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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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DOE-NE’s newest fuel consortium includes defense from antitrust laws
The Department of Energy's Office of Nuclear Energy is setting up a nuclear fuel Defense Production Act Consortium that will seek voluntary agreements with interested companies “to increase fuel availability, provide more access to reliable power, and end America’s reliance on foreign sources of enriched uranium and critical materials needed to power the nation’s nuclear renaissance.” According to an August 22 DOE press release, the plan invokes the Defense Production Act (DPA) to give consortium members “defense from antitrust laws when certain criteria are met” and “allow industry consultation to develop plans of action.” DOE-NE is looking for interested companies to join the consortium ahead of its first meeting, scheduled for October 14.
Adam Rau, James Turso (Penn State)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1352-1360
Maintaining system stability is an important task for operators of nuclear reactors. Automatic control can be a valuable tool in achieving this, however many modern control methods require a model of the system. These models may not account for changes in system parameters resulting from continued use or different operating points. Robust control techniques can account for such uncertainties, guaranteeing stability provided that plant parameters and dynamics remain within specified uncertainty bounds. The present work applies robust control methods to design a controller for the Penn State Breazeale Reactor (PSBR). The impact of wear on the control rod drive mechanism and changes resulting from different reactor power set points are considered. A Simulink model of the PSBR from [1] was linearized and simplified for the purpose of controller design. The model uses the normalized point-kinetics equations and core-averaged thermal-hydraulics. H? control synthesis methods were used to accommodate changes in power level and wear in the control rod drive mechanisms. System stability was verified on a Simulink model, and controller performance was compared to a proportional controller.