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)).
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).
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.
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, Ultra Energy 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 »
ORNL, Manufacturing Demonstration Facility, 2350 Cherahala Blvd., Knoxville, TN May 23-24, 2023 Facilitated by US Department of Energy – Office of Nuclear EnergyHosted by Oak Ridge National Laboratory The 2-day in-person workshop will bring together subject matter experts over our national laboratories, industry, and standard bodies to accelerate the development, qualification, demonstration and deployment of
Advanced Materials & Manufacturing Technologies (AMMT) Industry Workshop Read More »
This meeting is the second in a series ECA is hosting as part of our New Nuclear Initiative to define the role of local governments and the partnerships necessary to develop priorities, policies, educational resources and outreach on new nuclear development.
DOE Awards $22.1 Million to Advance Promising Nuclear Technolgies Read More »
