University of California, Berkeley September 6-8, 2023 What to expect: Three days of lectures, discussions and hands-on activities on multi-disciplinary aspects of molten salt science and technology supported by world experts. Who should apply: Graduate students, postdocs and professionals with interest in molten salts. Previous experience is not necessary, but selected participants will be required […]
2nd Molten Salt Bootcamp Read More »
GEN IV WEBINAR – 8:30 am EDT July 26, 2023 Many molten salt reactor designs involve the circulation of a cover gas to remove evolved fission products and maintain an inert atmosphere. The cover gas leaving the reactor core is expected to contain noble and non-noble gases, aerosols, volatile species, tritium, and other radionuclides. To
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, Moltex Energy 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.
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 »
