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GEN IV Webinar – Graphite-MOlten Salt Interactions Webinar

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 […]

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INL's Advanced Test Reactor

Advanced Materials & Manufacturing Technologies (AMMT) Industry Workshop

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

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GEN IV Webinar – Overview of Nuclear Graphite R&D in Support of Advanced Reactors Webinar

GEN IV WEBINAR – 8:30 am EDT April 5, 2023 As arguably the very first nuclear reactor core material, graphite has been utilized in a variety of nuclear applications since Enrico Fermi first stacked up bricks of graphite in a university squash court. But why? Graphite is not the first material that comes to mind

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