Type of component researched under approved GAIN NE Voucher
The objective of this project is to understand heat transfer for the novel molten fuel salt pin in a molten salt core concept. Heat transfer due to natural convection driven flow is a very complex phenomenon owing to the range of active length scales.
Salt to Metal to Salt Heat Transfer in Narrow Fuel Pins Read More »
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.
ICP-MS for Analysis of Lithium Isotopic Ratios in Materials Highly Enriched in 7Li Read More »
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)).
PIE-Enabled Study of Aqueous Corrosion & Zr Hydriding in Cr-Coated Cladding Read More »
This project will address first-of-a-kind (FOAK) experimental post-irradiation examination (PIE) of irradiation-induced bowing response in SiC-SiC structures.
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).
Development of Cladding Protective coating for FOAK ARC-100 Facility Read More »
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.
Advanced Moderator Module Validation for the Alpha Tech Micro Molten Salt Reactor Read More »
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).
High Temperature Neutron Flux Detector – Reactor Testing Read More »
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.
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.
Radiation Aging of Nuclear Power Plant Components, Analysis & Measurement Services Corp. Read More »
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 »
