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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Chris Wagner: The role of Eden Radioisotopes in the future of nuclear medicine
Chris Wagner has more than 40 years of experience in nuclear medicine, beginning as a clinical practitioner before moving into leadership roles at companies like Mallinckrodt (now Curium) and Nordion. His knowledge of both the clinical and the manufacturing sides of nuclear medicine laid the groundwork for helping to found Eden Radioisotopes, a start-up venture that intends to make diagnostic and therapeutic raw material medical isotopes like molybdenum-99 and lutetium-177.
Results 1 to 40 of 40
Session
ART/NEAMS Modeling and Simulation – Pebble Bed Reactors
Workshop
Sunday, April 21, 2024|8:00AM–12:00PM PDT
ART/NEAMS Modeling and Simulation – Molten Salt Reactors
Sunday, April 21, 2024|1:00–5:00PM PDT
Paper
Verification and Validation Activities of Molten Salt Reactors Multiphysics Coupling Schemes at Idaho National Laboratory
Mustafa K. Jaradat (INL), Namjae Choi (INL), Mauricio Tano Retamales (INL), Sebastian Schunert (INL), Abdalla Abou Jaoude (INL), Javier Ortensi (INL)
International Conference on Physics of Reactors (PHYSOR 2024)
Reactor Design and Analysis|Molten Salt Reactors Design and Core Analysis
Monday, April 22, 2024|3:30–5:15PM PDT
Preliminary Analysis of a Nuclear-Grade Sandwich Composite for Transportable Microreactor Shielding
Ryan H. Stewart (INL), Samuel E. Bays (INL), Adam X. Zabriskie (INL), Joshua N. Zelina (INL), Abderrafi M. Ougouag (INL), Robert C. O'Brien (INL)
Experimental Reactor Physics|Nuclear Criticality and Safety: III
Wednesday, April 24, 2024|3:30–5:15PM PDT
Computational Reactor Physics Methods to Support I&C
Technical Session|Panel
Brendan M. Kochunas, Vivek Agarwal, Richard B. Vilim
Panelists: Dianne Ezell (ORNL), Richard Vilim (ANL), Vivek Agarwal (INL), Shawn Stafford (Westinghouse Electric Co.)
Panels
Wednesday, April 24, 2024|1:30–3:15PM PDT
LDR Lite Benchmark: Coupled 3D Neutronics and Thermal-Hydraulics Analysis of a Control Rod Drop Transient
Rebekka Komu (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland), Riku Tuominen (VTT Technical Research Centre of Finland), Seppo Hillberg (VTT Technical Research Centre of Finland)
Reactor Design and Analysis|Light-Water Reactors Design and Core Analysis: III
Wednesday, April 24, 2024|10:15AM–12:00PM PDT
Prediction of the TREAT Facility Power and Temperature of Sirius-2c Nuclear Propulsion Fuel Experiment
Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Frederick N. Gleicher (INL), Mark DeHart (INL)
Experimental Reactor Physics|Research Reactors for Reactor Physics Analysis and Simulation: I
Monday, April 22, 2024|1:30–3:15PM PDT
Thermal Analysis of the Sirius-3 Nuclear Propulsion Fuel Experiments
Frederick N. Gleicher (INL), Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Mark DeHart (INL)
Reactor Design and Analysis|Fuel-Cycle Physics and Scenarios
Tuesday, April 23, 2024|1:30–3:15PM PDT
Pressurized-Water Reactor Core Design Using Multiobjective Plant Fuel Reload Optimization Platform
Junyung Kim (INL), Mohammad G. Abdo (INL), Congjian Wang (INL), Yong-Joon Choi (INL), Juan Cristhian Luque Gutierrez (NCSU), Jason Hou (NCSU)
Methods|Reactor Physics Methods in Control and Optimization Problems
Tuesday, April 23, 2024|3:30–5:15PM PDT
Long Time Scale Multiphysics Simulation of Spent Nuclear Fuel Canister in MOOSE
Rodrigo de Oliveira (INL), Joshua Hanophy (INL), Paolo Balestra (INL), Derek Gaston (INL)
Investigation of Ring-Heterogeneous Geometry Approximation for Efficient and Practical SFR Analysis
Namjae Choi (INL), Stefano Terlizzi (INL), Yaqi Wang (INL), Hansol Park (ANL), Changho Lee (ANL), Javier Ortensi (INL)
Methods|Multi-Physics Reactor Simulations and Validation: I
Monday, April 22, 2024|10:15AM–12:00PM PDT
Multiphysics Pebble-Bed Reactor Run-In Simulation Using a High-Fidelity Neutronics--Thermal Hydraulics Framework
R. Stewart (INL), J. Cavaluzzi (INL), P. Balestra (INL), G. Strydom (INL)
Reactor Design and Analysis|Pebble-bed Reactors Design and Core Analysis: I
Initial Demonstration of New Griffin Capability for Simulating the Running-In Phase of Pebble-Bed Reactors with Multiphysics
Joshua Hanophy (INL), Javier Ortensi (INL), Paolo Balestra (INL), Yaqi Wang (INL)
Reactor Design and Analysis|Advanced Reactors Design and Core Analysis: I
Status of the ICSBEP, IRPhE, SFCOMPO, and SINBAD Benchmark Handbooks
Christopher M. Perfetti, Mark D. DeHart, Catherine M. Percher
Panelists: Mark DeHart (INL), Germina Ilas (ORNL), Thomas Miller (ORNL), Rowdy Davis (UNM)
Development of a Steady State Reactor Physics Surrogate Model for the Idaho State University AGN-201 Digital Twin Using MOOSE
Quinton J. Williams (Oregon State), Ryan H. Stewart (INL), Todd S. Palmer (Oregon State), Camille J. Palmer (Oregon State), Chad Pope (Idaho State), Ashley Shields (INL), Christopher Ritter (INL)
Fuel Cycle and Other Applications|Nonproliferation and Safeguards, Accident Dose Analysis and Reactor Physics Analyses for Externally Driven Systems
Quantifying Uncertainties: Evaluating the Impact of Molten Salt Thermal Property Variability on Reactor Operation
Davide Rotilio (Univ. California, Berkeley), Mauricio Tano (INL), Abdalla Abou-Jaoude (INL), Samuel Walker (INL), Massimiliano Fratoni (Univ. California, Berkeley), Renato Gatto (Sapienza Univ. di Roma)
Methods|Multi-Physics Reactor Simulations and Validation: IV
Tuesday, April 23, 2024|10:15AM–12:00PM PDT
Coarse Mesh Finite Difference Acceleration for Pebble Tracking Transport in Griffin
Yaqi Wang (INL), Joshua Hanophy (INL), Namjae Choi (INL)
Methods|Methods for Reactor Physics Analyses: X
Recent Advanced Reactor Multiphysics Model Highlights in the Virtual Test Bed (VTB)
Abdalla Abou-Jaoude (INL), Guillaume Giudicelli (INL), Samuel Walker (INL), Emily Shemon (ANL), Hansol Park (ANL), Yiqi Yu (ANL), Nicolas Stauff (ANL)
Methods|Multi-Physics Reactor Simulations and Validation: V
Micro-Reactors Design and Core Analysis: I
Technical Session
Abdalla Abou-Jaoude (INL), Mauricio Tano Retamales (INL), Stefano Terlizzi (INL)
Reactor Design and Analysis
Deterministic High-Fidelity Neutronics Simulation of Pebble Bed Reactors with Pebble Tracking Transport
Liam Carlson (TAMU), Jean Ragusa (TAMU), Paolo Balestra (INL), Yaqi Wang (INL)
Reactor Design and Analysis|Pebble-bed Reactors Design and Core Analysis: II
LDR Lite Benchmark: Description of the Core Model
Riku Tuominen (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland)
Reactor Design and Analysis|Light-Water Reactors Design and Core Analysis: I
Progress Toward the Development of a High-Fidelity Neutronic Model of MARVEL Using Griffin
S. Terlizzi (INL), I. Trivedi (INL)
Reactor Design and Analysis|Micro-Reactors Design and Core Analysis: II
Initial Assessment of Online Cross Section Generation Capability of Griffin for Gas-Cooled Pebble-Bed Reactor
Hansol Park (ANL), Yeon Sang Jung (ANL), Changho Lee (ANL), Yaqi Wang (INL), Javier Ortensi (INL)
Methods|Methods for Reactor Physics Analyses: II
Pushing the Envelope for Irradiation Powers and Duration at the Advanced Test Reactor
Nathan Manwaring (INL), Solmayra Flores (INL)
OECD NEA Activities Related to Scientific Issues of Nuclear Reactor Systems
Scott P. Palmtag, Jason Hou
Panelists: Laurent Buiron (CEA), Oliver Buss (NEA/OECD), Gregory Delipei (NCSU), Gerhard Strydom (INL)
Generative AI for Reactor Physics
Majdi I. Radaideh, Carlo Fiorina
Panelists: Isaac Michaud (LANL), Oliver Buss (OECD/NEA), Scott Sidener (Westinghouse Electric Co.), Guillaume Giudicelli (INL)
Sensitivity of Thermo-Physical Salt Property Changes on Reactor Equilibrium for Salt-Cooled Pebble Bed Reactors
Ludovic Jantzen (Univ. California, Berkeley), Mauricio E. Tano (INL), Massimiliano Fratoni (Univ. California, Berkeley)
Griffin's Depletion Calculation of Molten Salt Reactor Experiment
D. Hartanto (ORNL), E. Davidson (ORNL), Y. Cao (ANL), T. Fei (ANL), M. Tano-Retamales (INL)
Extending MOOSE Capabilities with Discrete and Combinatorial Shape and Topology Optimization for Nuclear Engineering Applications
Muhammad Ramzy Altahhan (NCSU), Sebastian Schunert (INL), Yousry Azmy (NCSU)
Implementation of Unresolved Resonance Region Probability Tables in the GNDS Format
M.-A. Descalle (LLNL), C.M. Mattoon (LLNL), M.S. McKinley (LLNL), J. Northrop (Oregon State), G. Gert (LLNL), B.R. Beck (LLNL), A. Dreyfuss (LLNL)
Methods|Data, Methods, Code Validation: III
Dynamics and Stability Analysis Study of a Thermal Molten Salt Reactor
Thabit Abuqudaira (TAMU), Ümran Üzen (TAMU), Dahvien Dean (TAMU), Pavel Tsvetkov (TAMU), Piyush Sabharwall (INL)
Reactor Design and Analysis|Advanced Reactors Design and Core Analysis: II
Micro-Reactors Design and Core Analysis: II
Stefani Terlizzi (INL), Abdalla Abou-Jaoude
Designing Reactors for Integrated Energy Systems and Space Nuclear Reactors Design and Core Analysis
Yan Cao (ANL), Ishita Trivedi (INL)
Methods for Reactor Physics Analyses: II
Paolo Vinai (Chalmers Univ. Technology), Jaako Leppanen (VTT Technical Research Centre of Finland)
Methods
Methods for Reactor Physics Analyses: VI
John Tramm (ANL), Ville Valtavirta (VTT Technical Research Centre of Finland)
Multi-Physics Reactor Simulations and Validation: II
Mathieu Hursin (École Polytechnique Fédérale de Lausanne), Javier Ortensi (INL), Romain Henry (GRS)
Multi-Physics Reactor Simulations and Validation: V
Guillaume Giudicelli (INL), Emily R. Shemon
Organization Participant
Idaho National Laboratory
Sponsor & Exhibitor Profile
Scientific Machine Learning for Nuclear Engineering Applications
Core Level SMR Simulations with the Kraken Framework
