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

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.

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.

Understanding thermally activated plastic deformation behavior of Zircaloy-4

Kumar, N., Alomari, A., & Murty, K. L. (2018), Journal of Nuclear Materials, 504, 41–49.

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).

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 (pp. 183–192).

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., … Liu, Q. (2017), Journal of Nuclear Science and Technology, 54(12), 1321–1329.

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 (pp. 279–287).

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),

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., … Song, B. (2017), Science China-Technological Sciences, 60(8), 1255–1262.

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.

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.

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.

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

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

Coble, Orowan strengthening, and dislocation climb mechanisms in a Nb-Modified Zircaloy cladding

Kombaiah, B., & Murty, K. L. (2015), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 46A(10), 4646–4660.

Dislocation cross-slip controlled creep in Zircaloy-4 at high stresses

Kombaiah, B., & Murty, K. L. (2015), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 623, 114–123.

High temperature creep and deformation microstructures in recrystallized Zircaloy-4

Kombaiah, B., & Murty, K. L. (2015), Philosophical Magazine, 95(15), 1656–1679.

Investigation of portevin - Le Chatelier effect in HT-9 steel

Sarkar, A., Maloy, S. A., & Murty, K. L. (2015), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 631, 120–125.

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.

Microstructural approach to equal channel angular processing of commercially pure titanium-A review

Roodposhti, P. S., Sarkar, N. F. A., & Murty, K. L. (2015), Transactions of Nonferrous Metals Society of China, 25(5), 1353–1366.

Microstructural development of high temperature deformed AZ31 magnesium alloys

Roodposhti, P. S., Sarkar, A., & Murty, K. L. (2015), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 626, 195–202.

Microstructure-mechanical property correlation of cryo rolled Zircaloy-4

Sarkar, A., & Murty, K. L. (2015), Journal of Nuclear Materials, 456, 287–291.

A special twin relationship or a common Burgers misorientation between alpha plates after beta quenching in Zr alloy?

Chai, L. J., Chen, B. F., Zhou, Z. M., Murty, K. L., Ma, Y. L., & Huang, W. J. (2015), Materials Characterization, 104, 61–65.

Characterization of hot deformation behavior of Zr-1.0Sn-0.3Nb-0.3Fe-0.1Cr using processing map

Luan, B. F., Qiu, R. S., Zhou, Z., Murty, K. L., Zhou, J., & Liu, Q. (2014),

Creep behavior of hydrogenated zirconium alloys

Sarkar, A., Boopathy, K., Eapen, J., & Murty, K. L. (2014), Journal of Materials Engineering and Performance, 23(10), 3649–3656.

Creep deformation behavior of Sn-Zn solder alloys

Shrestha, T., Gollapudi, S., Charit, I., & Murty, K. L. (2014), Journal of Materials Science, 49(5), 2127–2135.

Effect of Mo and Bi on mechanical properties of Zr-Fe-Cr alloy at room ternperature

Luan, B. F., Yang, L. Q., Wei, T. G., Murty, K. L., Long, C. S., & Liu, Q. (2014),

Effect of low dose neutron irradiation on tensile behavior of ht-9 steel at room temperature

Sarkar, A., Alsabbagh, A. H., & Murty, K. L. (2014), (pp. 147–154).

Investigation of microstructure and mechanical properties of low dose neutron irradiated HT-9 steel

Sarkar, A., Alsabbagh, A., & Murty, K. L. (2014), Annals of Nuclear Energy, 65, 91–96.

Loading rate-dependent mechanical properties of bulk two-phase nanocrystalline Al-Pb alloys studied by nanoindentation

Varam, S., Rajulapati, K. V., Rao, K. B. S., Scattergood, R. O., Murty, K. L., & Koch, C. C. (2014), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 45A(11), 5249–5258.

Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel

Alsabbagh, A., Sarkar, A., Miller, B., Burns, J., Squires, L., Porter, D., … Murty, K. L. (2014), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 615, 128–138.

Burst and biaxial creep of thin-walled tubing of low c/a-Ratio HCP Metals

Murty, K. L., Seok, C. S., & Kombaiah, B. (2013), In 6th international conference on creep, fatigue and creep-fatigue interaction (Vol. 55, pp. 443–450).

Effect of predeformation on microstructural evolution of a Zr alloy during 550-700 degrees C aging after beta quenching

Chai, L. J., Luan, B. F., Murty, K. L., & Liu, Q. (2013), Acta Materialia, 61(8), 3099–3109.

Experimental observation of 12 alpha variants inherited from one beta grain in a Zr alloy

Chai, L. J., Luan, B. F., Zhang, M., Murty, K. L., & Liu, Q. (2013), Journal of Nuclear Materials, 440(1-3), 377–381.

Influence of grain size on radiation effects in a low carbon steel

Alsabbagh, A., Valiev, R. Z., & Murty, K. L. (2013), Journal of Nuclear Materials, 443(1-3), 302–310.

Twinning during recrystallization cooling in alpha-Zr alloy

Chai, L. J., Luan, B. F., Murty, K. L., & Liu, Q. (2013), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 576, 320–325.

High temperature deformation characteristics of Zirlo (TM) tubing via ring-creep and burst tests

Seok, C. S., Marple, B., Song, Y. J., Gollapudi, S., Charit, I., & Murty, K. L. (2011), (Vol. 241, pp. 599–602).

Temperature dependence of the dynamics of Portevin-Le Chatelier effect in Al-2.5 Pct Mg alloy

Chatterjee, A., Murty, K. L., Gayathri, N., Mukherjee, P., & Barat, P. (2011), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 42A(5), 1184–1190.

Creep behavior of ultra-fine grained Zn-4.5Al

Gobien, J. M., Murty, K. L., Scattergood, R. O., Goodwin, F., & Koch, C. C. (2010), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 527(27-28), 7382–7386.

Creep in nanocrystalline materials: Role of stress assisted grain growth

Gollapudi, S., Rajulapati, K. V., Charit, I., Koch, C. C., Scattergood, R. O., & Murty, K. L. (2010), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 527(21-22), 5773–5781.

Irradiation induced creep of graphite

Burchell, T. D., Murty, K. L., & Eapen, J. (2010), JOM: the Journal of the Minerals, Metals & Materials Society, 62(9), 93–99.

Low stress viscous creep in a ti-3al-2.5v tubing under internal pressurization

Gollapudi, S., Bhosle, V., Charit, I., & Murty, K. L. (2010), (pp. 755–762).

Materials for next-generation nuclear plants: Objectives and challenges

Murty, K. L. (2010), JOM: the Journal of the Minerals, Metals & Materials Society, 62(9), 60–61.

Newtonian viscous creep in metals

Murty, K. L., Gollapudi, S., & Charit, I. (2010), Transactions of the Indian Institute of Metals, 63(2-3), 85–91.

Understanding creep in nanocrystalline materials

Gollapudi, S., Rajulapati, K. V., Charit, I., Youssef, K. M., Koch, C. C., Scattergood, R. O., & Murty, K. L. (2010), Transactions of the Indian Institute of Metals, 63(2-3), 373–378.

structural materials issues for the next generation fission reactors

Charit, I., & Murty, K. L. (2010), JOM: the Journal of the Minerals, Metals & Materials Society, 62(9), 67–74.

Creep behavior of niobium-modified zirconium alloys

Charit, I., & Murty, K. L. (2008), Journal of Nuclear Materials, 374(3), 354–363. https://doi.org/10.1016/j.jnucmat.2007.08.019

Creep mechanisms in TI-3Al-2.5V alloy tubing deformed under closed-end internal gas pressurization

Gollapudi, S., Charit, I., & Murty, K. L. (2008), Acta Materialia, 56(10), 2406–2419. https://doi.org/10.1016/j.actamat.2008.01.052

Mechanical properties of bulk nanocrystalline aluminum-tungsten alloys

Rajulapati, K. V., Scattergood, R. O., Murty, K. L., Horita, Z., Langdon, T. G., & Koch, C. C. (2008), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 39A(10), 2528–2534. https://doi.org/10.1007/s11661-008-9593-3

Newtonian viscous creep in Ti-3Al-2.5V

Gollapudi, S., Bhosle, V., Charit, I., & Murty, K. L. (2008), Philosophical Magazine, 88(9), 1357–1367. https://doi.org/10.1080/14786430802144154

Static strain aging and dislocation-impurity interactions in irradiated mild steel

Murty, K. L., & Charit, I. (2008), (Vol. 382, pp. 217–222).

Strengthening mechanisms in nanocrystalline alloys

Scattergood, R. O., Koch, C. C., Murty, K. L., & Brenner, D. (2008), (Vol. 493, pp. 3–11).

Structural materials for Gen-IV nuclear reactors: Challenges and opportunities

Murty, K. L., & Charit, I. (2008), (Vol. 383, pp. 189–195).

Characterization of stress rupture behavior of cornmercial-purity-Ti via burst testing

Srikant, G., Marple, B., Charit, I., & Murty, K. L. (2007), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 463(1-2), 203–207.

Determination of activation volume in nanocrystalline Cu using the shear punch test

Guduru, R. K., Wong, P. Z., Darling, K. A., Koch, C. C., Murty, K. L., & Scattergood, R. O. (2007), Advanced Engineering Materials, 9(10), 855–859. https://doi.org/10.1002/adem.200700181

Mechanical properties of electrodeposited nanocrystalline copper using tensile and shear punch tests

Guduru, R. K., Darling, K. A., Scattergood, R. O., Koch, C. C., & Murty, K. L. (2007), Journal of Materials Science, 42(14), 5581–5588. https://doi.org/10.1007/s10853-006-1095-3

Proceedings of the Symposium on Radiation Effects, Deformation and Phase Transformations in Metals and Ceramics, Organized in Honor of Prof. Monroe S. Wechsler - TMS Annual Meeting, San Antonio, Texas, USA 12-16 March 2006 - Preface

Murty, K. L., Mansur, L. K., Simonen, E. P., & Bajaj, R. (2007), Journal of Nuclear Materials, 361(2-3), VII–.

Synergistic effects of interstitial impurities and radiation defects on mechanical characteristics of ferritic steels

Charit, I., Seok, C. S., & Murty, K. L. (2007), Journal of Nuclear Materials, 361(2-3), 262–273. https://doi.org/10.1016/j.jnucmat.2006.12.003

Thickness and clearance effects in shear punch testing

Guduru, R. K., Nagasekhar, A. V., Scattergood, R. O., Koch, C. C., & Murty, K. L. (2007), Advanced Engineering Materials, 9(3), 157–160. https://doi.org/10.1002/adem.200600255

The mechanical behavior of multiphase nanocrystalline materials

Koch, C. C., Scattergood, R. O., & Murty, K. L. (2007), JOM: the Journal of the Minerals, Metals & Materials Society, 59(3), 66–70.

Effect of Pb on the mechanical properties of nanocrystalline Al

Rajulapati, K. V., Scattergood, R. O., Murty, K. L., Duscher, G., & Koch, C. C. (2006), Scripta Materialia, 55(2), 155–158. https://doi.org/10.1016/j.scriptamat.2006.03.051

Finite element analysis of a shear punch test

Guduru, R. K., Nagasekhar, A. V., Scattergood, R. O., Koch, C. C., & Murty, K. L. (2006), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 37A(5), 1477–1483. https://doi.org/10.1007/s11661-006-0092-0

Mechanical properties of nanocrystalline Fe-Pb and Fe-Al2O3

Guduru, R. K., Scattergood, R. O., Koch, C. C., Murty, K. L., Guruswamy, S., & McCarter, M. K. (2006), Scripta Materialia, 54(11), 1879–1883. https://doi.org/10.1016/j.scriptamat.2006.02.014

Nanocrystalline Al-Mg alloy with ultrahigh strength and good ductility

Youssef, K. M., Scattergood, R. O., Murty, K. L., & Koch, C. C. (2006), Scripta Materialia, 54(2), 251–256. https://doi.org/10.1016/j.scriptamat.2005.09.028

Shear punch tests for a bulk metallic glass

Guduru, R. K., Darling, K. A., Scattergood, R. O., Koch, C. C., Murty, K. L., Bakkal, M., & Shih, A. J. (2006), Intermetallics, 14(12), 1411–1416. https://doi.org/10.1016/j.intermet.2006.01.052

Texture development and anisotropic deformation of zircaloys

Murty, K. L., & Charit, I. (2006), Progress in Nuclear Energy, 48(4), 325–359. https://doi.org/10.1016/j.pnucene.2005.09.011

The properties of the ring and burst creep of ZIRLO cladding

Seok, C. S., Bae, B. K., Koo, J. M., & Murty, K. L. (2006), Engineering Failure Analysis, 13(3), 389–397. https://doi.org/10.1016/j.engfailanal.2005.02.009

Ball indentation tests for a Zr-based bulk metallic glass

Trichy, G. R., Scattergood, R. O., Koch, C. C., & Murty, K. L. (2005), Scripta Materialia, 53(12), 1461–1465. https://doi.org/10.1016/j.scriptamat.2005.08.010

Breakthroughs in optimization of mechanical properties of nanostructured metals and alloys

Koch, C. C., Youssef, K. M., Scattergood, R. O., & Murty, K. L. (2005), Advanced Engineering Materials, 7(9), 787–794. https://doi.org/10.1002/adern.200500094

Effect of annealing temperature on texture and creep anisotropy in Ti3Al2.5V alloy

Murty, K. L., Kishore, R., Yan, J., Scattergood, R. O., & Helsel, A. W. (2005), In Textures of materials: ICOTOM 14: Proceedings of the 14th International Conference on Textures of Materials, held in Leuven, Belgium, July 11-15, 2005 / Paul van Houtte; Leo Kestens. Uetikon-Zuerich, Switzerland ; Enfield, NH: Trans Tech Publications, 2005. (Materials science forum ; 495-497) (Vol. 495-497, pp. 1645–1650). Utikon-Zurich, Switzerland: Trans Tech Publications.

Effect of temperature on transitions in creep mechanisms in class-A alloys

Murty, K. L., Dentel, G., & Britt, J. (2005), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 410, 28–31.

Ultrahigh strength and high ductility of bulk nanocrystalline copper

Youssef, K. M., Scattergood, R. O., Murty, K. L., Horton, J. A., & Koch, C. C. (2005), Applied Physics Letters, 87(9).

Nondestructive monitoring of structural materials using automated ball indentation (ABI) technique

Murty, K. L., & Mathew, M. D. (2004), Nuclear Engineering and Design, 228(03-Jan), 81–96. https://doi.org/10.1016/j.nucengdes.2003.06.006

Short-term rupture studies of Zircaloy-4 and Nb-modified Zircaloy-4 tubing using closed-end internal pressurization

Zhou, Y., Devarajan, B., & Murty, K. L. (2004), Nuclear Engineering and Design, 228(03-Jan), 13–.

Ultratough nanocrystalline copper with a narrow grain size distribution

Youssef, K. M., Scattergood, R. O., Murty, K. L., & Koch, C. C. (2004), Applied Physics Letters, 85(6), 929–931. https://doi.org/10.1063/1.1779342

Plastic instability and mechanical anisotropy of textured zinc

Rao, G. S. S., Godavarti, P. S., Mahmood, S. T., & Murty, K. L. (2002), Journal of Testing and Evaluation, 30(3), 197–207.

Fracture in ferritic reactor steel - Dynamic strain aging and cyclic loading

Murty, K. L., & Seok, C. C. (2001), JOM: the Journal of the Minerals, Metals & Materials Society, 53(7), 23–26.

LWR pellet-cladding interactions: Materials solutions to SCC

Edsinger, K., & Murty, K. L. (2001), JOM: the Journal of the Minerals, Metals & Materials Society, 53(7), 9–13.

Materials issues in light water reactors

Murty, K. L. (2001), JOM: the Journal of the Minerals, Metals & Materials Society, 53(7), 88.

Deformation mechanisms and transients in creep of zircaloys: Applications to nuclear technology

Murty, K. L. (2000), Transactions of the Indian Institute of Metals, 53(3), 107–120.

High temperature deformation characteristics of tin-based solder alloys: Application to electronic packaging

Mathew, M. D., Yang, H., Movva, S., & Murty, K. L. (2000), Transactions of the Indian Institute of Metals, 53(3), 369–379.

Materials issues in nuclear-waste management

Yim, M. S., & Murty, K. L. (2000), JOM: the Journal of the Minerals, Metals & Materials Society, 52(9), 26–29.

The internal pressurization creep of Zr alloys for spent-fuel dry storage feasibility

Murty, K. L. (2000), JOM: the Journal of the Minerals, Metals & Materials Society, 52(9), 34–38.

Ball indentation studies on the effect of aging on mechanical behavior of alloy 625

Mathew, M. D., Murty, K. L., Rao, K. B. S., & Mannan, S. L. (1999), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 264(1-2), 159–166.

Characterization of gradients in mechanical properties of SA- 533B steel welds using ball indentation

Murty, K. L., Miraglia, P. Q., Mathew, M. D., Shah, V. N., & Haggag, F. M. (1999), International Journal of Pressure Vessels and Piping, 76(6), 361–369. https://doi.org/10.1016/S0308-0161(99)00006-X

Creep studies for Zircaloy life prediction in water reactors

Murty, K. L. (1999), JOM: the Journal of the Minerals, Metals & Materials Society, 51(10), 32–39.

Effect of dynamic strain aging on mechanical and fracture properties of A516Gr70 steel

Seok, C. S., & Murty, K. L. (1999), International Journal of Pressure Vessels and Piping, 76(14-15), 945–953. https://doi.org/10.1016/S0308-0161(99)00075-7

Low temperature aging embrittlement of CF-8 stainless steel

Mathew, M. D., Lietzan, L. M., Murty, K. L., & Shah, V. N. (1999), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 269(1-2), 186–196.

Non-destructive studies on tensile and fracture properties of molybdenum at low temperatures (148 to 423 K)

Mathew, M. D., & Murty, K. L. (1999), Journal of Materials Science, 34(7), 1497–1503. https://doi.org/10.1023/A:1004547709783

Role and significance of source hardening in radiation embrittlement of iron and ferritic steels

Murty, K. L. (1999), Journal of Nuclear Materials, 270(1-2), 115–128. https://doi.org/10.1016/S0022-3115(98)00766-1

Compressive mechanical behavior of nanocrystalline Fe investigated with an automated ball indentation technique

Malow, T. R., Koch, C. C., Miraglia, P. Q., & Murty, K. L. (1998), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 252(1), 36–43.

Effect of temperature on mechanical anisotroof Zircaloy-4 sheet

Wang, Y., & Murty, K. L. (1998), Metals and Materials (Seoul, Korea), 4(4), 723–726.

In-situ nuclear magnetic resonance investigation of strain, temperature, and strain-rate variations of deformation-induced vacancy concentration in aluminum

Murty, K. L., DeTemple, K., Kanert, O., & Dehosson, J. T. M. (1998), Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, 29(1), 153–159. https://doi.org/10.1007/s11661-998-0168-0

Indentation-Energy-to-Fracture (IEF) parameter for characterization of DBTT in carbon steels using nondestructive Automated Ball Indentation (ABI) technique

Haggag, F. M., Byun, T. S., Hong, J. H., Miraglia, P. Q., & Murty, K. L. (1998), Scripta Materialia, 38(4), 645–651.

Nondestructive determination of tensile properties and fracture toughness of cold worked A36 steel

Murty, K. L., Mathew, M. D., Wang, Y., Shah, V. N., & Haggag, F. M. (1998), International Journal of Pressure Vessels and Piping, 75(11), 831–840. https://doi.org/10.1016/S0308-0161(98)00093-3

Special issue on interfacial reactions, solid state transformations and thermal management - Foreword

Ghosh, G., Kang, S., Murty, K. L., & Notis, M. (1998), Journal of Electronic Materials, 27(11), 1137. https://doi.org/10.1007/s11664-998-0061-z

An investigation of the deformation mechanisms in Sn5%Sb alloy using tensile, creep and ABI tests from ambient to 473K

Murty, K. L., Mathew, M. D., & Haggag, F. M. (1998), Metals and Materials (Seoul, Korea), 4(4), 799–802.

Tensile, creep, and ABI tests on Sn5 percent Sb solder for mechanical property evaluation

Murty, K. L., Haggag, F. M., & Mahidhara, R. K. (1997), Journal of Electronic Materials, 26(7), 839–846. https://doi.org/10.1007/s11664-997-0260-z

Zircaloy life prediction and new generation zircaloys for LWRs

Murty, K. L. (1997), Transactions of the Indian Institute of Metals, 50(6), 533–562.

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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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