Justin Thomas
Engineering · The Ohio State University
Publications
82
Citations
733
Est. group size
~23
Recurring co-author estimate
Active years
61
Publishing since 1966
This record appears to combine work from multiple distinct researchers sharing the same name, spanning nuclear reactor engineering (safety analysis, thermal-hydraulics, and simulation of advanced reactor designs like the Versatile Test Reactor and heat-pipe microreactors), as well as unrelated topics such as antibody pharmacokinetics, uterine tumor biology, and construction materials. The nuclear engineering thread focuses on modeling and verifying computational tools used to predict reactor behavior under normal and accident conditions. Prospective students should verify which specific body of work and institutional affiliation corresponds to the advisor they are considering, given the apparent mixing of unrelated research areas under one name.
Publication output has grown somewhat over the last decade, rising from a handful of papers per year in 2017-2021 to a peak of 7 in 2023, though the underlying topics suggest this trend may reflect merged records from different authors rather than one continuous research trajectory.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- PARET/ANL v7.7 Verification and Validation Report
2025
- Predicting the clinical subcutaneous absorption rate constant of monoclonal antibodies using only the primary sequence: a machine learning approach
mAbs · 2024
- Productivity Analysis of Structural Steel Fabrication in Construction Using Simulation
Lecture notes in operations research · 2023
- Verification and Validation of the STAT7 Code
2023
- Non thymomatous dual antibody positive myesthenia gravis
Journal of the Neurological Sciences · 2023
- Modeling of Safety Basis Events in the VTR
Nuclear Science and Engineering · 2022
- Safety Analysis for the Versatile Test Reactor Conceptual Design
2022
- Simulation of a TRISO-Fueled Heat-Pipe Microreactor Using MOOSE-Based Reactor Physics Code Griffin
2022
- Thermal-Hydraulics Modeling and Simulations of Hot Pool Using the SAS-CFD Coupled Code
2022
- Initial Sensitivity Analyses for Versatile Test Reactor Transient Safety Performance
Transactions of the American Nuclear Society - Volume 123 · 2020
- Multiscale modelling of the phénix dissymmetric test benchmark
Nuclear Engineering and Design · 2019
- System thermal-hydraulic modelling of the phénix dissymmetric test benchmark
Nuclear Engineering and Design · 2019
- Cellular kinetics of MED12-mutant uterine leiomyoma growth and regression in vivo
Endocrine Related Cancer · 2018
- Subtype-Specific Tumor-Associated Fibroblasts Contribute to the Pathogenesis of Uterine Leiomyoma
Cancer Research · 2017
- Fibre Reinforced Pervious Concrete Using Banana Fibre
International Journal of Engineering and Management Research · 2017
- Regular and Young Investigator Award Abstracts×5
- Nuclear Engineering and Design×3
- mAbs×1
- Cancer Research×1
- The Journal of General Physiology×1
- Yunlin Xu
Engineering · Purdue University West Lafayette
- Muhammad Rizki Oktavian
Engineering · Purdue University West Lafayette
- Hany S. Abdel‐Khalik
Engineering · Purdue University West Lafayette
- Hussein Khalil
Engineering · Purdue University West Lafayette
- L.R.C. Moraes
Engineering · The Ohio State University
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 19, 2026.
Claim or correct this profile