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Enabling System Technologies to Improve the Economics and Performance of Existing LWRs and Advanced BWR Plants: Improving Off-gas System Performance, General Electric-Hitachi

General Electric-Hitachi, Argonne National Laboratory and the Idaho National Laboratory provided improved operational guidance for the current and advanced BWR off-gas system designs and identified off-gas system design improvements for use in BWR SMRs.

Enabling System Technologies to Improve the Economics and Performance of Existing LWRs and Advanced BWR Plants: Improving Off-gas System Performance, General Electric-Hitachi 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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Characterization of the Radiation Stability of Molten Nitrate/Nitrite Salts for use as Heat Transfer Fluids in Nuclear Reactor Power Plants, Yellowstone Energy

The objective of this project is to complete the necessary irradiation testing required and accelerate the retirement of risk related to qualification of nuclear environment nitrate salts. It is expected that the results of this project will significantly advance the MNSR design by qualifying the radiation stability of nitrate salt coolants in a nuclear environment.

Characterization of the Radiation Stability of Molten Nitrate/Nitrite Salts for use as Heat Transfer Fluids in Nuclear Reactor Power Plants, Yellowstone Energy Read More »

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Radiation Testing for Nuclear Inspection Systems, Vega Wave Systems

The objective of this project was to test the Enduray Vision System developed by Vega Wave Systems Inc., using 3 MeV X-rays generated by the Van de Graaff system, to assess the radiation tolerance of the system. These tests showed that the Enduray Vision System was 10× more radiation-hard than the best available commercial competitor in terms of dose rate and can easily sustain radiation dose rates and total doses seen in the most extreme commercial applications in the nuclear energy industry.

Radiation Testing for Nuclear Inspection Systems, Vega Wave Systems Read More »

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