initial loading level. The WOL specimens will be fatigue precracked at different loads to different precrack lengths. Sufficiently large load will be applied so that K value larger than KISCC is applied using a bolt under constant load-line displacement. The crack is allowed to grow until arrest which takes place since K decreases with increasing crack length. Crack lengths will be monitored by DC potential drop method that allows continuous monitoring of the crack growth. An online data acquisition system will be used along with specially developed software for continuous recording of data including time variations of load (using internally strain-gauged bolts), DC drop and crack-length as well as K.

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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)

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Mechanistic and Validated Creep/Fatigue Predictions for Alloy 709 from Accelerated Experiments and Simulations

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/15

End Date: 9/30/19

Abstract

As a promising candidate for fast reactor program, Alloy 709 possesses excellent high temperature thermo-mechanical properties. To support its qualification in the ASME code for Class 1 Components in Elevated Temperature Service (Section 3, Division 1, Subsection NH), we propose mechanistic methods for predicting creep and creep-fatigue deformation rates/strains based on accelerated in-situ and ex-situ tests, and mesoscale dislocation dynamics simulations. There are four research tasks in the proposed program. In Task 1, ex-situ creep and creep-fatigue experiments will be conducted by PD/PI (Murty, NCSU) at high temperatures and stresses followed by microstructure evaluations using high resolution transmission electron microscopy (HR-TEM), and Atom Probe Tomography (APT). To evaluate the time evolution of the microstructure, in Task 2, in-situ X-ray synchrotron (XRD) experiments will be conducted by PI-3 (Almer, ANL) and PI-2 (Kaoumi, USC) at the Advanced Photon Source (APS), along with in-situ TEM experiments by PI-2. Using the microstructure information from Tasks 1 and 2, mesoscale dislocation dynamics (DD) will be conducted by PI-4 (Eapen, NCSU) in Task 3 to follow the microstructure evolution at accelerated and reactor operating conditions. In Task 4, realistic continuum creep damage mechanics (CDM), informed by in-situ experiments and simulations on microstructure evolution, will be employed to predict the accumulated strains during creep and creep-fatigue at reactor operating conditions.

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National Academy for Nuclear Training Fellowship Program 2014-2015

National Academy for Nuclear Training(1/01/15 - 12/31/15)

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National Academy for Nuclear Training Fellowship Program 2014-2015

Sponsor: National Academy for Nuclear Training

Start Date: 1/01/15

End Date: 12/31/15

Abstract

This proposal is to request the continued participation of NCSU Nuclear Engineering in the National Academy for Nuclear Training Fellowship Program. The support level of one student per year at $25,000 is requested.

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National Academy for Nuclear Training Fellowship Program 2013-2014

National Academy for Nuclear Training(1/01/14 - 12/31/14)

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National Academy for Nuclear Training Fellowship Program 2013-2014

Sponsor: National Academy for Nuclear Training

Start Date: 1/01/14

End Date: 12/31/14

Abstract

This proposal is to request the continued participation of NCSU Nuclear Engineering in the National Academy for Nuclear Training Fellowship Program. The support level of one student per year at $25,000 is requested.

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