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Nuclear Energy University Program Awards

Integrated research projects

2014

Integrated Approach to Fluoride High Temperature Reactor (FHR) Technology and Licensing Challenges, Georgia Institute of Technology, The Ohio State University, Texas A&M University at College Station and at Kingsville.

Integrated FHR Technology Development: Tritium Management, Materials Testing, Salt Chemistry Control, Thermal-Hydraulics and Neutronics with Associated Benchmarking, Massachusetts Institute of Technology, University of California at Berkeley, University of Wisconsin at Madison, and University of New Mexico.

2011

High-Temperature Salt-Cooled Reactor for Power and Process Heat, Massachusetts Institute of Technology, University of California at Berkeley, and the University of Wisconsin at Madison.

NEUP R&D Projects

2013

Advanced High Temperature Inspection Capabilities for Small Modular Reactors – Iowa State University.

Compact Heat Exchanger Design and Testing for Advanced Nuclear Reactors and Advanced Power Cycles– The Ohio State University.

Tritium Mitigation/Control for Advanced Reactor Systems – The Ohio State University.

2012

Fuel Core Design Options to Overcome the Heavy Metal Loading Limit and Improve Performance and Safety of Liquid Salt Cooled Reactors – Georgia Institute of Technology.

2011

Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors – University of California at Berkeley.

2010

Carbide Coatings for Nickel Alloys, Graphite, and Carbon/Carbon Composites to be Used in Fluoride Salt Valves – Johns Hopkins University.

Design, Testing, and Modeling of the Direct Reactor Auxiliary Cooling System for AHTRs – The Ohio State University.

Development of Thermal Transient Flow Rate Sensors for High Temperature, Irradiation, Corrosive Environment – University of Nevada-Las Vegas.

Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling– University of Wisconsin-Madison.

Theses

Pietro Avigni, Thermal Hydraulic Modeling of the Advanced High Temperature Reactor for the Evaluation of Steady State and Transient Conditions, Politecnico Di Milano, 2011-12.

Anselmo Cisneros, Pebble Bed Reactors Design Optimization Methods and their Application to the Pebble Bed Fluoride Salt Cooled High Temperature Reactor, University of California at Berkeley, Fall 2013.

Richard B. Cunningham, Multidimensional CFD Modeling of a Liquid Salt Pebble Bed Heat Transfer Loop, University of Tennessee at Knoxville, May 2014.

Massimiliano Fratoni, Development and applications of methodologies for the neutronic design of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR), University of California at Berkeley, Fall 2008.

Cristhian Galvez, Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors, University of California at Berkeley, Spring 2011.

Michael Laufer, Granular Dynamics in Pebble Bed Reactor Cores, University of California at Berkeley, Spring 2013.

Matthew Minck, Preventing Fuel Failure for a Beyond Design Basis Accident in a Fluoride Salt Cooled High Temperature Reactor, Massachusetts Institute of Technology, 2013.

Luke Olson, Materials Corrosion in Molten LiF-NaF-KF Eutectic Salt, University of Wisconsin at Madison, 2009.

John Ritchie, Pressure Measurement Instrumentation in a High Temperature Molten Salt Test Loop, University of Tennessee at Knoxville, December 2010.

Judy Rodriguez, Tritium Production Analysis and Management Strategies for a Fluoride-Salt-Cooled High-Temperature Test Reactor (FHTR), Massachusetts Institute of Technology, 2013.

Raluca Scarlat, Design of Complex Systems to Achieve Passive Safety: Natural Circulation Cooling of Liquid Salt Pebble Bed Reactors, University of California at Berkeley, Fall 2012.

Jitka Žáková, Analysis of an Advanced Graphite Moderated and Molten Salt Cooled High Temperature Reactor, Royal Institute of Technology Stockholm, Sweden 2007.

Contacts

David Holcomb, HolcombDE@ornl.gov, Salt Reactor Technical Lead

Jess Gehin, GehinJC@ornl.gov, ORNL Reactor Technology Lead

Gary Mays, MaysGT@ornl.gov, Advanced Reactor Systems and Safety Lead