Industry FOA Awardees

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2018 (1st Round)

The following projects were selected under the Funding Opportunity Announcement titled "U.S. Industry Opportunities for Advanced Nuclear Technology Development" (DE-FOA-0001817) - 1st round of calendar year 2018 (application due date of January 31, 2018) 

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Tier I: First of a Kind (FOAK) Nuclear Demonstration Readiness Projects

NuScale Power, LLC Logo

NuScale Power, LLC
Corvallis, OR

NuScale Small Modular Reactor First-Of-A-Kind Nuclear Demonstration Readiness Project (Phase 1) 

Initiates the first phase of a U.S. product realization effort required to bring the NuScale design to market.

NuScale Power's Phase 1 Abstract

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X Energy, LLC   Logo

X Energy, LLC
Greenbelt, MD

Design and License Application Development for TRISO-X: A Cross-Cutting, High Assay Low Enriched Uranium Fuel Fabrication Facility

Development of a High Assay Low Enriched Uranium fuel fabrication facility enabling mid-2020s deployment of all advanced reactor designs while increasing the competitiveness of the U.S. nuclear industry. This effort includes fuel requirements feasibility studies, facility preliminary and final design, and license application development and submittal - culminating in NRC acceptance and docketing.

X Energy's Abstract

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Tier II: Advanced Reactor Development Projects

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General Atomics
San Diego, CA

Combining Multi-Scale Modeling with Microcapsule Irradiation to Expedite Advanced Fuels Deployment 

Develops a fission-product release and swelling model for uranium carbide (UC) based on modeling and irradiation tests in the High Flux Isotope Reactor to assess the accuracy of the analytical models and shows how advances in multi-scale modeling can alleviate the burden of extensive irradiation experiments and reduce the cost of advanced reactor development.

General Atomics' Tier II Abstract

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NuVision Engineering, Inc.
Pittsburgh, PA

Dynamic Natural Convection - Passive Cooling For The LWR Fleet

Develops an engineered solution to redirect and use the energy of the decay heat to passively cool the reactor core, thus eliminating the need for power from off-site grids and on-site redundant power supplies and safety systems. 

NuVision Engineering's Abstract

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BWXT Nuclear Energy, Inc Logo

BWXT Nuclear Energy, Inc
Lynchburg, VA

Establishment of an integrated advanced manufacturing and data science driven paradigm for advanced reactor systems

Develops the ability to implement Additive Materials Manufacturing (AMM) to the fabrication process for nuclear components and sub-components that will yield acceptable material structure and strength that can be accepted by American Society for Testing and Materials (ASTM) and incorporated into the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) for review and acceptance by the US Nuclear Regulatory Commission.

BWXT Nuclear Energy's Abstract

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Elysium Industries USA
Clifton Park, NY

Modeling and Optimization of Flow and Heat Transfer in Reactor Components for Molten Chloride Salt Fast Reactor Application

Evaluates and optimizes the thermal-fluid performance of reactor components using computational fluid dynamics (CFD) methods. 

Elysium Industries' Abstract

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Tier III: Regulatory Assistance Grants

General Atomics Logo

General Atomics
San Diego, CA

Pre-Application License Review of Silicon Carbide Composite Clad Uranium Carbide Fuel for Long-Life Gas-Cooled Fast Reactor Cores

Determines requirements for licensing SiC/UC for use in a gas-cooled fast reactor long-life core, including the experimental database, validated performance and safety codes, and approach to licensing a prototype core.

General Atomics' Tier III Abstract

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Analysis and Measurement Services Corporation Logo

Analysis and Measurement Services Corporation
Knoxville, TN

Resolving the Regulatory Issues with Implementation of Online Monitoring Technologies to Extend the Calibration Intervals of Process Instruments in Nuclear Power Plants

Compiles, analyzes, and documents the state-of-the-art in online monitoring technology for online calibration verification of pressure, level, and flow transmitters in nuclear power plants. 

Analysis and Measurement Services Corporation's Abstract

 

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