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1. DEVELOPMENT OF A PRACTICAL FUEL MANAGEMENT SYSTEM FOR PSBR BASED ON ADVANCED THREE-DIMENSIONAL MONTE CARLO COUPLED DEPLETION METHODOLOGY

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2. Modeling and Design of A New Core-Moderator Assembly and Neutron Beam Ports for the Penn State Breazeale Nuclear Reactor (PSBR)

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3. THE DEVELOPMENT OF A THERMAL HYDRAULIC FEEDBACK MECHANISM WITH A QUASI-FIXED POINT ITERATION SCHEME FOR CONTROL ROD POSITION MODELING FOR THE TRIGSIMS-TH APPLICATION

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4. Improvements to the PSBR Fuel Management and Neutronics Model in Support of the New Core Moderator Assembly

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5. Fission matrix methods for temperature and control feedback of small nuclear systems

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6. Improvements on Power Calibration and Core Monitoring at the Penn State Breazeale Reactor

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Open Access