The 2024 conference was hosted by Sandia National Laboratory in Albuquerque, New Mexico.
Plenary Session
- Opening Remarks, Announcements, and Welcome – Bryan Oliver
- Design, Build, Test, Repeat: A Novel Approach to Delivering Advanced Reactor Technology – Ed Blandford
Session 1A
- Establishing Radiation Safety Culture at the Nuclear Engineering & Science Center – Abby Kurwitz
- Nuclear Reactor and Non-Reactor Operator/Supervisor Training Improvements – Lance Lippert
- Operating Experience Program and Rapid Iterative Approach to Reactor Deployment – Peiwen Whysall
Session 1B
- A reactor-based Intense Positron Source – Van Herd
- Restarting from scratch: Waking up MITR-II’s Nuclear Instrumentation – Dane Kouttron
- Designing a Water-Tight Torlon Container for Medical Isotope Production Using the Central Thimble of the NETL Nuclear Research Reactor – William Charlton
Session 2A
- Twelve Memorable Quotes that Assist in Describing Status of Reactor and Relationships – David Slaughter
- Benchmarking and Sensitivity Analysis of the UNM AGN-201M – Rowdy Davis
- Hermes Demonstration Reactor, Modeling and Startup Physics Testing Synergism – Nader Satvat
- The Eden All-Target Reactor and Integrated Hot Cell Facility for the Production of Medical Radioisotopes – Ed Parma
Session 2B
- Development of a Thermal to 14 MeV Neutron Conversion Screen for The Annular Core Research Reactor Facility (ACRRF) Using Enriched Lithium Deuteride – Tracy Spoerer
- Lessons Learned from Participation in the IAEA Proficiency Tests for Nuclear Analytical Techniques – Luke Gilde
- The Advanced Dimensional Depletion for Engineering of Reactors (ADDER) software: Software Overview and Future Developments – Christian Castagna
- Benchmark Experiments at the Sandia Pulsed Reactor Facility – Critical Experiments (SPRF/CX) – David Ames
Session 3A
- Reactor Tank Leak Finding With Rhodamine Dye – Ted Goodell
- Use of Indirect Neutron Radiography to Image Spent Fuel at the Annular Core Research Reactor – Sophia Brodish
- Separate Operating Issues Caused by Operator Error and Mechanical Failure – Steve Reese
- Transition from Film Based Radiography to Digital Image Acquisition for the Commercial Imaging of Pyrotechnic Devices – Wes Frey
- Design, installation, and performance of a third generation mesitylene based cold neutron source at the Penn State Breazeale Reactor – Daniel Beck
- Utah Reactor Tank Repair – Andrew Allison
Session 3B
- 2024 Status Report University Fuel Services Program – Doug Morrell
- Challenges in Research Reactor Simulator Acquisition: Lessons Learned – Majd Zaker
- Overcoming Unique Challenges in the Return to Service of NIST NBSR – David Cisclo
- Demonstration of Advanced Encryption for an Instrumentation and Control System Using ARCADE – Daniel Cole
- Overview of the Molten-salt Research Temperature-controlled Irradiation (MRTI) Experiment at the NRAD Reactor – Steven Pappas / Charles Jones
- Corrective Action Programs for Research Reactors – A Real Life Example – Randy Strader
NRC Presentations
- Perspectives on the Future of NPUF Regulations – Andrea Veil
- Advanced Reactor Landscape and the Importance of RTRs – Josh Borromeo
- Non-power Production or Utilization Facility (NPUF) License Renewal Rulemaking – Holly Cruz
- Non-Power Production and Utilization Facility Licensing Branch – Overview – Holly Cruz
- Overview of NPUF Oversight Program – Travis Tate
Session 4
- A Novel Method of Extracting Real-Time Reactor Console Data – Jacqueline Cottingham / William Charlton
- Design Overview of Natura Resources MSR-1 – Brazos Fitch
- Capturing Pulse Data on a Pulsing Reactor – Randy Hyde
- Design Optimizations of the NuScale Microreactor for High Thermal Neutron Fluxes – Jackson Keppen
- Improved Power Indication in the Advanced Test Reactor – Nathan Manwaring
- Implementation of a New Digital Console at the PSU Breazeale Reactor – Jeff Geuther / Adams Tong
- Control System Upgrade for the University of Texas TRIGA II Reactor – Paul Whaley
- Advances in Research and Test Reactor Plate Stability for LEU Conversion – Erik Wilson
Plenary
Session 5A
- NBSR Safety Classification of Structures, Systems and Components – Yaniv Shaposhnik / Dagistan Sahin
Session 5B
- Evaluating Detection Capabilities of Irradiated Methylammonium Lead Iodide Perovskite Crystals – Coleman Smith
- USGS TRIGA Aluminum-Clad Fuel Condition – Clayton Manning
- USGS TRIGA Reactor Fuel Element Measurement Tool – Chris Farwell
Session 6A
- Hermes Demonstration Reactor, Modeling and Startup Physics Testing Synergism – Nader Satvat
- Preliminary Design Considerations for MITR-III – Sara Hauptman
- Addressing Unclad and Unidentified Fissile Material in Highly Radioactive Debris – Dagistan Sahin
- PULSTAR Utilization and Irradiation Testing Capabilities for Advanced Reactor Research – Austin Wells
Session 6B
- USGS TRIGA Reactor Fuel Configurations and History – Jonathan Wallick
- Licensing of the Abilene Christian University Molten Salt Research Reactor – Benjamin Beasley
- ETU 1.0 Lessons Learned – Andrew Williamson
