Photo of ARTHUR MOTTA

Arthur Motta

Professor And Chair Of Nuclear Engineering

Department(s):

  • Mechanical and Nuclear Engineering
  • Nuclear Engineering

138 Reber Building

atm2@psu.edu

814-865-0036

Personal or Departmental Website

Research Areas:

Nuclear Power

Interest Areas:

Mechanisms of materials degradation when exposed to the nuclear reactor environment, including radiation damage, microstructural evolution, corrosion and hydriding for better prediction of materials behavior and development of new materials.

 
 

 

Education

  • BS, Mechanical Engineering, Federal University of Rio de Janeiro, 1980
  • MS, Nuclear Engineering, Federal University of Rio de Janeiro, 1983
  • Ph D, Nuclear Engineering, University of California, Berkeley, 1988

Publications

Book

  • Kevin Crowley, Joseph E Shepherd and Arthur T Motta, 2016, Lessons Learned from The Fukushima Nuclear Accident for Improving Safety and Security of U.S. Nuclear Plants: Phase 2

Book, Chapter

  • T. R. Allen, R. J. M. Konings and Arthur T Motta, 2012, Corrosion of zirconium alloys, Elsevier, pp. 49-68

Conference Proceeding

  • Evrard Lacroix and Arthur T Motta, 2016, "Validation of BISON Calculation of Hydrogen Distribution by Comparison to Experiment", pp. 10
  • Brendan M Ensor, Arthur T Motta, John Seidensticker, Ram Bajaj and Zhonghou Cai, 2015, "XANES analysis of iron in Zircaloy-4 oxides formed at different temperatures studied with microbeam synchrotron radiation", ANS LWR Fuel Performance Meeting, TopFuel 2015, paper A0191
  • Christopher Dances, Christopher Piotroski, Michael Mankosa, Kostadin Ivanov, Maria Avramova and Arthur Motta, 2014, "Anisotropic azimuthal power and temperature distribution impact on hydride distribution", Transactions of the American Nuclear Society, 111, pp. 122-125
  • A. Couet, Arthur T Motta, R. J. Comstock and A. Ambard, 2014, "Oxide electronic conductivity and hydrogen pickup fraction in Zr alloys", 2014 Annual Meeting on Transactions of the American Nuclear Society and Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors, NSFM 2014, pp. 845-848
  • A Couet, A T Motta and R J Comstock, 2014, "Effect of alloying elements on hydrogen pickup in zirconium alloys", 17th Zirconium in the Nuclear Industry, ASTM STP 1543., ASTM International, pp. 1-33
  • Kimberly Colas, Arthur T Motta, Mark R. Daymond and Jonathan Almer, 2014, "Mechanisms of hydride reorientation in Zircaloy-4 studied in situ", Zirconium in the Nuclear Industry: 17th International Symposium, STP 1543, ASTM International, pp. 1107-1137
  • B. de Gabory and Arthur T Motta, 2013, "Structure of Zircaloy 4 oxides formed during autoclave corrosion", ANS LWR Fuel Performance Meeting, TopFuel 2013
  • I. Davis, O. Courty, M. Avramova, Arthur T Motta and K. N. Ivanov, 2013, "High fidelity multi-physics coupling for prediction of anisotropic azimuthal power and temperature distribution on fuel rod: Impact on hydride distribution", Proceedings of the 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15)
  • K. B. Colas, Arthur T Motta, M. R. Daymond, J. Almer and Z. Cai, 2011, "Hydride behavior in Zircaloy-4 during thermomechanical cycling", 15th International Symposium on Environmental Degradation of Materials Nuclear Power Plants
  • J. B. Bischoff and Arthur T Motta, 2011, "Comparison of the oxidation behavior of the 14 CrODS alloy in steam and supercritical water", 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
  • A. Kohnert, T. Faney, B. D. Wirth, D. Kaoumi, C. Topbasi and Arthur T Motta, 2011, "Cluster dynamics modeling of defect evolution in ferritic martensitic iron chrome alloys", 15th International Conference on Fusion Reactor Materials, (ICFRM-15)
  • C. Topbasi, Arthur T Motta and M. A. Kirk, 2011, "Microstructure evolution of advanced ferritic-martensitic steels under 1 MeV Kr irradiation", 15th International Conference on Fusion Reactor Materials, (ICFRM-15)
  • Arthur T Motta, J. B. Bischoff, A. Siwy, M. J. Gomes da Silva, R. J. Comstock, Z. Cai and B. Lai, 2009, "Characterization of oxide layers formed during corrosion in supercritical water", Proceedings of the 17th NACE International Corrosion Congress
  • J. B. Bischoff, Arthur T Motta, Y. Chen and T. R. Allen, 2009, "Oxidation of 9CrODS exposed to supercritical water", Proceedings of the NACE 2009 Corrosion Conference
  • M. E. Flanagan, D. A. Koss and Arthur T Motta, 2008, "The influence of hydrogen on the deformation behavior of Zircaloy-4", Proceedings of the 2008 Water Reactor Fuel Performance Meeting
  • J. B. Bischoff, Arthur T Motta, L. Tan and T. R. Allen, 2008, "Influence of alloy microstructure on oxide growth in HCM12A in supercritical water", Materials Research Society (MRS) Proceedings Symposium R: Materials for Future Fusion and Fission Technologies
  • J. Kunkle, Arthur T Motta, R. J. Comstock and P. Hosemann, 2008, "Characterization of HT-9 ferritic-martensitic steels oxidized in lead bismuth eutectic", Transactions of the American Nuclear Society and Embedded Topical Meetings: Isotopes for Medicine and Industry and Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors (NFSM), pp. 1115-1116
  • D. Kaoumi, Arthur T Motta and M. A. Kirk, 2008, "Characterization and in-situ ion-irradiation of MA957 ODS steel", Transactions of the American Nuclear Society and Embedded Topical Meetings: Isotopes for Medicine and Industry and Nuclear Fuels and Structural Materials fr the Next Generation Nuclear Reactors (NFSM), pp. 1113-1114
  • Arthur T Motta, A. D. Siwy, J. M. Kunkle, J. B. Bischoff, R. J. Comstock, Y. Chen and T. R. Allen, 2007, "Microbeam synchrotron radiation diffraction and fluorescence study of oxide layers formed on 9CrODS steel in supercritical water", Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Systems-Water Reactors
  • P. A. Raynaud, M. J. Meholic, D. A. Koss, Arthur T Motta and K. S. Chan, 2007, "Influence of hydride microstructure on through-thickness crack growth in Zircaloy-4 sheet", Proceedings of the 13th International Conference on Environmental Degradation of Materials in Nuclear Systems-Water Reactors
  • P. A. Raynaud, D. A. Koss, Arthur T Motta and K. S. Chan, 2007, "Fracture of hydrided Zircaloy-4 sheet under through-thickness crack growth conditions", Proceedings of the 2007 International LWR Fuel Performance Meeting
  • Y. H. Jeong, J. Y. Park, H. G. Kim, J. T. Busby, E. L. Gartner, M. Atzmon, G. S. Was, R. J. Comstock, M. Silva and Arthur T Motta, 2006, "Corrosion of Zr-based fuel cladding alloys in supercritical water", Proceedings of the 12th Int. Conference on Degradation of Materials in Nuclear Systems: Water Reactors, pp. 1369-1377
  • A. Yilmazbayhan, Arthur T Motta, H. G. Kim, Y. H. Jeong, J. Y. Park and R. J. Comstock, 2006, "Characterization of oxides formed on model zirconium alloys in 360 C water using synchrotron radiation", Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System – Water Reactors, pp. 201-210
  • D. Kaoumi, Arthur T Motta and R. C. Birtcher, 2006, "Irradiation-enhanced second-phase precipitation in Zr-Fe nanocrystalline thin films", Proceedings of the Symposium on Growth, Modification, and Analysis by Ion Beams at the Nanoscale, Materials Research Society Symposium Proceedings, 908E, pp. 0908-OO04-04.1 - 4.6
  • Arthur T Motta, A. Yilmazbayhan, R. Comstock, B. Lai and Z. Cai, 2004, "Using small X-ray beams to understand corrosion in nuclear fuel cladding", Proceedings of IMECE04; 2004 ASME International Mechanical Engineering Congress
  • R. S. Daum, D. W. Bates, D. A. Koss and Arthur T Motta, 2003, "The Influence of a Hydrided Layer on the Fracture of Zircaloy-4 Cladding Tubes", Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions, pp. 249-258
  • Arthur T Motta, R. A. Holt and U. Colak, 2003, "Irradiation growth in zirconium at low temperatures by direct athermal deposition of vacancies at extended sinks", 11th ASTM International Symposium on Reactor Dosimetry, World Scientific, New Jersey, pp. 278-285
  • O. N. Pierron, D. A. Koss, Arthur T Motta, R. S. Daum and K. S. Chan, 2002, "Failure of Zircaloy-4 sheet containing hydride blisters", Proceedings of the Nuclear Safety Research Conference
  • R. S. Daum, S. Majumdar, M. C. Billone, D. W. Bates, D. A. Koss and Arthur T Motta, 2002, "On the embrittlement of Zircaloy-4 under RIA relevant conditions", 13th International Symposium on Zirconium in the Nuclear Industry, pp. 696-713
  • Adrien Couet, Arthur T Motta and Robert J Comstock, , "Effect of Alloying Elements on Hydrogen Pickup in Zirconium Alloys", 17th ASTM International Symposium on Zr in the Nuclear Industry, STP, (1543)

Journal Article

  • A. Couet, Arthur T Motta, A. Ambard and Didier Livigni, 2017, "In-situ electrochemical impedance spectroscopy measurements of zirconium alloy oxide conductivity: relationship to hydrogen pickup", Corrosion Science, 100
  • Ece Alat, Arthur T Motta, Robert J. Comstock, Jonna M. Partezana and Douglas E Wolfe, 2016, "Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding(vol 281pg 133, 2015)", Surface and Coatings Technology, 304, pp. 620
  • Mohamed S. Elbakhshwan, Simerjeet K. Gill, Arthur T Motta, Randy Weidner, Thomas Anderson and Lynne E. Ecker, 2016, "Sample environment for in situ synchrotron corrosion studies ofmaterials in extreme environments", Review of Scientific Instruments, 87, (10)
  • Ece Alat, Arthur T Motta, Robert J. Comstock, Jonna M. Partezana and Douglas E Wolfe, 2016, "Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding", Journal of Nuclear Materials, 478, pp. 236-244
  • Mahmut N. Cinbiz, Donald A. Koss and Arthur T Motta, 2016, "The influence of stress state on the reorientation of hydrides in a zirconium alloy", Journal of Nuclear Materials, 477, pp. 157-164
  • M. Desormeaux, B. Rouxel, Arthur T Motta, M. Kirk, C. Bisor, Y. de Carlan and A. Legris, 2016, "Development of radiation damage during in-situ Kr++ irradiation ofFe-Ni-Cr model austenitic steels", Journal of Nuclear Materials, 475, pp. 156-167
  • Arthur T Motta, Adrien Couet and Robert J. Comstock, 2015, "Corrosion of zirconium alloys used for nuclear fuel cladding", Annual Review of Materials Research, 45, pp. 311-343
  • Arthur T Motta, T.R. Allen , D. Kaoumi , J.P. Wharry , Z. Jiao , C. Topbasi , A. Kohnert , L. Barnard , A. Certain , K.G. Field , G.S. Was , D.L. Morgan , B.D. Wirth and , Y. Yang , 2015, "Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature", Journal of Materials Research, 30
  • Benoit de Gabory, Arthur T Motta and Ke Wang, 2015, "Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO oxide layers", Journal of Nuclear Materials, 456, pp. 272-280
  • E. Alat, Arthur T Motta, R. J. Comstock, J. M. Partezana and Douglas E Wolfe, 2015, "Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding", Surface & Coatings Technology, 281, pp. 133-143
  • T. R. Allen, D. Kaoumi, J. P. Wharry, Z. J. Jiao, C. Topbasi, A. Kohnert, L. Barnard, A. Certain, K. G. Field, G. S. Was, D. L. Morgan, Arthur T Motta, B. D. Wirth and Y. Yang, 2015, "Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature", Journal of Materials Research, 30, (9), pp. 1246-1274
  • D. J. Spengler, Arthur T Motta, R. Bajaj, J. R. Seidensticker and Z. H. Cai, 2015, "Characterization of Zircaloy-4 corrosion films using microbeam synchrotron radiation", Journal of Nuclear Materials, 464, pp. 107-118
  • B. de Gabory, Y. Dong, Arthur T Motta and E. A. Marquis, 2015, "EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation", Journal of Nuclear Materials, 462, pp. 304-309
  • Y. Liu, I. Bhamji, P. J. Withers, Douglas E Wolfe, Arthur T Motta and M. Preuss, 2015, "Evaluation of the interfacial shear strength and residual stress of TiAlN coating on ZIRLO (TM) fuel cladding using a modified shear-lag model approach", Journal of Nuclear Materials, 466, pp. 718-727
  • O. F. Courty, Arthur T Motta, C. J. Piotrowski and J. D. Almer, 2015, "Hydride precipitation kinetics in Zircaloy-4 studied using synchrotron X-ray diffraction", Journal of Nuclear Materials, 461, pp. 180-185
  • C. J. Ulmer, Arthur T Motta and M. A. Kirk, 2015, "In situ ion irradiation of zirconium carbide", Journal of Nuclear Materials, 466, pp. 606-614
  • J. Y. Park, I. H. Kim, Arthur T Motta, C. J. Ulmer, M. A. Kirk, E. A. Ryan and P. M. Baldo, 2015, "Irradiation-induced disordering and amorphization of Al3Ti-based intermetallic compounds", Journal of Nuclear Materials, 467, pp. 601-606
  • C. Topbasi, D. Kaoumi, Arthur T Motta and M. A. Kirk, 2015, "Microstructural evolution in NF616 (P92) and Fe-9Cr-0.1C-model alloy under heavy ion irradiation", Journal of Nuclear Materials, 466, pp. 179-186
  • A. Couet, Arthur T Motta and A. Ambard, 2015, "The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys", Corrosion Science, 100, pp. 73-84
  • Adrien Couet, Arthur T Motta and Robert J Comstock, 2014, "Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics", Journal of Nuclear Materials, 451, (1-3), pp. 1-13
  • A Couet, Arthur T Motta, B de Gabory and Z Cai, 2014, "Microbeam X-ray absorption near-edge spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers", Journal of Nuclear Materials, 452, pp. 311-320
  • O Courty, Arthur T Motta and J D Hales, 2014, "Modeling and simulation of hydrogen behavior in Zircaloy-4 fuel cladding", Journal of Nuclear Materials, 452, pp. 311-320
  • Y. Dong, Arthur T Motta and E. A. Marquis, 2013, "Atom probe tomography study of alloying element distributions in Zr alloys and their oxides", Journal of Nuclear Materials, 442, (1-3), pp. 270-281
  • J. Bischoff, Arthur T Motta, C. Eichfeld, R. J. Comstock, G. Cao and T. R. Allen, 2013, "Corrosion of ferritic-martensitic steels in steam and supercritical water", Journal of Nuclear Materials, 441, (1-3), pp. 604-611
  • K. B. Colas, Arthur T Motta, M. R. Daymond and J. D. Almer, 2013, "Effect of thermo-mechanical cycling on zirconium hydride reorientation studied in situ with synchrotron X-ray diffraction", Journal of Nuclear Materials, 440, pp. 586-595
  • A. Couet, Arthur T Motta, R. J. Comstock and R. L. Paul, 2012, "Cold neutron prompt gamma activation analysis, a non-destructive technique for hydrogen level assessment in zirconium alloys", Journal of Nuclear Materials, 425, pp. 211-217
  • C. Topbasi, Arthur T Motta and M. A. Kirk, 2012, "In situ study of heavy ion induced radiation damage in NF616 (P92) alloy", Journal of Nuclear Materials, 425, pp. 48-53
  • J. Bischoff and Arthur T Motta, 2012, "Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water", Journal of Nuclear Materials, 424, pp. 261-276
  • J. Bischoff and Arthur T Motta, 2012, "EFTEM and EELS analysis of the oxide layer formed on HCM12A exposed to SCW", Journal of Nuclear Materials, 430, pp. 171-180
  • Arthur T Motta and L.-Q. Chen, 2012, "Hydride formation in Zirconium alloys", Journal of Metals, 64, pp. 1403-1408
  • Arthur T Motta, 2011, "Waterside corrosion in zirconium alloys", Journal of the Minerals, Metals and Materials Society (JOM), 63, (8), pp. 59-63
  • J. Desquines, D. A. Koss, Arthur T Motta, B. Cazalis and M. Petit, 2011, "The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)", Journal of Nuclear Materials, 412, pp. 250-267
  • C. Bisor-Melloul, M. Tupin, P. Bossis, J. Chene, J. L. Bechade and Arthur T Motta, 2011, "Understanding of hydriding mechanisms during corrosion in PWR simulated conditions and influence of zirconium hydrides on corrosion", Revue Generale Nucleaire, (2), pp. 111-116
  • K. B. Colas, Arthur T Motta, J. D. Almer, M. R. Daymond, M. Kerr, A. D. Banchik, P. Vizcaino and J. R. Santisteban, 2010, "In situ study of hydride precipitation kinetics and re-orientation in Zircaloy using synchrotron radiation", Acta Materialia, 58, pp. 6575-6583
  • K. B. Colas, Arthur T Motta, M. R. Daymond, M. Kerr and J. D. Almer, 2010, "Hydride platelet reorientation in Zircaloy studied with synchrotron radiation diffraction", Journal of American Society for Testing and Materials (ASTM) International, 8, (1), pp. JAI103033
  • M. A. Kirk, P. M. Baldo, A. C. Y. Liu, E. A. Ryan, R. C. Birtcher, Z. Yao, S. Xu, M. L. Jenkins, M. Hernandez-Mayoral, D. Kaoumi and Arthur T Motta, 2009, "In-situ TEM and ion irradiation of ferritic materials", Microscopy and Research Technique, 72, pp. 182-186
  • R. S. Daum, Y. S. Chu and Arthur T Motta, 2009, "Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron radiation diffraction", Journal of Nuclear Materials, 392, (3), pp. 453-463
  • A. D. Siwy, T. E. Clark and Arthur T Motta, 2009, "Transmission electron microscopy of oxide development on 9Cr ODS in supercritical water", Journal of Nuclear Materials, 392, pp. 280-285
  • J. B. Bischoff, Arthur T Motta and R. J. Comstock, 2009, "Evolution of the oxide structure of 9CrODS exposed to supercritical water", Journal of Nuclear Materials, 392, pp. 272-279
  • J. Bentley, D. T. Hoelzer, J. T. Busby, A. G. Certain, T. R. Allen, D. Kaoumi, Arthur T Motta and M. A. Kirk, 2009, "TEM characterization of crept and irradiated nano-structured ferritic alloys", Microscopy and Microanalysis, 15, (S2), pp. 1350-1351
  • D. Kaoumi, Arthur T Motta and R. C. Birtcher, 2008, "Influence of alloying elements on grain-growth in Zr(Fe) and Cu(Fe) thin-films under in-situ ion irradiation", Journal of Nuclear Materials, 382, (2-3), pp. 184-189
  • P. A. Raynaud, D. A. Koss, Arthur T Motta and K. S. Chan, 2008, "Fracture toughness of hydrided Zircaloy-4 sheet under through-thickness crack growth conditions", Journal of ASTM International, 5, (1)
  • Arthur T Motta, M. J. Gomes da Silva, A. Yilmazbayhan, R. J. Comstock, J. Ilavsky, Z. Cai and B. Lai, 2008, "Microstructural characterization of oxides formed on model Zr alloys using synchrotron radiation", Journal of ASTM International, 5, (2)
  • D. Kaoumi, Arthur T Motta and R. C. Birtcher, 2007, "Grain growth in nanocrystalline metal thin films under in situ ion-beam irradiation", Journal of ASTM International, 4, (8)
  • Arthur T Motta, A. Yilmazbayhan, M. J. Gomes da Silva, R. J. Comstock, G. S. Was, J. T. Busby, E. Gartner, Q. Peng, Y. H. Jeong and J. Y. Park, 2007, "Zirconium alloys for supercritical water reactor applications: Challenges and possibilities", Journal of Nuclear Materials, 371, (1-3), pp. 61-75
  • Q. Peng, E. Gartner, J. T. Busby, Arthur T Motta and G. S. Was, 2007, "Corrosion behavior of model zirconium alloys in deaerated supercritical water at 500ºC", Corrosion, 63, (6), pp. 577-590
  • A. Yilmazbayhan, E. Breval, Arthur T Motta and R. J. Comstock, 2006, "Transmission electron microscopy examination of oxide layers formed in Zr alloys", Journal of Nuclear Materials, 349, pp. 265-281
  • D. Kaoumi, Arthur T Motta and R. C. Birtcher, 2006, "Grain growth in metallic thin films during in situ ion irradiation in A TEM", Nuclear Instruments and Methods in Physics Research B, 242, pp. 490-493
  • Arthur T Motta, Aylin Yilmazbayhan, Robert J. Comstock, Jonna M. Partezana, George P. Sabol, Barry Lai and Zhonghou Cai, 2005, "Microstructure and growth mechanism of oxide layers formed in Zr alloys studied with micro beam synchrotron radiation", Journal of ASTM International, 2, (5)
  • Andrew Glendening, Donald A. Koss, Olivier N. Pierron, Arthur T Motta and Robert S. Daum, 2005, "Failure of hydrided Zircaloy-4 under equal-biaxial and plane-strain tensile deformation", Journal of ASTM International, 2, (6)
  • D. R. Olander and Arthur T Motta, 2005, "A new book: 'Light-water reactor materials'", Nuclear Engineering and Technology, 37, (4), pp. 309-316
  • A. Yilmazbayhan, Arthur T Motta, R. J. Comstock, G. P. Sabol, B. Lai and Z. Cai, 2004, "Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: Relation to corrosion rate", Journal of Nuclear Materials, 324, pp. 6-22
  • O. N. Pierron, D. A. Koss and Arthur T Motta, 2003, "Tensile specimen geometry and the constitutive behavior of Zircaloy 4", Journal of Nuclear Materials, 312, pp. 257-261
  • O. N. Pierron, D. A. Koss, Arthur T Motta and K. S. Chan, 2003, "The influence of hydride blisters on the fracture of Zircaloy-4", Journal of Nuclear Materials, 322, pp. 21-35
  • A. Yilmazbayhan, O. Delaire, Arthur T Motta, R. C. Birtcher, J. M. Maser and B. Lai, 2003, "Determination of the Alloying Content in the Matrix of Zr Alloys Using Synchrotron Radiation Microprobe X-Ray Fluorescence", Journal of Nuclear Materials, 321, pp. 221-232
  • S. E. Cumblidge, Arthur T Motta, G. L. Catchen, J. Boehmert and G. Brauer, 2003, "Evidence for Irradiation-Induced Metallic Precipitates in Neutron Irradiated Model Alloys and Pressure Vessel Weld Steel", Journal of Nuclear Materials, 302, pp. 245-257
  • R. S. Daum, S. Majumdar, H. Tsai, T. S. Bray, D. A. Koss, Arthur T Motta and M. C. Billone, 2002, "Mechanical property testing of irradiated Zircaloy cladding under reactor transient conditions", pp. pp. 195
  • Arthur T Motta, K. T. Erwin, O. Delaire, R. C. Birtcher, Y. Chu, J. Maser, D. Mancini and B. Lai, 2002, "Synchrotron radiation study of second phase particles and alloying elements in Zircaloy-4", pp. 59-76
  • N. Poynor, S. E. Cumblidge, R. L. Rasera, G. L. Catchen and Arthur T Motta, 2002, "Hyperfine interactions of 181Ta in Zr2Ni observed using PAC spectroscopy", Hyperfine Interactions, 136, (3), pp. 549-553
  • Yan Dong, Arthur T Motta and Emmanuelle Marquis, , "Multi-scale Characterization of Oxidized Zirconium Alloys", Microscopy and Microanalysis, 22, (S3), pp. 2
  • Arthur T Motta, , "Mechanistic Understanding of Zirconium Alloy Fuel Cladding Performance", ASTM STP 1597 18th International Symposium on Zr in the Nuclear Industry
  • Arthur T Motta, Adrien Couet, Robert J Comstock and Antoine Ambard, , "Hydrogen Pick-Up Mechanism in Zirconium Alloys", ASTM STP 1597 18th International Symposium on Zr in the Nuclear Industry
  • Adytha Shivprasad, Arthur T Motta, Aylin Kucuk, Suresh Yagnik and Zhonghou J Cai, , "Microbeam X-Ray Absorption Near-Edge Spectroscopy of Oxide Layers in Irradiated Zircaloy-2", ASTM STP 1597 18th International Symposium on Zr in the Nuclear Industry
  • Mahmut N Cinbiz, Arthur T Motta, Donald A Koss and Michael Billone, , "Hydride Reorientation in Zircaloy-4 Under Different States of Stress as Studied With in Situ X-Ray Diffraction", ASTM STP 1597 18th International Symposium on Zr in the Nuclear Industry

Journal Article, In-House

  • J. Busby, T. S. Byun, R. Klueh, P. Maziasz, J. Vitek, K. Natesan, M. Li, R. Wright, S. Maloy, M. Toloczko, Arthur T Motta, B. D. Wirth, G. R. Odette and T. R. Allen, 2008, "Candidate developmental alloys for improved structural materials for advanced fast reactors"
  • Arthur T Motta and A. Pineau, 2008, "Sommaire sur le RIA et evaluation de la strategie IRSN"

Manuscript

  • Adrien Couet, Arthur T Motta, Benoit de Gabory and Zhonghou Cai, 2014, "Microbeam X-Ray absorption near-edge spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers", Journal of Nuclear Materials, 452, pp. 614-627
  • C. Topbasi, Arthur T Motta and M. A. Kirk, 2011, "In-situ study of heavy ion induced radiation damage in NF616 (P92) alloy", Journal of Nuclear Materials
  • A. Couet, Arthur T Motta, B. De Gabory and Z. Cai, , "X-ray absorption near-edge spectroscopy study of Fe and Nb oxidation states evolution in Zircaloy-4, ZIRLO, Zr-2.5Nb and Zr-0.4Fe-0.2Cr oxide layers", Journal of Nuclear Materials
  • P. A. Raynaud, D. A. Koss and Arthur T Motta, , "Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet", Journal of Nuclear Materials, 420, (1), pp. 69-82

Other

  • J. R. M.-L. Lescoat, A. Gentils, O. Kaitasov, E. Marquis, Arthur T Motta, M. Kirk and Y. de Carlan, 2012, "Stability of 18 chromium ODS steels under ion-irradiation"
  • T. W. Heo, K. B. Colas, Arthur T Motta and L.-Q. Chen, 2012, "Phase-field simulation and experimental measurements of delta-hydride precipitation in Zr-alloys"
  • Arthur T Motta, , "Light water reactor materials", American Nuclear Society
  • Arthur T Motta, , "Rapid access to 1BM diffraction beam line", Advanced Photon Source

Part of Book

  • C. Lemaignan and Arthur T Motta, , Zirconium alloys in nuclear reactors, VCH, Germany

Research Projects

  • March 2014 - March 2017, "Three-dimensional fuel pin model validation by prediction of hydrogen distribution in cladding and comparison with experiment," (Sponsor: DOE-NEUP).
  • June 2013 - May 2017, "Analysis of Oxide layers in Zircaloy-4 using Synchrotron radiation," (Sponsor: Bettis Laboratories).
  • March 2014 - March 2017, "High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation," (Sponsor: DOE-NEUP Integrated research Program).
  • January 2013 - January 2017, "NEUP: IRP: Advanced Accident-Tolerant Ceramic Coatings for Zr-alloy Cladding: The C^3 Project," (Sponsor: University of Tennessee - Knoxville).
  • August 2013 - August 2016, "Faculty Development Grant for Sensor Development and Control Methods in Nuclear Power Plants," (Sponsor: NRC).
  • September 2012 - June 2016, "Characterization of Irradiated Zr-Based Alloys and Alloy Oxides using Advanced Synchrotron Radiation Techniques," (Sponsor: Electric Power Research Institute).
  • January 2011 - December 2015, "NEUP: Fundamental Studies of the Role of Grain Boundaries on Uniform Corrosion of Advanced Nuclear Reactor Materials," (Sponsor: Drexel University).

Honors and Awards

  • Wlliam J. Kroll Medal, ASTM, May 2016
  • 2016 Leaders of Engineering Lecture, Rensselaer Polytechnic Institute, Mechanical Aerospace and Nuclear Engineering Department, March 2016
  • Mishima Award, American Nuclear Society, April 2015
  • Fellow of the American Nuclear Society, American Nuclear Society, November 2014 - November 2014

Service

Service to Penn State:

  • Chairperson, NucE Faculty Search Committee, September 2015 - February 2016
  • Member, AD-14 Review Committe for Kenan Unlu as RSEC and Breazeale Reactor Director, August 2016 - October 2016
  • Chairperson, NucE Faculty Search Committee, June 2016 - December 2016
  • Member, Assistant Dean for Undergraduate and Graduate Studies Search Committee, May 2014 - May 2015
  • Member, NucE Faculty Search Committee, October 2013 - June 2014
  • Chairperson, Faculty Search Committee, August 2014 - December 2014
  • Member, Faculty Search Committee MatSE, September 2010 - November 2012
  • Member, Committee Member, Engineering Management Committee, September 2015
  • , Graduate Coordinator for NucE, August 2015
  • Member, Mechanical and Nuclear Engineering Executive Committee, July 2010
  • , ABET Coordinator for NucE, June 2015
  • Member, FEW (Food Energy Water) Nexus Working Group, April 2015
  • Chairperson, NucE Candidacy Exam Committee, August 2015
  • Chairperson, NucE Distinguished Speaker Series Commmittee, July 2010
  • Member, MNE Assessment of Curricula, July 2010

Service to External Organizations:

  • Co-Organizer, NuMat 2016 Track 2 Chair, Elsevier, February 2016 - November 2016
  • Chairperson, Symposium Chair, 18th ASTM International Symposium on Zirconium in the Nuclear Industry, ASTM, September 2014 - May 2016
  • Committee Member, Lessons Learned from the Fukushima Nuclear Accident for Improving Safety of U.S. Nuclear Power Plants, Phase II: Spent Fuel Pools, National Academy of Sciences Committee, August 2014 - January 2016
  • Organizer, Semi-annual meeting on High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation held at PSU, DOE NEUP-IRP, June 2015 - June 2015
  • Organizer, Argonne National Laboratory, September 2014 - September 2014
 


 

About

The Department of Mechanical and Nuclear Engineering at Penn State is one of the nation’s largest and most successful engineering departments. We serve more than 1,000 undergraduate students and more than 330 graduate students

We offer B.S. degrees in mechanical engineering and nuclear engineering as well as resident (M.S., Ph.D.) and online (M.S., M.Eng.) graduate degrees in nuclear engineering and mechanical engineering. MNE's strength is in offering hands-on experience in highly relevant research areas, such as energy, homeland security, biomedical devices, and transportation systems.

Department of Mechanical and Nuclear Engineering

137 Reber Building

The Pennsylvania State University

University Park, PA 16802-4400

Phone: 814-865-2519