GAIN-EPRI-NEI Advanced Fuels Workshop
The purpose of the GAIN-EPRI-NEI Advanced Fuels Workshop was to connect advanced reactor designers with DOE national laboratory nuclear fuel expertise.
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Year
GAIN-EPRI-NEI’S Workshop about Economics-Based R&D for Nuclear Power Construction
The purpose of the GAIN-EPRI-NEI’s Workshop about Economics-Based R&D for Nuclear Power Construction was to present the latest economic-related research on the costs associated with constructing nuclear power plants; and, to spur discussion and solicit input about EPRI’s current project titled, Economic Based R&D Roadmap for New Nuclear Power.
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Chemical Method Development for Quantifying Oxygen in Beryllium Salts, Kairos Power
The goal of this project was to develop a method for analyzing the oxygen content using a commercial inert gas fusion analyzer. This included the development of a calibration curve for the method, quantification of its performance, and testing on FLiBe samples from several sources, including ORNL-produced FLiBe as well as Kairos Power Flibe.
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Enabling System Technologies to Improve the Economics and Performance of Existing LWRs and Advanced BWR Plants: Improving Off-gas System Performance, General Electric-Hitachi
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.
Advanced Fuel Stability Analysis Using High-Fidelity LARGE-SCALE Computational Fluid Dynamic Simulations, Framatome
The objective of this project was to improve nuclear power generation’s safety and competitiveness by providing robust information about the flow patterns and formations throughout the simulated fluid domain.
Plasma Separation Process Feasibility Study for the Commercial Enrichment of Gadolinium-157, Exelon Generation
The objective of this project was to determine if currently available technology can be used to modernize the PSP to a level of cost-effectiveness to realize the potential cost saving in the nuclear fuel cycle.
Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium, Elysium Industries
Elysium intended to demonstrate the viability, safety, and economic improvement of using spent nuclear fuel and plutonium in molten chloride salt fast reactor fuel salt. A main objective was to eliminate waste and close the fuel cycle, thereby minimizing proliferation, in addition to providing dispatchable power complementary to renewables.
Integrated Nuclear Hybrid Energy System, Eastman Chemical Co.
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.
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Development and Testing of Alumina-forming Austenitic Stainless Steels for Lead Fast Reactor, Westinghouse Electric Co.
Oak Ridge National Laboratory (ORNL) worked with Westinghouse Electric Co. to optimize AFA steels for applications specific to LFRs, as reliable materials for key components such as fuel rod cladding, heat exchangers, reactor internals and the reactor vessel.
Nuclear Cybersecurity Initiative, NexDefense Inc.
This project will enable NexDefense to evaluate their existing software on a production nuclear test bed, hence laying the path for future commercial adoption.
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