High-Temperature Gas Reactor

Technologies researched under a GAIN NE Voucher for High-Temperature Gas Reactors

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Reference Data for Determination of Carbon and Oxygen Content in TRISO Fuel Kernels

Standard Nuclear is developing alternative methods to assess the carbon and oxygen content in the fuel kernel. They will partner with Oak Ridge National Laboratory (ORNL) to perform LECO testing in the Low Activation Materials Development and Analysis (LAMDA) laboratory to help baseline and calibrate the method. By developing an alternative method for assessing carbon and oxygen content in TRISO fuel kernels, this project will reduce the cost and inefficiencies associated with current destructive testing methods.

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Development of Analytical Techniques for Trace Impurities in 2LiF-BeF2, Kairos Power

Kairos will partner with Pacific Northwest National Laboratory (PNNL) to extend measurements of dissolved oxygen and corrosion products in FLiBe to the full range of relevant/significant impurities, as well as incorporating the measurement methods into their quality assurance program/practices. Refinement of analytical methods for species in salt that impact system operation will enable Kairos to continue along the aggressive timeline for near term nuclear demonstration and commercial deployment.

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Heat Exchanger Evaluation, NuCube Energy

NuCube will partner with Idaho National Laboratory (INL) to receive assistance in computational analysis of the heat exchanger design. INL has developed a code to optimize high temperature heat exchangers for both installation and operating costs and has validated that code for conventional shell and tube heat exchangers. This analysis will allow NuCube to assess the performance of the heat exchanger and support an optimized design prior to finalization of the detailed design and fabrication to support a demonstration project.

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Ceramic Matrix Composites (CMC) Irradiation Testing, Westinghouse Electric

Westinghouse will partner with Oak Ridge National Laboratory (ORNL) to perform an irradiation test and associated Post-Irradiation Examination (PIE) on a specific CMC to ensure it is a viable option for the eVinci microreactor prior to performing a larger irradiation campaign. The work will utilize the High Flux Isotope Reactor (HFIR) at ORNL.

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Horizontal Refueling and Remote Handling Design Review, Boston Atomics

The Remote Systems Group (RSG) at Oak Ridge National Laboratory (ORNL) will perform a three-stage design review focused on operations, the detailed design, and a failure modes and effects analysis. Their experience base is uniquely valuable to MIGHTR and In-Vesel Fuel Handling Machine (IVFHM) development. This project will mitigate the risk of operational complexity by reviewing a critical system.

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