Sandia National Laboratory

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GAIN announces second round FY 2024 Nuclear Energy Voucher recipient

The Gateway for Accelerated Innovation in Nuclear (GAIN) announced today that three 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 second award for FY 2024.

GAIN announces second round FY 2024 Nuclear Energy Voucher recipient Read More »

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GAIN announces first round FY 2024 Nuclear Energy Voucher recipient

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 first award for FY 2024.

GAIN announces first round FY 2024 Nuclear Energy Voucher recipient 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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Risk-Informed Mechanistic Source Term Calculations for a Compact Fast Reactor, Oklo Inc.

The objective of this project was to focus on the coupling of three high fidelity analysis codes for detailed core analysis, an analysis of the Oklo reactor design to assesses the potential for radionuclide release to the environment during accident scenarios, and an assessment and provision of relevant metal fuel data through inspection of post-irradiation examination data from past metal fuel testing. This project had two additional objectives, the experimental characterization of liquid metal heat pipe performance, failure behavior, and phenomena and the testing of generic heat pipes beyond their design limits, providing original data and insights.

Risk-Informed Mechanistic Source Term Calculations for a Compact Fast Reactor, Oklo Inc. Read More »

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