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

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).

Microstructural, textural and hardness evolution of commercially pure Zr surface-treated by high current pulsed electron beam

Chai, L. J., Chen, B. F., Wang, S. Y., Zhang, Z., & Murty, K. L. (2016), Applied Surface Science, 390, 430-434.

Effects of microstructure and processing methods on creep behavior of AZ91 magnesium alloy

Roodposhti, P. S., Sarkar, A., Murty, K. L., & Scattergood, R. O. (2016), Journal of Materials Engineering and Performance, 25(9), 3697-3709.

Grain boundary sliding mechanism during high temperature deformation of AZ31 Magnesium alloy

Roodposhti, P. S., Sarkar, A., Murty, K. L., Brody, H., & Scattergood, R. (2016), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 669, 171-177.

The role of grain size on neutron irradiation response of nanocrystalline copper

Mohamed, W., Miller, B., Porter, D., & Murty, K. (2016), Materials, 9(3).

Modeling irradiation creep of graphite using rate theory

Sarkar, A., Eapen, J., Raj, A., Murty, K. L., & Burchell, T. D. (2016), Journal of Nuclear Materials, 473, 197-205.

Microstructural and textural evolution of commercially pure Zr sheet rolled at room and liquid nitrogen temperatures

Chai, L. J., Luan, B. F., Xiao, D. P., Zhang, M., Murty, K. L., & Liu, Q. (2015), Materials & Design, 85, 296-308.

View all publications via NC State Libraries

Grants

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 - 9/30/16)

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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: 9/30/16

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 - 9/30/18)

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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: 9/30/18

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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Study on High Temperature Creep Behavior of Zirconium Alloys

Korea Atomic Energy Research Institute (KAERI)(9/01/13 - 8/31/15)

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Study on High Temperature Creep Behavior of Zirconium Alloys

Sponsor: Korea Atomic Energy Research Institute (KAERI)

Start Date: 9/01/13

End Date: 8/31/15

Abstract

The work proposed here involves a review on creep of Zirconium alloys using literature data and information from KAERI and will be performed by Dr. Murty as part of the Nuclear Materials Characterization & Analyses Trust Account at NC State University, Raleigh, NC. Dr. Murty's scope of work will involve the following activities: - Provide general advice on creep test method and know-how to perform the creep test of zirconium-based alloys up to high temperature. - Provide specific advice to KAERI on the creep mechanism of zirconium-based alloys with the alloy composition, texture, microstructure, and irradiation effect. - Provide specifications for establishing a tube type testing technique for the zirconium cladding tubes. - Write progress reports to KAERI summarizing experimental results obtained. - Collaborate with KAERI researchers in preparing and submitting journal articles for publication on research results. - Collaborate with KAERI researchers in identifying and soliciting additional funding for this research

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MRI: Development of a Miniature, High Temperature, Multiaxial Testing System for Advanced Materials and Engineering Research

National Science Foundation (NSF)(8/15/13 - 7/31/17)

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MRI: Development of a Miniature, High Temperature, Multiaxial Testing System for Advanced Materials and Engineering Research

Sponsor: National Science Foundation (NSF)

Start Date: 8/15/13

End Date: 7/31/17

Abstract

A novel testing system will be designed and developed for mechanical testing of miniature tubular specimens under any combination of axial, torsional, and internal pressure monotonic and cyclic loading in the room to 1000oC temperature. The proposed test system size and orientation will be designed such that it can be set under an optical microscope (OM) and scanning electron microscope (SEM) for in-situ microstructural studies. With the emerging research in materials genome and integrated computational materials engineering, importance and significance in performing materials testing under realistic multiaxial loading and environmental (temperature, chemical and gas) conditions are in urgent need. For enhancing resilience of manufactured components, design of new materials should consider failure mechanisms at critical points (weld toe, stress concentration and hot spot) through testing miniature specimen under multiaxial loading. Such tests need to be performed at high temperatures for understanding premature failures of components in energy and aerospace industries. Manufacturing processes, welding, cold drawing, quenching, surface finishing etc. induce localized material heterogeneity whose influence on failure mechanism can only be studied through testing miniature coupons. Extreme service loading and environmental conditions alter local material properties, which can only be studied through miniature specimens in determining remaining life of critical components. Development of micro-fabrication techniques requires material properties and their evolutions which can only be determined accurately through miniature specimen testing under realistic loading. According to the investigators? knowledge, the proposed testing system currently is not commercially available anywhere in the world. Moreover, even a standard size axial-torsion mechanical testing machine with or without high temperature capability is not available at any universities in North Carolina or its neighboring states. The proposed miniature testing system will be shared by a large group of inter and intra university researchers in performing fundamental research on advanced material design and characterization, micro-forming, constitutive modeling, computational modeling, and failure-life prediction for the energy, aerospace, automobile, electronics, communication, biomedical, sensor and infrastructure industries. The proposed testing system will create research opportunities in material design and component manufacturing, integrated through constitutive and computational modeling research, as well as, meeting the research needs of material characterization usually obtained through standard testing systems. Development of the proposed testing system will performed by detailed thermo-mechanical analysis. Technologies of actuators, sensors, heating and pressurization, digital image correlation, water cooled grips and their controls will be critically evaluated in developing and integrating technologies needed for developing the proposed material testing system. Cooperation with the U.S. commercial partners will facilitate this process. The proposed system will impact design and development of new materials, high performance components, and micro-forming processes. Other important outcomes will be eliminating the long (10-20 years) trial & error methods of designing new materials for enhancing component life, and predicting failure life of components with much less uncertainty than today. Two Graduate and one undergraduate student will be trained on the novel testing system through designing and developing the proposed testing system. Many other students will be trained for use of the testing system in performing their research towards MS and PhD degrees. Undergraduate students through their research projects and K-12 teachers through The Engineering Place and Women in Engineering will perform experiments with the proposed system. Partnership with an US commercial testing system manufacturer will allow quick commercialization of the new system to other r

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North Carolina State University's Graduate Fellowship In Nuclear Engineering (NCSU-GFINE)

US Nuclear Regulatory Commission(8/01/13 - 7/31/17)

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North Carolina State University's Graduate Fellowship In Nuclear Engineering (NCSU-GFINE)

Sponsor: US Nuclear Regulatory Commission

Start Date: 8/01/13

End Date: 7/31/17

Abstract

We propose to create and administer a financial aid mechanism for graduate students in nuclear engineering to be named the North Carolina State University?s Graduate Fellowship In Nuclear Engineering (NCSU?GFINE). The primary objective of NCSU?GFINE is to enhance the ability of NCSU?s Department of Nuclear Engineering to recruit and retain outstanding individuals and to provide incentive to the sponsored graduate students to maintain high academic performance. In addition, the selection formula will slightly favor minorities, women, and persons with disabilities in order to further promote diversity in the department?s graduate student population. Ultimately, the collective effort by US educational institutions to raise the admission standards and to diversify their graduate student populations, as proposed here for NCSU, will translate into a highly competent and diverse cadre of leaders for the nuclear engineering endeavor at large. The benefit to the nation from NCSU?GFINE is that it will contribute to the production of a highly competitive group of advanced-degree nuclear engineers capable of assuming leadership positions in their area of specialization within the field of nuclear engineering. The diverse profile of NCSU?GFINE fellows will be reflective of the US?s population and supportive of the nation?s goals of achieving social justice and economic equity for underprivileged groups. The so-developed workforce will be best positioned to lead the nation?s charge to reinvigorate its nuclear industry, and 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. 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. The support of industry for the Department and its mission, and their interest in NCSU?GFINE is evidenced by their contribution to the cost-sharing arrangement.

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Aging of Used Nuclear Fuel in Storage: Accelerated Characterization and Modeling of Performance

US Dept. of Energy (DOE)(12/15/11 - 12/15/15)

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Aging of Used Nuclear Fuel in Storage: Accelerated Characterization and Modeling of Performance

Sponsor: US Dept. of Energy (DOE)

Start Date: 12/15/11

End Date: 12/15/15

Abstract

This is a subcontract to TAMU (Dr. Sean McDevitt) with NCSU PIs to work on creep of spent fuel as a part of the proposal on aging of used nuclear fuel in storage being submitted to DOE/NEUP under solicitation: CALL FOR PROPOSALS (CFP) NO. NEUP-002-11 under Integrated Research Projects.

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