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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Graphite Finite Element Model Verification, Ultra Safe Nuclear Corporation
The benchmarks, analytical solutions, and failure criteria developed during this project will be used directly by USNC-Tech to evaluate the current graphite core design of the MMR™ reactor, resulting in an optimized core and a down-selection of the graphite used for the core.
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Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor Using VERA-CS, SMR, LLC
The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.
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Addressing Gaps in Legacy Data on Fuel Steel Interactions, Oklo, Inc.
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.
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Combined Effects Testing of High- Temperature and Neutron Fluence to Support the Qualification of NE-300, a High-Temperature Neutron Shielding Material, Neutroelectric, LLC
Neutroelectric and Oak Ridge National Laboratory will perform critical combined tests at the High Flux Isotope Reactor in support of qualification of this new material, NE-300, for use in commercial nuclear reactor applications.
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Advanced Test Reactor Experiment Design for Measurement of Lightbridge Fuel™ Thermophysical Properties, Lightbridge Corp.
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).
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Advanced Coolant and Moderator Enclosure Solutions for Micro Gas Cooled Reactors with Enhanced Efficiency and Safety, HolosGen, LLC
HolosGen, LLC with assistance from Argonne National Laboratory (ANL) will develop advanced coolant sleeve and moderator enclosure solutions for the Holos-Quad micro-gas cooled reactor (GCR) concept operating at high temperatures.
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Testing of I&C Sensors and Cables for Small Modular Reactors, Analysis & Measurement Services Corp
The objective of this project was to use the thermal hydraulics laboratory and vacuum test chambers at Oak Ridge National Laboratory (ORNL) for response characterization of resistance temperature detectors and thermal aging of instrumentation and control (I&C) cables in vacuum to generate more useful data for I&C cable derating purposes.
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Improvements to SAS4A Severe Accident Modeling Capabilities to Support Licensing and Commercialization of TerraPower’s Traveling Wave Reactors, TerraPower, LLC.
TerraPower and Argonne National Laboratory (ANL) will develop additional capabilities within the SAS4A code that analyzes a postulated severe accident leading to coolant boiling and/or fuel failure.
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Nuclear Material Holdup Modeling and Measurement Campaign for the Columbia Fuel Fabrication Facility, Westinghouse Electric Co.
Westinghouse Electric Company and Oak Ridge National Laboratory designed and performed an experiment to develop a non-destructive assay measurement method that addressed the challenges of the volumetric deposits within the large ventilation system housings.
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Develop ASME Section III Division 5 Design Rules for Elevated Temperature Cladded Class A Type 316 Stainless Steel Components, Kairos Power
Kairos collaborated with Argonne National Laboratory (ANL) to develop design rules and associated materials data for the design of cladded components made of Type 316 stainless steel and cladded by non-code qualified corrosion resistant materials.
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Liquid Fluoride Thorium Reactor (LFTR) Preliminary Safeguards Assessment, Flibe Energy
The objective of this project was to provide FEI with design recommendations for the implementation of nuclear material accountancy and enable FEI to meet its sustainability and operational goals for the LFTR.