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.
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®.
The High-Assay Low Enriched Uranium Demand and Deployment Options Report addresses findings and recommendations to meet HALEU demand.
HALEU Workshop Report: High-Assay Low Enriched Uranium Demand and Deployment Options Read More »
GAIN announced today that Elysium Industries, Kairos Power, Terrestrial Energy and Ultra Safe Nuclear Corp. will each receive a GAIN Nuclear Energy (NE) Voucher to accelerate the innovation and application of advanced nuclear technologies.
GAIN announces second round FY 2022 Nuclear Energy Voucher recipients Read More »
The objective of this project is to couple Serpent and Griffin to enable a thermal-hydraulics and neutronics multiphysics model of the transient scenario which will accelerate Radiant’s reactor design process.
Microreactor Control Drum Failure Simulation, Radiant Read More »
The objective of this project is to assess the RELAP5- 3D code for application to the MSRR design and licensing pathway to resolve data limitations for both the input models for the plant design and models specific to the liquid fuel molten salt core.
To broaden the understanding of fuel-clad chemical interactions (FCCI), Oklo partnered with Idaho National Laboratory (INL) to conduct an out-of-pile experimental investigation into FCCI behavior that addresses each of these variables in order to expand the operating envelopes to better align with the Aurora reactor as well as other advanced concepts.
Addressing Gaps in Legacy Data on Fuel Steel Interactions, Oklo, Inc. Read More »
The scope of this project included the design of an experiment for irradiating Lightbridge metallic fuel material samples in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL).
Framatome used failure modes and effects analysis (FMEA) to determine and define potential failure mechanisms for the U-50Zr alloy design.
Advanced Metallic U-Zr Fuel for LWR Applications – FMEA and PIRT Development, Framatome Read More »
General Electric-Hitachi, Argonne National Laboratory and the Idaho National Laboratory provided improved operational guidance for the current and advanced BWR off-gas system designs and identified off-gas system design improvements for use in BWR SMRs.
