GAIN Webinar Series – National Laboratories Capabilities Webinar

The objective of this webinar was to provide an overview of the national lab capabilities specific to demonstrating advanced nuclear energy technology.

GAIN Webinar Series: National Laboratories Capabilities Webinar

June 4, 2020

The objective of this webinar was to provide an overview of the national lab capabilities specific to demonstrating advanced nuclear energy technology.

Additional Resources

Optimization and Assessment of the Neutronics and Fuel Cycle Performance of the Transatomic Power Molten Salt Reactor Design

NE-24-34975_Sigma-Aldrich

Development of Oxygen IR Calibration Standards for High-Purity Chloride Salts

NE-24-33971_Terrestrial Energy USA Inc.

Thermogravimetric Analysis of IMSR Fuel Salt Simulants

NE-23-32134_Metatomic

Metomic Molten Salt Immersed Hydrochlorination Subsystem Characterization

Salt to Metal to Sal Heat Transfer in Narrow Fuel Pins

NE-23-31236_Kairos Power

ICP-MS for Analysis of Lithium Isotopic Ratios in Materials Highly Enriched in 7Li

NE-23-31247_Alpha Tech

Advanced Moderator Module Validation for the Alpha Tech Micro Molten Salt Reactor

Molten Salt Reactors

Electroanalytical Sensors for Liquid Fueled Fluoride Molten Salt Reactor Abstract

NE-23-29866_Flibe Energy

Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor

NE-25-36449_Kairos Power

Development of Analytical Techniques for Trace Impurities in 2LiF-BeF2

Verification of Molten-Salt Properties at High Temperatures

Legacy Metal Fuel Data Exploration for Commercial Scale-Up

Fuel Salt Characterization

Fuel Salt Characterization for the Transatomic Power Molten Salt Reactor

IMSR Fuel Salt Property Confirmation Thermal Conductivity and Viscosity

IMSR Fuel Salt Property Confirmation Thermal Conductivity and Viscosity

Evaluation of Power Fluidic Pumping Technology for Molten Salt Reactor Applications

Evaluation of Power Fluidic Pumping Technology for Molten Salt Reactor Applications

NE-25-37807_TerraPower

Thermophysical Property Measurements of NaCl-KCl-UCl3

BNNT Materials Abstract FINAL 26.4

Validation of BNNT Gaskets for High-Temperature Molten Salt Nuclear Systems

NE-23-32134_Metotomic

NE-23-31236_Kairos-Power

Nuclear Waste Management Strategy for Molten Salt Reactor Systems

Experimental Validation of Nondestructive Assay Capabilities for Molten Salt Safeguards FY20

Online Monitoring for Molten Salt Reactor and Matieral Control & Accounting

Molten Salt Reactor Safeguards Modeling

Materials Control & Accounting for Molten Salt Reactors

Conversion of Light Water Reactor Spent Nuclear fuel to Fluoride Salt Fuel

NE-25-37676_NaturaResources

Molten Salt Nuclear Graphite Qualification Plan

NE-20-23946_KairosPower

Pebble Bed Large Eddy Simulations for Lower Order Methods Benchmarking and Uncertainty Quantification Development

NE-20-23935_Natura Resources.1

RELAP5-3D Development and Assessment for Liquid-fueled Molten Salt Reactor Licensure

NE-23-29866_Flibe Energy

Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor

NE-21-25117_TerraPower

NE-19-18706_FlibeEnergy

Metal Organic Frameworks for Noble Gas Management in the Lithium Fluoride Thorium Reactor

RFA-18-15820_ThorConUSA

Electroanalytical Sensors for Liquid Fueled Fluoride Molten Salt Reactor

RFA-17-14589_Muons

Conversion of LWR Spent Nuclear Fuel to Fluoride Salt Fuel

Domestic Safeguards Material Control and Accountancy Considerations for Molten Salt Reactors

Thermophysical Properties Measurements of NaCl-PuCl3

RELAP5-3D Development and Assessment for Liquid-fuels Molten Salt Reactor Licensure

Pebble Bed Large Eddy Simulations for Lower Order Methods Benchmarking and Uncertainty Quantification Development

Density Measurements of Plutonium Bearing Salts via Neutron Beam Dilatometry

Deployment of Advanced Electroanalytical Sensors in the Kairos Power Engineering Test Unit (ETU)

Chlorine Nuclear Data Measurement and Evaluation

Investigation of the Structural Integrity and Corrosion Resistance of Surface Treatment on Alloy-709 in a Molten Fluoride Salt Environment

Advanced Functional Membrane Testing for Noble Gas Management in a Molten Salt Reactor

Evaluation of Optical Techniques for Molten Salt Reactor Materials Control and Accounting

Thermophysical Properties Measurements of NaCl-PuCl3

Molten Salt Reactor Signatures And Modeling Study

Experimental Validation of NDA Capabilities for Molten Salt Reactors

Flow Enhanced Electrochemical Sensors for Molten Salt Reactors Presentation by Argonne National Lab

Flow Enhanced Electrochemical Sensors for Molten Salt Reactors

Advanced Safeguards and Securities Workshop Overview

Treatment of Uncertainty in a Risk-Informed Licensing Approach

Advanced Reactor Safeguards: Program Overview

Performance of DMA Fused Radar and Video

Small Modular Reactor Security by Design and Analysis

Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium

Development of the Microscale Nuclear Battery Reactor System

Development of the Microscale Nuclear Battery Reactor System

NEAMS Nuclear Energy Advanced Modeling and Simulation Program ThermalFluids Test Stand

NEAMS Nuclear Energy Advanced Modeling and Simulation Program ThermalFluids Test Stand

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel

Synthesis of Molten Chloride Salt Fast Reactor Fuel Salt from Spent Nuclear Fuel

Quantify Sodium FluorideBeryllium Fluoride Salt Properties for Liquid Fueled Fluoride Molten Salt Reactors

Quantify Sodium Fluoride/Beryllium Fluoride Salt Properties for Liquid Fueled Fluoride Molten Salt Reactors

Domestic Safeguards Material Control and Accountancy Considerations for Molten Salt Reactors

Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium

Chemical Method Development for Quantifying Oxygen in Beryllium Salt

Chemical Method Development for Quantifying Oxygen in Beryllium Salt

Develop ASME Section III Division 5 Design Rules for Elevated Temperature Cladded Class A Type 316 Stainless Steel Components

Develop ASME Section III Division 5 Design Rules for Elevated Temperature Cladded Class A Type 316 Stainless Steel Components

Liquid Fluoride Thorium Reactor (LFTR) Preliminary Safeguards Assessment

Liquid Fluoride Thorium Reactor (LFTR) Preliminary Safeguards Assessment

Metal Organic Frameworks for Noble Gas Management in the Liquid Fluoride Thorium Reactor