Scott Greenwood Reactor Systems Modeling and Safety Analysis Staff Member Contact GREENWOODMS@ORNL.GOV All Publications Increasing Revenue of Nuclear Power Plants With Thermal Storage CANDIDATE CORE DESIGNS FOR THE TRANSFORMATIONAL CHALLENGE REACTOR... Status Report on the MSRE TRANSFORM Model for Thermal-Hydraulic Benchmarking Design and Modeling of a Liquid-Fuel Salt Experiment for the Versatile Test Reactor... Advanced Manufacturing for Nuclear Core Design A FREQUENCY RESPONSE APPROACH TO MODEL VALIDATION FOR THE COMPACT INTEGRAL EFFECTS TEST FACILITY IN TRANSFORM Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the ... Dynamic System Models for Informing Licensing and Safeguards Investigations of Molten Salt Reactors – Revision 1 Linear Stability Studies of a Natural Circulation–Based Small Modular Reactor Nuclear Thermal Propulsion Dynamic Modeling with Modelica Modified Point-Kinetics Model for Neutron Precursors and Fission Product Behavior for Fluid-Fueled Molten Salt Reactors Time-Dependent Reliability Analysis of Nuclear Hybrid Energy Systems Molten Salt-Fueled Nuclear Reactor Model for Licensing and Safeguards Investigations Kinetic Precursor Drift Model for Fluid-Fueled Molten Salt Reactors Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion... Nuclear Hybrid Energy System Reliability Model Progress Report Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety analysis Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Supervisory Control System for Multi-Modular Advanced Reactors Supervisory Control System for Multi-Modular Advanced Reactors... Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Advanced Reactor Systems Group
