Multiple Archives

Development of Casting Techniques for ẟ-phase Uranium-Zirconium Alloys, Lightbridge Corp

The casting, processing, and shipping of HALEU alloys, like those being developed by Lightbridge, require the ability to experiment with higher temperatures in a facility that can perform these functions. The goal of this project was to identify an appropriate casting method (i.e., crucible and coating combination) that results in an acceptable impurity concentration in the as-cast ingot.

Development of Casting Techniques for ẟ-phase Uranium-Zirconium Alloys, Lightbridge Corp Read More »

Real-Time Generation Risk Assessment (GRA) Model for Commercial Nuclear Power Plant

Entergy will partner with Oak Ridge National Laboratory (ORNL) to implement real-time Generation Risk Assessment (GRA) modeling to address these issues. ORNL’s unique experience in implementing GRA models combined with the use of their Operational Performance Risk Assessment (OPRA) software will be used to integrate the model with real-time data. Entergy will roll out the model at one of its operating plants an if successful look to expand to other plants in their fleet.

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Investigation of the Structural Integrity and Corrosion Resistance of Surface Treatment on Alloy-709 in a Molten Fluoride Salt Environment, Terrestrial Energy USA, Inc.

This project seeks to perform baseline studies on surface-treated A709 for corrosion resistance and mechanical properties to understand long-term corrosion protection when subject to periods of sustained and cyclic loading at high temperatures and its potential use in the IMSR®.

Investigation of the Structural Integrity and Corrosion Resistance of Surface Treatment on Alloy-709 in a Molten Fluoride Salt Environment, Terrestrial Energy USA, Inc. Read More »

Multiphysics Design Optimization and Additive Manufacturing of Nuclear Components, Westinghouse Electric Company, LLC

Westinghouse and Oak Ridge National Laboratory will use multiphysics design optimization methods and additive manufacturing to help develop new nuclear components as well as optimized replacements to existing components that are optimum for meeting design requirements and are manufacturable.

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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 »

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 »