Fiscal year (FY) 2007 Award list

Project Title	Lead Organization* and Collaborators
Generation IV Nuclear Energy Initiative
An Advanced Integrated Diffusion/Transport Method for the Design, Analysis and Optimization of the Very-High Temperature Reactors	Georgia Institute of Technology*; Idaho National Laboratory; Pennsylvania State University
Implications of Graphite Radiation Damage on the Neutronic, Operational, and Safety Aspects of Very-High Temperature Reactors	North Carolina State University*; Oak Ridge National Laboratory ; Idaho National Laboratory
Experimental and CFD Analysis of Advanced Convective Cooling Systems	Texas Engineering Experiment Station*
Establishing a Scientific Basis for Optimizing Compositions, Processing Paths and Fabrication Methods for Nanostructured Ferritic Alloys for Use in Advanced Fission Energy Systems	University of California-Santa Barbara*
Materials and Design Methodology for Very High Temperature Nuclear Systems	University of Illinois-Urbana*; Stress Engineering Services
Fission Product Transport in TRISO-Coated Particle Fuels: Multi-Scale Modeling and Experiment	University of Wisconsin-Madison*
Emissivity of Candidate Materials for VHTR Applications: Role of Oxidation and Surface Modification Treatments	University of Wisconsin-Madison*
Advancing the Fundamental Understanding and Scale-up of TRISO Fuel Coaters Via Advanced Measurement and Computational Techniques	Washington University*
Nuclear Hydrogen Initiative
Optimization of Heat Exchangers	University of California Los Angeles*
Liquid Salts as Media for Process Heat Transfer from VHTRs: Forced Convective Channel Flow Thermal Hydraulics, Materials, and Coatings	University of Wisconsin-Madison*
Advanced Fuel Cycle Research and Development
Economic, Repository and Proliferation Impacts of Advanced Nuclear Fuel Cycles	*Cornell University; University of Texas-Austin
Experimental Development and Demonstration of Ultrasonic Measurement Diagnostics for Sodium Fast Reactor Thermohydraulics	*Kansas State University
Chemistry of Transuranic Elements in Solvent Extraction Processes: Factors Controlling Redox Specialization of Pu and Np in Separation Processes	*Oregon State University; Argonne National Laboratory
Analysis of Advanced Fuel Assemblies and Core Designs for the Current and Next Generations of LWRs	*Texas Engineering; Experiment Station
Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Fast Reactors	* Texas Engineering Experiment Station
Neutronic/Thermalhydraulic Coupling Techniques for Sodium Cooled Fast Reactor Simulations	*Texas Engineering Experiment Station; University of Chicago; Commissariat a l’Energie Atomique; Argonne National Laboratory
New Fission-Product Waste Forms: Development and Characterization	*University of California-Davis; Sandia National Laboratory; Eltron Research, Inc.; Brigham Young University
Identification and Analysis of Critical Gaps in Nuclear Fuel Cycle Codes Required by the SINEMA Program	* University of Cincinnati Idaho State University Idaho National Laboratory
Fundamental Processes of Coupled Radiation Damage and Mechanical Behavior in Nuclear Fuel Materials for High Temperature Reactors	*University of Florida; Idaho National Laboratory; Los Alamos National Laboratory
Fundamental Studies of Irradiation-Induced Defect Formation and Fission Product Dynamics in Oxide Fuels	*University of Illinois-Urbana; Los Alamos National Laboratory
Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced Burner Reactor	*University of Michigan; University of California-Berkeley; Los Alamos National Laboratory; Oak Ridge National Laboratory
Computations for Advanced Nuclear Fuels	*University of Missouri-Columbia