Past Voucher Awards
The successes and significant contributions of past GAIN NE voucher recipients have real-world impacts on our energy future. GAIN is proud to provide these nuclear innovators with a single point of access to the broad range of capabilities — people, facilities, materials, and data — across the Department of Energy’s complex and its National Lab capabilities.
Past Voucher Recipients
Categories
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ICP-MS for Analysis of Lithium Isotopic Ratios in Materials Highly Enriched in 7Li
The goal of this project would be to evaluate performance capabilities of instruments and develop standardized hardware configurations and operating procedures to analyze lithium isotopic ratios to support production of Flibe coolant that is highly enriched in 7Li.
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PIE-Enabled Study of Aqueous Corrosion & Zr Hydriding in Cr-Coated Cladding
The objective of this project is to enhance understanding of aqueous corrosion and hydrogen transport for Zr hydride formation in Cr-coated claddings, as a function of the Cr-coating deposition method (cold spray (CS) or physical vapor deposition (PVD)).
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Post-Irradiation Examination to Quantify Irradiation-Induced Bowing of SiGA® Silicon Carbide Composite Structures
This project will address first-of-a-kind (FOAK) experimental post-irradiation examination (PIE) of irradiation-induced bowing response in SiC-SiC structures.
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Development of Cladding Protective coating for FOAK ARC-100 Facility
This project will support the qualification of ARC’s fuel, by demonstrating the potential use of a barrier on the cladding to prevent fuel cladding chemical interaction (FCCI).
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Advanced Moderator Module Validation for the Alpha Tech Micro Molten Salt Reactor
The ARC Reactor is a thermal spectrum molten salt microreactor that uses low-enriched uranium fuel and operates at the high temperature of 600°C. Alpha Tech has identified YH2-x as an exceptional moderator that experiences little to no swelling.
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High Temperature Neutron Flux Detector – Reactor Testing
Ultra has developed a prototype detector but to complete the anticipated testing program for the prototype detector and demonstrate suitable operation at reactor flux levels, the detector requires testing at fluxes equivalent to those typically seen in power reactor operation (1E10 – 1E11nv).
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Redox Potentials for Proliferation-Hardened Actinide Recovery in NuCycle, Curio Solutions
The project will acquire reduction potentials for NuCycle’s electrolysis process that will allow: (1) the implementation of safeguards by design, and (2) the generation of a coextracted actinide product meeting recycle specifications.
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Radiation Aging of Nuclear Power Plant Components, Analysis & Measurement Services Corp.
Under this voucher, AMS performed radiation aging of two temperature and two pressure sensors at the Gamma Irradiation Facility of the High Flux Isotope Reactor at the Oak Ridge National Laboratory.
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Dynamic Natural Convection System, Dynac Systems LLC
This Gateway for Accelerated Innovation in Nuclear voucher paired DYNAC Systems with Idaho National Laboratory to evaluate the company’s Dynamic Natural Convection (DNC) system.
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Assessment of Small Modular Reactors, Dow
The focus of this project is to look at the integration of small modular reactors (SMRs) for both electricity and process heat.
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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.
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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.
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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).
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Criticality Safety Evaluation of NuCycle™, Curio Solutions
The project will evaluate the criticality safety limits of the conceptual equipment designs for NuCycle™.
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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.