Publications
Journal articles, conference papers, technical reports, presentations, and posters — a selection, more added over time. Self-published studies are not refereed and are marked where they were drafted with AI assistance.
2026
Does a Meta-Doctrine System Change Model Behaviour, or Just Make It Legible? A Self-Ablation Study Under Equal Compute
S. Greenwood — Self-published study report
What Survives When Best Practice Catches Up? A Twin-Chain Longitudinal Evaluation of a Meta-Doctrine Layer for AI Coding Agents
S. Greenwood — Self-published study report
2025
An Interactive Virtual Radioisotope Processing Facility
S. Greenwood, M. Naranjo, W. Kirkland, B. Beatty — ANS Annual Conference, Chicago, Illinois
Enhancing Radiation Glovebox Training with Coupled Immersive Technology and Real-Time Dose Estimates
S. Greenwood, D. De Wet, L. Harris, N. Nelson, G. Westphal — ANS Annual Conference 2025, Chicago, Illinois
Analyzing Human Performance in Immersive Extended Reality Environments
D. W. Yoo, M. S. Greenwood, L. Harris
Modeling HFIR's Steady State Heat Transfer Code with Modelica
R. Barr, M. S. Greenwood, W. Williams, K. Lee
2024
A Digital Twin Framework for Liquid-cooled Supercomputers as Demonstrated at Exascale★
W. Brewer, M. Maiterth, V. Kumar, R. Wojda, S. Bouknight, J. Hines, W. Shin, M. S. Greenwood, D. Grant, W. Williams, F. Wang — The International Conference for High Performance Computing, Networking, Storage, and Analysis
Thermo-Fluid Modeling Framework for Supercomputer Digital Twins: Part 1, Demonstration at Exascale
V. Kumar, M. S. Greenwood, W. Brewer, D. Grant, N. Parkison, W. Williams — America Modelica Conference
Thermo-Fluid Modeling Framework for Supercomputing Digital Twins: Part 2, Automated Cooling Models
M. S. Greenwood, V. Kumar, W. Brewer — America Modelica Conference
Visualizing an Exascale Data Center Digital Twin: Considerations, Challenges and Opportunities
M. Maiterth, W. Brewer, D. De Wet, S. Greenwood, V. Kumar, J. Hines, S. Bouknight, J. Wang, T. Dykes, F. Wang — IEEE Visualization and Visual Analytics (IEEE VIS 2024), St. Pete Beach, Florida
2023
Using Augmented Reality for Visualizing and Interacting with Ionizing Radiation Data
M. S. Greenwood et al. — US Patent Application No. 18/134,649
2022
Corrosion of 316H stainless steel in flowing FLiNaK salt
S. Raiman, M. Kurley III, D. Sulejmanovic, A. Willoughby, S. Nelson, K. Mao, C. Parsih, M. S. Greenwood, B. Pint — Journal of Nuclear Materials
Dynamic Mass Accountancy Modeling of a Molten Salt Reactor Using Equilibrium Thermodynamics
M. Poschmann, M. Piro, M. S. Greenwood — Nuclear Engineering and Design
SOURCE TERM AND DEPLETION COUPLING WITH DYNAMIC SYSTEM MODELING SOLUTIONS FOR FUEL CYCLE OPERATIONS
S. Skutnik, B. R. Betzler, M. Dion, M. S. Greenwood — NURETH-19: International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Virtual Interaction with Physics Enhanced Reality (VIPER): Using Augmented Reality to Visualize and Interact with Ionizing Radiation Data★
M. Smith, M. S. Greenwood, N. Nelson, N. Thompson, D. Peplow — ANS Annual Meeting
2021
Candidate Core Designs for the Transformational Challenge Reactor
B. Ade, B. R. Betzler, A. Wysocki, M. S. Greenwood, P. Chesser, K. Terrani, P. Jain, J. Burns, B. Hiscox, J. Rader, J. Heineman, F. Heidet, A. Bergeron, J. Sterbentz, T. Holschuh, N. Brown, Robert Kile — Journal of Nuclear Energy
Identifying Candidate Biomarkers of Ionizing Radiation in Human Pulmonary Microvascular Lumens Using Microfluidics—A Pilot Study
L. Millet, R. Giannone, M. S. Greenwood, C. Foster, K. O'Neil, A. Braatz, S. Davern — Micromachines
Review of molten salt reactor off-gas management considerations
H. Andrews, J. McFarlane, S. Chapel, N. D. Ezell, D. Holcomb, D. De Wet, M. S. Greenwood, K. Myhre, S. Bryan, A. Lines, B. Riley, H. Felmy, P. Humrickhouse — Nuclear Engineering and Design
An Overview of the Integrated Energy System Investigation of the Eastman Chemical Company Kingsport, Tennessee, Facility
M. S. Greenwood, A. Yigitoglu, J. Rader, R. Cumberland, W. Poore III, R. Belles, B. Zhang, M. Muhlheim, W. Tharp — Waste Management Symposium 2021 (WM2021)
Dynamic Modeling and Signatures of a Liquid-Fueled Molten Salt System
L. Scott, M. Dion, M. S. Greenwood, K. Hogue, S. O'Brien, S. Skutnik, G. Westphal — INMM and ESARDA Joint Annual Meeting
Liquid-vapor equilibrium and transport phenomena in molten salt systems
J. McMurray, J. McFarlane, M. S. Greenwood, A. McAlister, M. Kurley III — TMS
Modern Techniques for Visualizing Radiation Data in Nuclear Space Scenarios
M. Smith, M. S. Greenwood — Nuclear and Emerging Technologies for Space (NETS)
Progression Problems for Validation of Species Transport Calculations for Molten Salt Reactors
A. Graham, R. Taylor, M. S. Greenwood, B. Collins — Proceedings of Fundamental Properties to Advance Molten Salt Reactor Technology
TRANSFORM: Description and Applications
M. S. Greenwood
TRANSFORM: Description and Applications
M. S. Greenwood — ORNL Software and Data Expo 2021
2020
TRANSFORMATIONAL CHALLENGE REACTOR PRECONCEPTUAL CORE DESIGN STUDIES
B. Ade, A. Wysocki, P. Jain, P. Chesser, M. S. Greenwood, K. Terrani, B. R. Betzler — Nuclear Engineering and Design
Method for Visualizing Radiation Data using Unreal Engine
M. S. Greenwood, M. Smith — ANS Winter Meeting and Nuclear Technology Expo
TRANSFORM – A Vision for Modern Advanced Reactor System-Level Modeling and Simulation Using Modelica
M. S. Greenwood — ANS Winter Meeting and Nuclear Technology Expo
Developing technology and capabilities to solve MSR off-gas challenges
K. Myhre, J. McFarlane, H. Andrews, N. D. Ezell, S. Chapel, M. S. Greenwood
Geographic Information System Mapping for Visualization of Integrated Energy Systems
D. De Wet, M. S. Greenwood
Leveraging Modern Visualization Tools for Integrated Energy System Analysis
M. S. Greenwood, T. Norby
TRANSFORM - A Vision for Modern Advanced Reactor System-Level Modeling and Simulation Using Modelica
M. S. Greenwood
Building on a legacy of nuclear modeling and simulation research
J. Ellis et al. — Nuclear News 63
2019
Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the Molten Salt Demonstration Reactor
M. S. Greenwood et al. — Nuclear Technology
A Frequency Response Approach to Model Validation for the Compact Integral Effects Test Facility in TRANSFORM
D. De Wet et al. — Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), American Nuclear Society, Portland, OR
Design and Modeling of a Liquid-Fuel Salt Experiment for the Versatile Test Reactor
M. S. Greenwood et al. — Transactions of the American Nuclear Society - Volume 121, AMNS
Linear Stability Studies of a Natural Circulation Based Small Modular Reactor
J. D. Rader et al. — Proceedings of 11th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT), Orlando, FL
Nuclear Thermal Propulsion Dynamic Modeling with Modelica
J. D. Rader et al. — Proceeding of Nuclear and Emerging Technologies for Space (NETS), Las Vegas, NV
Status Report on the MSRE Transform Model for Thermal-Hydraulic Benchmarking
M. S. Greenwood, D. De Wet — ORNL/TM-2019/1359
2018
Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors
M. S. Greenwood, B. R. Betzler — Nuclear Science and Engineering
Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion
J. D. Rader, M. S. Greenwood, P. W. Humrickhouse — Nuclear Technology
Kinetic Precursor Drift Model for Fluid-Fueled Molten Salt Reactors
M. S. Greenwood, B. R. Betzler — Proceedings of the ANS Annual Conference, Philadelphia, PA
Time-dependent Reliability Analysis of Nuclear Hybrid Energy Systems
A. G. Yigitoglu, M. S. Greenwood, T. J. Harrison — The Probabilistic Safety Assessment & Management (PSAM) Conference 14, Los Angeles, CA
Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors
M. S. Greenwood, B. R. Betzler, A. L. Qualls — ORNL/TM-2018/876
Kinetic Precursor Drift Model for Salt-Fueled Molten Salt Reactors
M. S. Greenwood, B. R. Betzler
Small Modular Reactors and the Future of Nuclear Energy
M. S. Greenwood
Increasing Revenue of Nuclear Power Plant with Thermal Storage
K. Borowiec et al.
2017
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis
N. R. Brown et al. — Ann. Nuclear Energy 103
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview
A. L. Qualls et al. — Ann. Nuclear Energy 107
Presentation and comparison of experimental critical heat flux data at conditions prototypical of light water small modular reactors
M. S. Greenwood, J. P. Duarte, M. Corradini — Nuclear Engineering and Design
Component Development for Nuclear Hybrid Energy Systems
M. S. Greenwood — 12th International Modelica Conference, Prague, Czech Republic
Control Systems for a Dynamic Multi-Physics Model of a Nuclear Hybrid Energy System
M. S. Greenwood, D. W. Fugate, S. M. Cetiner — 10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, San Francisco, CA
Nuclear Hybrid Energy System Model Stability Testing
M. S. Greenwood, S. M. Cetiner, D. W. Fugate — ORNL/TM-2017/153
Component Development for Nuclear Hybrid Energy Systems
M. S. Greenwood
Control Systems for a Multiphysics Nuclear Hybrid Energy System
M. S. Greenwood, D. Fugate, S. Cetiner
Nuclear Hybrid Energy Systems & Discretized Models
M. S. Greenwood
Nuclear Hybrid Energy Systems: Design, Simulation, Analysis and Optimization
M. S. Greenwood
Nuclear Hybrid Energy Systems Design, Modeling and Simulation, Analysis, and Optimization
M. S. Greenwood
2016
Mechanistic CHF modeling for natural circulation applications in SMR
J. Luitjens et al. — Nuclear Engineering and Design
Core design characteristics of the fluoride salt-cooled high temperature demonstration reactor
N. R. Brown et al. — International Congress on Advances in Nuclear Power Plants, San Francisco, CA, ICAPP
Summary of the Workshop on Molten Salt Reactor Technologies Commemorating the 50th Anniversary of the Startup of the Molten Salt Reactor Experiment
M. S. Greenwood et al. — International Congress on Advances in Nuclear Power Plants, San Francisco, CA
Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design
A. L. Qualls et al. — ORNL/TM-2016/85
Nuclear Hybrid Energy Systems FY16 Modeling Efforts at ORNL
S. M. Cetiner et al. — ORNL/TM-2016/418
Nuclear Hybrid Energy Systems Initial Integrated Case Study Development and Analysis
T. J. Harrison, M. S. Greenwood — ORNL/TM-2016/707
Dynamic Thermal Hydraulic Modeling TRANSFORM-ed
M. S. Greenwood
Nuclear Hybrid Energy Systems
M. S. Greenwood
2015
Study of Critical Heat Flux in Natural Convection–Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries
J. Yang et al. — Nuclear Science and Engineering
Comparison of experimental critical heat flux data to prediction methods for conditions prototypical of light water small modular reactors
M. S. Greenwood, J. P. Duarte, M. Corradini — International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Mechanistic CHF modeling for natural circulation applications in SMR
J. Luitjens et al. — US-Japan Seminar on Two-Phase Flow Dynamics, West Lafayette, IN, USA
The Critical Heat Flux at High Pressure and Low Mass Flux Prototypic of Proposed Light Water Small Modular Reactors
M. S. Greenwood — University of Wisconsin-Madison
2013
Study of Critical Heat Flux for a Four Rod Bundle at Small Modular Reactor Operating Conditions
M. S. Greenwood et al. — 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-15), Pisa, Italy
Study of Critical Heat Flux in Natural Convection Cooled TRIGA Reactors with Single Annulus and Rod Bundle Geometries
J. Yang et al. — 15th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-15), Pisa, Italy
2012
Critical heat flux in natural convection TRIGA reactors with 2×2 bundle
J. Yang, M. De Angelis, M. S. Greenwood — Transactions of the American Nuclear Society