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.
Dynamic Natural Convection System, Dynac Systems LLC Read More »
The focus of this project is to look at the integration of small modular reactors (SMRs) for both electricity and process heat.
Assessment of Small Modular Reactors, Dow Read More »
The objective is to integrate the core and shielding analysis tools in order to design a safe and economically viable microreactor.
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.
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).
Thermal Property Measurements for an LEU-Fueled Molten Salt Reactor, Flibe Energy, Inc. Read More »
GAIN announced today that four companies will be provided a GAIN Nuclear Energy (NE) Voucher to accelerate the innovation and application of advanced nuclear technologies.
GAIN announces first round FY 2023 Nuclear Energy Voucher recipients Read More »
GAIN announced today that three nuclear companies will be provided a GAIN Nuclear Energy (NE) Voucher to accelerate the innovation and application of advanced nuclear technologies.
GAIN announces fourth round FY 2022 Nuclear Energy Voucher recipients Read More »
Elementl is evaluating dozens of locations in the U.S. for siting suitability of advanced reactor technologies.
Elementl Power LLC Read More »
TVA has begun planning an Advanced Nuclear Program and is beginning to study future deployment of advanced nuclear reactors (ANRs). This project will screen the TVA service area to help determine suitable sites for future ANR deployment.
TVA Siting Study, Tennessee Valley Authority Read More »
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.
Chlorine Nuclear Data Measurement and Evaluation, TerraPower Read More »
