Advanced Reactor Archives

Development of Casting Techniques for ẟ-phase Uranium-Zirconium Alloys, Lightbridge Corp

The casting, processing, and shipping of HALEU alloys, like those being developed by Lightbridge, require the ability to experiment with higher temperatures in a facility that can perform these functions. The goal of this project was to identify an appropriate casting method (i.e., crucible and coating combination) that results in an acceptable impurity concentration in the as-cast ingot.

Development of Casting Techniques for ẟ-phase Uranium-Zirconium Alloys, Lightbridge Corp Read More »

Improvements to Passive Heat Removal Systems in SAS4A/SASSYS-1

For this project, ARC will work with Argonne National Laboratory (ANL) to enhance the SAS modeling capabilities for passive heat removal systems, including the generic RVACS model and the DRACS heat exchanger models. These enhancements will enable ARC to recover safety margins and have a better representation of the system’s response during long-term cooling events.

Improvements to Passive Heat Removal Systems in SAS4A/SASSYS-1 Read More »

Independent Code-to-Code Verification of Aalo-1 Fuel and Core Performance

Aalo will partner with Idaho National Laboratory (INL) to perform independent analyses on fuel performance using the BISON code as well as thermal-hydraulics using RELAP5-3D. This work will support the independent code-to-code verification to support Aalo’s future licensing efforts.

Independent Code-to-Code Verification of Aalo-1 Fuel and Core Performance Read More »

An Advanced Multiphysics Simulation Capability for Radiant’s Microreactor Design and Shielding Analysis, Radiant Industries Inc.

The objective is to integrate the core and shielding analysis tools in order to design a safe and economically viable microreactor.

An Advanced Multiphysics Simulation Capability for Radiant’s Microreactor Design and Shielding Analysis, Radiant Industries Inc. Read More »

Experimental and Software Validation of Integral Thermal-Hydraulic Behavior in Fuel Assemblies, Oklo Inc.

This project seeks to address 1) pressure drop behavior of a typical sodium fast reactor fuel assembly with an orifice device and 2) orifice device onset of cavitation.

Experimental and Software Validation of Integral Thermal-Hydraulic Behavior in Fuel Assemblies, Oklo Inc. Read More »

Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor, Flibe Energy, Inc.

This project seeks to model and experimentally confirm the composition of two known salt systems (LiF-NaF-UF4 and LiF-NaF-ThF4) as the fuel and blanket salt for Flibe’s Lithium Fluoride Low-Enrichment Uranium Reactor (LFLEUR).

Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor, Flibe Energy, Inc. Read More »

Chlorine Nuclear Data Measurement and Evaluation, TerraPower

This project will perform new measurements of 35Cl(n,p), analyze the experimental data from these measurements, generate new 35Cl and 37Cl cross-section evaluations in ENDF/B format, and assess the impacts of the expected changes to chlorine nuclear data by comparing analysis of MCRE with updated cross-section libraries to results with existing nuclear data.

Chlorine Nuclear Data Measurement and Evaluation, TerraPower Read More »

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

The objective of this project is to evaluate a metalorganic framework (MOF) for continuous separation of Xe and Kr from the off-gas in the FCMSR in order to optimize the noble gas management of the FC-MSR and chemical processes for fuel salt production and conditioning and support the safety and licensing bases.

Advanced Functional Membrane Testing for Noble Gas Management in a Molten Salt Reactor, Elysium Industries Read More »

Support for Analysis of USNC Micro Modular Reactor Fuel Performance, Ultra Safe Nuclear Corp.

This project will include the analysis of fuel performance under Micro Modular Reactor (MMR) operating conditions and assess if using recycled uranium in Fully Ceramic Microencapsulated (FCM) fuel is viable.

Support for Analysis of USNC Micro Modular Reactor Fuel Performance, Ultra Safe Nuclear Corp. Read More »

Investigation of the Structural Integrity and Corrosion Resistance of Surface Treatment on Alloy-709 in a Molten Fluoride Salt Environment, Terrestrial Energy USA, Inc.

This project seeks to perform baseline studies on surface-treated A709 for corrosion resistance and mechanical properties to understand long-term corrosion protection when subject to periods of sustained and cyclic loading at high temperatures and its potential use in the IMSR®.

Investigation of the Structural Integrity and Corrosion Resistance of Surface Treatment on Alloy-709 in a Molten Fluoride Salt Environment, Terrestrial Energy USA, Inc. Read More »