Advanced Reactor

Tech for use in Advanced Reactors

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Advanced Coolant and Moderator Enclosure Solutions for Micro Gas Cooled Reactors with Enhanced Efficiency and Safety, HOLOSGEN, LLC

HolosGen, LLC with assistance from Argonne National Laboratory (ANL) will develop advanced coolant sleeve and moderator enclosure solutions for the Holos-Quad micro-gas cooled reactor (GCR) concept operating at high temperatures.

Advanced Coolant and Moderator Enclosure Solutions for Micro Gas Cooled Reactors with Enhanced Efficiency and Safety, HOLOSGEN, LLC Read More »

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Develop ASME Section III Division 5 Design Rules for Elevated Temperature Cladded Class A Type 316 Stainless Steel Components, Kairos Power

Kairos collaborated with Argonne National Laboratory (ANL) to develop design rules and associated materials data for the design of cladded components made of Type 316 stainless steel and cladded by non-code qualified corrosion resistant materials.

Develop ASME Section III Division 5 Design Rules for Elevated Temperature Cladded Class A Type 316 Stainless Steel Components, Kairos Power Read More »

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Chemical Method Development for Quantifying Oxygen in Beryllium Salts, Kairos Power

The goal of this project was to develop a method for analyzing the oxygen content using a commercial inert gas fusion analyzer. This included the development of a calibration curve for the method, quantification of its performance, and testing on FLiBe samples from several sources, including ORNL-produced FLiBe as well as Kairos Power Flibe.

Chemical Method Development for Quantifying Oxygen in Beryllium Salts, Kairos Power Read More »

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Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium, Elysium Industries

Elysium intended to demonstrate the viability, safety, and economic improvement of using spent nuclear fuel and plutonium in molten chloride salt fast reactor fuel salt. A main objective was to eliminate waste and close the fuel cycle, thereby minimizing proliferation, in addition to providing dispatchable power complementary to renewables.

Assessing Fuel Cycle Options for Elysium Molten Chloride Salt Fast Reactor from Spent Nuclear Fuel, Plutonium, and Depleted Uranium, Elysium Industries Read More »

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Development and Testing of Alumina-forming Austenitic Stainless Steels for Lead Fast Reactor, Westinghouse Electric Co.

Oak Ridge National Laboratory (ORNL) worked with Westinghouse Electric Co. to optimize AFA steels for applications specific to LFRs, as reliable materials for key components such as fuel rod cladding, heat exchangers, reactor internals and the reactor vessel.

Development and Testing of Alumina-forming Austenitic Stainless Steels for Lead Fast Reactor, Westinghouse Electric Co. Read More »

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Quantify Sodium Fluoride/Beryllium Fluoride Salt Properties for Liquid Fueled Fluoride Molten Salt Reactors, ThorCon USA

The objective of this project was to measure thermophysical property data for molten salt compositions characteristic of those proposed for use in the ThorCon molten salt reactor. The measured property data support reactor design activities and safety case development.

Quantify Sodium Fluoride/Beryllium Fluoride Salt Properties for Liquid Fueled Fluoride Molten Salt Reactors, ThorCon USA Read More »

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