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Materials Science

D-Index
60
Citations
11403
World Ranking
7150
National Ranking
1779

Overview

Todd R. Allen is affiliated with the University of Michigan-Ann Arbor in the United States. Their research primarily focuses on Engineering, with a significant concentration in subfields such as Mechanical Engineering, Aerospace Engineering, and Materials Chemistry. Additional areas of study include Safety, Risk, Reliability and Quality, as well as Sociology and Political Science.

The main topics covered in Todd R. Allen's work include:

  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Mechatronics Education and Applications
  • Graphite, nuclear technology, radiation studies
  • Integrated Energy Systems Optimization
  • Microstructure and Mechanical Properties of Steels
  • Metallurgy and Material Forming

Their recent papers are diverse and span various journals and years of publication:

  • IEEE/ASME Transactions on Mechatronics, 2022
  • RNN-Based online anomaly detection in nuclear reactors for highly imbalanced datasets with uncertainty, Nuclear Engineering and Design, 2020
  • IEEE/ASME Transactions on Mechatronics, 2022
  • Technoeconomic analysis of small modular reactors decarbonizing industrial process heat, Joule, 2023
  • IEEE/ASME Transactions on Mechatronics, 2022

Todd R. Allen frequently collaborates with several co-authors, including:

  • I-Ming Chen
  • George T.-C. Chiu
  • Dawn Melley
  • Peter Tuohy
  • K Ray Liu

The scientist publishes regularly in a number of venues, with the most frequent being:

  • IEEE/ASME Transactions on Mechatronics
  • SSRN Electronic Journal
  • Nuclear Engineering and Design
  • Joule
  • New Labor Forum

In addition to journal articles, Todd R. Allen has contributed to book publications. Notably, they authored a book titled Comprehensive Nuclear Materials, published by Elsevier BV in 2020, which has garnered a significant number of citations.

Best Publications

  • Comprehensive Nuclear Materials

    Rudy J. M. Konings;Todd R. Allen;Roger E Stoller;Shinsuke Yamanaka

  • Materials corrosion in molten LiF–NaF–KF salt

    Luke C. Olson;James W. Ambrosek;Kumar Sridharan;Mark H. Anderson

  • Corrosion and stress corrosion cracking in supercritical water

    G.S. Was;P. Ampornrat;G. Gupta;S. Teysseyre

  • Emulation of neutron irradiation effects with protons: validation of principle

    G.S Was;J.T Busby;T Allen;E.A Kenik

  • Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants

    L. Tan;X. Ren;K. Sridharan;T.R. Allen

  • Corrosion of a stainless steel and nickel-based alloys in high temperature supercritical carbon dioxide environment

    V. Firouzdor;K. Sridharan;G. Cao;M. Anderson

  • Corrosion behavior of ferritic–martensitic steel T91 in supercritical water

    Yun Chen;Kumar Sridharan;Todd Allen

  • Corrosion of austenitic alloys in high temperature supercritical carbon dioxide

    G. Cao;V. Firouzdor;K. Sridharan;M. Anderson

  • Effect of thermomechanical treatment on the corrosion of AA5083

    L. Tan;T.R. Allen

  • On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys

    T.R. Allen;J.T. Busby;G.S. Was;E.A. Kenik

  • Corrosion behavior of 9-12% Cr ferritic-martensitic steels in supercritical water

    Lizhen Tan;Xiaowei Ren;Todd R. Allen

  • Corrosion of Zirconium Alloys

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

  • Effect of shot-peening on the oxidation of alloy 800H exposed to supercritical water and cyclic oxidation

    L. Tan;X. Ren;K. Sridharan;T.R. Allen

  • Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys

    Gary S. Was;Janelle P. Wharry;Brian Frisbie;Brian D. Wirth

  • Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys

    J.D. Tucker;R. Najafabadi;T.R. Allen;D. Morgan

  • Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation

    T.R. Allen;J. Gan;J.I. Cole;M.K. Miller

  • Materials Challenges for Generation IV Nuclear Energy Systems

    T. R. Allen;K. Sridharan;L. Tan;W. E. Windes

  • Corrosion of austenitic and ferritic-martensitic steels exposed to supercritical carbon dioxide

    Lizhen Tan;Mark Anderson;D Taylor;Todd R. Allen

  • The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water

    L. Tan;K. Sridharan;T.R. Allen

  • Microstructure tailoring for property improvements by grain boundary engineering

    Lizhen Tan;K. Sridharan;Todd R. Allen;Randy K Nanstad

  • Oxidation behavior of iron-based alloy HCM12A exposed in supercritical water

    L. Tan;Y. Yang;T.R. Allen

Frequent Co-Authors

Kumar Sridharan
Kumar Sridharan University of Wisconsin–Madison
Lizhen Tan
Lizhen Tan Oak Ridge National Laboratory
Gary S. Was
Gary S. Was University of Michigan–Ann Arbor
Arthur T. Motta
Arthur T. Motta Pennsylvania State University
Marquis A. Kirk
Marquis A. Kirk Argonne National Laboratory
Suntharampillai Thevuthasan
Suntharampillai Thevuthasan Pacific Northwest National Laboratory
Shigeharu Ukai
Shigeharu Ukai Hokkaido University
Roger E. Stoller
Roger E. Stoller Oak Ridge National Laboratory
Dane Morgan
Dane Morgan University of Wisconsin–Madison
Brian D. Wirth
Brian D. Wirth University of Tennessee at Knoxville

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