Posts from 2023
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 »
The Gateway for Accelerated Innovation in Nuclear (GAIN) announced today that seven companies will be provided a GAIN Nuclear Energy (NE) Voucher to accelerate the innovation and application of advanced nuclear technologies. NE vouchers provide advanced nuclear technology innovators with access to the extensive nuclear research capabilities and expertise available across the U.S. Department of Energy (DOE) national laboratory complex. This is the third award for FY 2023.
GAIN announces third round FY 2023 Nuclear Energy Voucher recipient 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 »
DOE is seeking feedback on two draft RFPs to acquire HALEU- a crucial material needed to develop and deploy advanced reactors in the United States.
U.S. Department of energy to aquire high-assay low-enriched uranium material Read More »
GEN IV WEBINAR – 8:30 am EDT May 24, 2023 The new High Temperature Reactor (HTR) designs being considered for future Gen IV nuclear reactor deployment include designs utilizing molten salt as the primary coolant. These molten-salt cooled, graphite core designs pose new material compatibility challenges that are not considered within the gas-cooled HTR designs
GEN IV Webinar – Graphite-MOlten Salt Interactions Webinar Read More »
