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Materials Science

D-Index
45
Citations
9025
World Ranking
11660
National Ranking
2725

Overview

Arthur T. Motta is affiliated with Pennsylvania State University in the United States. Their research primarily focuses on materials science and engineering, with a specific emphasis on nuclear materials and related fields.

The main fields of study associated with their work include:

  • Materials Science
  • Engineering

Their subfields of study reflect specialized interests in:

  • Materials Chemistry
  • Aerospace Engineering
  • Mechanical Engineering
  • Metals and Alloys
  • Inorganic Chemistry

Key topics covered in their publications are:

  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Fusion materials and technologies
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Nuclear materials and radiation effects
  • Nuclear Engineering Thermal-Hydraulics
  • Solidification and crystal growth phenomena

Arthur T. Motta has contributed extensively to several journals with a notable concentration of work published in the Journal of Nuclear Materials, with 16 publications. Other frequent publication venues include:

  • Computational Materials Science
  • Nuclear Engineering and Design
  • Acta Materialia
  • Microscopy and Microanalysis

Their recent publications reflect ongoing research into zirconium alloys, hydride morphology, and neutron damage effects, among other topics. Recent papers include:

  • Quantifying the effect of hydride microstructure on zirconium alloys embrittlement using image analysis, 2021, Journal of Nuclear Materials
  • Implementation and Validation of the Hydride Nucleation-Growth-Dissolution (HNGD) model in BISON, 2020, Journal of Nuclear Materials
  • Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments, 2021, Journal of Nuclear Materials
  • Emulation of neutron damage with proton irradiation and its effects on microstructure and microchemistry of Zircaloy-4, 2021, Journal of Nuclear Materials
  • In-situ ion irradiation induced grain growth in nanocrystalline ceria, 2020, Journal of Nuclear Materials

Frequent co-authors in their research include:

  • Pierre-Clément A. Simon
  • B.F. Kammenzind
  • Michael Tonks
  • Gary S. Was
  • Florian Passelaigue

Best Publications

  • Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium

    W. J. Weber;R. C. Ewing;C. R. A. Catlow;T. Diaz de la Rubia

  • Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding

    Arthur T. Motta;Adrien Couet;Robert J. Comstock

  • Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate

    Aylin Yilmazbayhan;Arthur T Motta;Robert J Comstock;George P Sabol

  • Hydrogen in zirconium alloys: A review

    Arthur T. Motta;Laurent Capolungo;Long Qing Chen;Mahmut Nedim Cinbiz

  • Transmission electron microscopy examination of oxide layers formed on Zr alloys

    Aylin Yilmazbayhan;Else Breval;Arthur T. Motta;Robert J. Comstock

  • Zirconium Alloys in Nuclear Applications

    Clément Lemaignan;Arthur T. Motta

  • A thermal spike model of grain growth under irradiation

    D. Kaoumi;A. T. Motta;R. C. Birtcher

  • Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding

    Ece Alat;Arthur T. Motta;Robert J. Comstock;Jonna M. Partezana

  • Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

    Arthur T. Motta;Aylin Yilmazbayhan;Marcelo J. Gomes da Silva;Robert J. Comstock

  • Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water

    Jeremy Bischoff;Arthur T. Motta

  • Corrosion of Zirconium Alloys

    T.R. Allen;R.J.M. Konings;A.T. Motta

  • Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics

    Adrien Couet;Arthur T. Motta;Robert J. Comstock

  • In situ study of hydride precipitation kinetics and re-orientation in Zircaloy using synchrotron radiation

    K.B. Colas;A.T. Motta;J.D. Almer;M.R. Daymond

  • Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction

    R. S. Daum;Y. S. Chu;A. T. Motta

  • Precipitate evolution in the Zircaloy-4 oxide layer

    D. Pêcheur;F. Lefebvre;Arthur Thompson Motta;C. Lemaignan

  • Amorphization of intermetallic compounds under irradiation - A review

    Arthur T. Motta

  • The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys

    Adrien Couet;Arthur T. Motta;Antoine Ambard

  • Hydride Formation in Zirconium Alloys

    Arthur T. Motta;Long Qing Chen

  • Atom probe tomography study of alloying element distributions in Zr alloys and their oxides

    Yan Dong;Arthur T. Motta;Emmanuelle A. Marquis

  • Transmission electron microscopy characterization of Zircaloy-4 and ZIRLO™ oxide layers

    Benoit de Gabory;Arthur T. Motta;Ke Wang

  • Failure of Zircaloy cladding under transverse plane-strain deformation

    T.M. Link;D.A. Koss;A.T. Motta

  • Zirconium alloys for supercritical water reactor applications : Challenges and possibilities

    Arthur Motta;Aylin Yilmazbayhan;Marcelo Silva;Robert J. Comstock

Frequent Co-Authors

Gary S. Was
Gary S. Was University of Michigan–Ann Arbor
Todd R. Allen
Todd R. Allen University of Michigan–Ann Arbor
Jonathan Almer
Jonathan Almer Argonne National Laboratory
Mark R. Daymond
Mark R. Daymond Queen's University
Long Qing Chen
Long Qing Chen Pennsylvania State University
Brian D. Wirth
Brian D. Wirth University of Tennessee at Knoxville
Marquis A. Kirk
Marquis A. Kirk Argonne National Laboratory
Robert S. Daum
Robert S. Daum University of Chicago
Emmanuelle A. Marquis
Emmanuelle A. Marquis University of Michigan–Ann Arbor
Dane Morgan
Dane Morgan University of Wisconsin–Madison

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