- Prof. Arthur Motta
- Pennsylvania State University
- Penn State
- CV File
Arthur Motta is the Chair of the Graduate Nuclear Engineering Program and a Professor of Nuclear Engineering and Materials Science and Engineering at Penn State University. He holds degrees in Mechanical Engineering and Nuclear Engineering from the Federal University of Rio de Janeiro, Brazil, and a Ph.D. in Nuclear Engineering from the University of California, Berkeley. Before joining the Penn State faculty in 1992, he worked as a research associate for the CEA at the Centre for Nuclear Studies in Grenoble, France, for two years and as a post-doctoral fellow for AECL at Chalk River Laboratories in Canada.
Prof. Motta works in the area of radiation damage and environmental degradation to materials with specific emphasis in Zr alloys, with current projects in the areas of mechanical testing, corrosion and radiation damage. He has special interests in using advanced characterization techniques such as x-ray scattering from synchrotron radiation sources, transmission electron microscopy, and in situ irradiation to discern fundamental mechanisms of corrosion and radiation damage.
Prof. Motta is a Fellow of the American Nuclear Society (ANS) and in 2015 he received the Mishima Award from the ANS for outstanding contributions in research and development work on nuclear fuel and materials. In 2016 he was awarded the ASTM William J. Kroll Medal for sustained impactful contributions to zirconium metallurgy including corrosion, hydriding, mechanical properties and irradiation effects.
- Amorphization, Cladding, Corrosion, Hydrides, intermetallic, Material Characterization, Material Degradation, Radiation Damage, Synchrotron, Zirconium, Zirconium Alloys
|"Application of NSUF Capabilities Towards Understanding the Emulation of High Dose Neutron Irradiations with Ion Beams" Kevin Field, Stephen Taller, Christopher Ulmer, Zhijie Jiao, Tarik Saleh, Arthur Motta, Gary Was, Transactions of the American Nuclear Society Vol. 116 2017 Link|
|"Characterization of faulted dislocation loops and cavities in ion irradiated alloy 800H" Christopher Ulmer, Arthur Motta, Journal of Nuclear Materials Vol. 498 2018 458-467 Link|
"Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature"
Todd Allen, Zhijie Jiao, Djamel Kaoumi, Janelle Wharry, cem topbasi, Aaron Kohnert, Leland Barnard, Alicia Certain, Kevin Field, Gary Was, Dane Morgan, Arthur Motta, Brian Wirth, Yong Yang,
Journal of Materials Research
Designing materials for performance in high-radiation fields can be accelerated through a carefully chosen combination of advanced multiscale modeling paired with appropriate experimental validation. The studies reported in this work, the combined efforts of six universities working together as the Consortium on Cladding and Structural Materials, use that approach to focus on improving the scientific basis for the response of ferritic–martensitic steels to irradiation. A combination of modern modeling techniques with controlled experimentation has specifically focused on improving the understanding of radiation-induced segregation, precipitate formation and growth under radiation, the stability of oxide nanoclusters, and the development of dislocation networks under radiation. Experimental studies use both model and commercial alloys, irradiated with both ion beams and neutrons. Transmission electron microscopy and atom probe are combined with both first-principles and rate theory approaches to advance the understanding of ferritic–martensitic steels.
|"Emulation of neutron-irradiated microstructure of austenitic 21Cr32Ni model alloy using dual-ion irradiation" Muhammet Ayanoglu, Arthur Motta, Journal of Nuclear Materials Vol. 570 2022 Link|
|"Microbeam X-ray Absorption Near-edge Spectroscopy of Alloying Elements in the Oxide Layers of Irradiated Zircaloy-2" Aditya Shivprasad, Arthur Motta, Aylin Kucuk, Suresh Yagnik, Zhonghou Cai, OSTI.gov, Vol. 2018 Link|
|"Microstructural evolution of the 21Cr32Ni model alloy under irradiation" M. Ayanoglu, Arthur Motta, Journal of Nuclear Materials Vol. 510 2018 297-311 Link|
|U.S. Department of Energy Announces FY17 CINR FOA Awards - DOE selected 14 NSUF projects DOE selected five university, four national laboratory, and five industry-led projects that will take advantage of NSUF capabilities to investigate important nuclear fuel and material applications. Wednesday, September 20, 2017 - Calls and Awards|
This NSUF Profile is 100
Authored an NSUF-supported publication
Presented an NSUF-supported publication
Submitted an RTE Proposal to NSUF
Awarded an RTE Proposal
Collaborated on 3+ RTE Proposals
Microstructure Analysis of High Dose Neutron Irradiated Alloys - FY 2018 RTE 3rd Call, #1531
Microstructure Analysis of HIgh Dose Neutron Irradiated Microstructures - FY 2013 RTE Solicitation, #425
Microstructure Analysis of High Dose Neutron Irradiated Microstructures - FY 2016 RTE 2nd Call, #650
The microstructure characterization of 21Cr32Ni model austenitic alloy irradiated at BOR60 reactor - FY 2019 RTE 2nd Call, #1730