• NERI 2009 Annual Report
• I-NERI 2009 Annual Report

Reports

Annual Reports   • NERI 2009 Annual Report • NERI 2008 Annual Report • NERI 2007 Annual Report • NERI 2006 Annual Report • NERI 2005 Annual Report • NERI 2004 Annual Report • NERI 2003 Annual Report • NERI 2002 Annual Report • NERI 2001 Annual Report   • Advanced Reactor, Fuel Cycle, and Energy Products Workshop for Universities, Workshop Proceedings, June 16-17, 2005 • NERI Project Reports—Annual and Final • Technological Opportunities to Increase the Proliferation Resistance of Global Civilian Nuclear Power Systems (TOPS), October 2000 • Nuclear Energy Research Advisory Committee Subcommittee on Long-Term Planning for Nuclear Energy Research: Long-Term Nuclear Technology Research and Development Plan, June 2000 • Summary Report of the Nuclear Energy Research Initiative Workshop, An Assessment of Research Opportunities, June 1998 • Federal Energy Research and Development for the Challenges of the Twenty First Century, Report of the Energy Research and Development Panel, President's Committee of Advisors on Science and Technology, November, 1997. • The Future of University Nuclear Engineering Programs and University Research and Training Reactors, May 10, 2000

2007 NERI-C Awards

Project Title	NERI Consortia Participants
NERI Consortium for Real-Time Detection of Actinide Compositions in the UREX+ Process	Texas A&M University; Purdue University; University of Illinois, Chicago; ANL
Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation	University of California, Davis; California Institute of Technology; Northwestern University; University of California, Los Angeles
Performance of Actinide-Containing Fuel Matrices Under Extreme Radiation and Temperature Environments	University of Illinois, Urbana-Champaign; Georgia Institute of Technology; South Carolina State University; University of Michigan
Advanced Instrumentation and Control Methods for Small and Medium Export Reactors with IRIS Demonstration	University of Tennessee; North Carolina State University; PennState University; South Carolina State University; Westinghouse (unfunded)
Advanced Aqueous Separation Systems for Actinide Partitioning	Washington State University; Hunter College (CUNY); Tennessee Technological University; University of New Mexico; University of North Carolina –Wilmington; PNNL; LBNL; INL
An Innovative Approach to Precision Fission Measurements using a Time Projection Chamber	Georgia Institute of Technology; Abilene Christian University; California Polytechnic State University; Colorado School of Mines; Ohio University; Oregon State University; LANL; LLNL; INL
Risk-Informed Balancing of Safety, Nonproliferation, and Economics for the SFR	Massachusetts Institute of Technology; Idaho State University; The Ohio State University
Deployment of a Suite of High Performance Computational Tools for Multiscale Multiphysics Simulation of Generation IV Reactors	Rensselaer Polytechnic Institute; Columbia University; State University of New York, Stony Brook; BNL
Cladding and Structural Materials for Advanced Nuclear Energy Systems	University of Michigan; Alabama A&M University; Pennsylvania State University; University of California, Berkeley; University of California, Santa Barbara; University of Wisconsin, Madison
A Research Program on Very High Temperature Reactors (VHtrs)	University of Missouri, Columbia; North Carolina State University; Washington University, St. Louis
Advanced Electrochemical Technologies for Hydrogen Production by Alternative Thermo chemical Cycles	Pennsylvania State University; Tulane University; University of South Carolina; ANL

Note: Lead University is listed first in italics.
ANL - Argonne National Laboratory
BNL - Brookhaven National Laboratory
INL - Idaho National Laboratory
LANL - Los Alamos National Laboratory
LBNL - Lawrence Berkeley National Laboratory
LLNL - Lawrence Livermore National Laboratory
PNNL - Pacific Northwest National Laboratory

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

Fiscal year (FY) 2006 Award list

Project Title	Lead Organization* and Collaborators
Advanced Fuel Cycle Initiative
Radiation Stability of Candidate Materials for Advanced Fuel Cycles	University of Wisconsin-Madison*
Solution-Based Synthesis of Nitride Fuels	University of Nevada-Las Vegas*; Los Alamos National Laboratory
The Development and Production of Functionally Graded Composite for Pb-Bi Service	Massachusetts Institute of Technology*; Los Alamos National Laboratory
Flexible Conversion Ratio Fast Reactor Systems Evaluation	Massachusetts Institute of Technology*
Development and Utilization of Mathematical Optimization in Advanced Fuel Cycle Systems Analysis	North Carolina State University*; Argonne National Laboratory
Engineered Materials for Cesium and Strontium Storage	Purdue University *
Feasibility of Recycling Plutonium and Minor Actinides in Light Water Reactors Using Hydride Fuel	University of California- Berkeley*; Massachusetts Institute of Technology; Argonne National laboratory
Accelerator-Based Study of Irradiation Creep of Pyrolytic Carbon Used in TRISO Fuel Particles for the VHTR	University of Michigan*; Oak Ridge National Laboratory; Idaho National Laboratory
Development of Acetic Acid Removal Technology for the UREX+ Process	University of Tennessee*; Oak Ridge National Laboratory
Separation of Nuclear Fuel Surrogates from Silicon Carbide Inert Matrix	University of Florida*
Enhancements to High Temperature In-Pile Thermocouple Performance	University of Idaho*; Idaho National Laboratory
Design and Development of Selective Extractants for An/Ln Separations	University of New Mexico*; Washington State University; Idaho National Laboratory
Microwave Processing Of Simulated Advanced Nuclear Fuel Pellets	Virginia Polytechnic Institute and State University*; University of Tennessee
Generation IV Nuclear Energy Systems Initiative
Ab Initio-Based Modeling of Radiation Effects in Multi-Component Alloys	University of Wisconsin-Madison*
Managing Model Data Introduced Uncertainties in Simulator Predictions for Generation IV Systems via Optimum Experimental Design	North Carolina State University*; Idaho National Laboratory; Argonne National Laboratory
Uncertainty Quantification in the Reliability and Risk Assessment of Generation IV Reactors	Purdue University*; Ohio State University
An Advanced Neutronic Analysis Toolkit with Inline Monte Carlo Capability for VHTR Analysis	University of Michigan*; Studsvik of America; General Atomics; TransWare Enterprises, Idaho National Laboratory; Argonne National Laboratory; ORNL
Improving Corrosion Behavior in SCWR, LFR and VHTR Reactor Materials by Formation of a Stable Oxide	The Pennsylvania State University*; Westinghouse Electric Company
Multiscale Modeling of the Deformation of Advanced Ferritic Steels for Generation IV Nuclear Energy Systems	University of California - Los Angeles*; California State University-Northridge
Nuclear Hydrogen Initiative
Gradient Meshed and Toughened SOEC Composite Seal with Self-Healing Capabilities	Virginia Polytechnic Institute and State University
Ni-Si Alloys for the S-I Reactor-Hydrogen Production Process Interface	University of Missouri-Rolla*; Idaho National Laboratory
Microstructure Sensitive Design for Materials in Solid Oxide Electrolyzer Cell	Georgia Tech Research Corporation*; Pacific Northwest National Laboratory
Dynamic Simulation and Optimization of Nuclear Hydrogen Production Systems	Massachusetts Institute of Technology*
High Performance Electrolyzers for Hybrid Thermochemical Cycles	University of South Carolina*; Sandia National Laboratory; Savannah River National Laboratory; Argonne National Laboratory
Development of Efficient Flowsheet and Transient Modeling for Nuclear Heat Coupled Sulfur Iodine Cycle for Hydrogen Production	Purdue University*

FY 2007 Advanced Reactor, Fuel Cycle, and Energy Products Workshop for Universities Workshop Highlights:

Agenda
Overview/Purpose
	The Global Nuclear Energy Partnership (GNEP) Program Overview/ University Programs Presented by: Paul Lisowski
	Advanced Reactor, Fuel Cycle, and Energy Products Workshop for Universities Presented by: John Gutteridge
Funding Opportunity Announcement
	Financial Assistance Funding Opportunity Nuclear Energy Research Initiative for Consortia Presented by: Beth Dahl
R&D Presentations
	Separations and Waste Forms Presented by: James Bresee
	Fuels Presented by: Mitchell Meyer
	Transmutation Science Presented by: Ning Li
	Systems Analysis Presented by: William Halsey
	GNEP Modeling and Simulation Presented by: Kirk Levedahl
	Appropriately Sized Reactors for International Deployment Presented by: Daniel Ingersoll
	Sodium Fast Reactor, including Advanced Burner Reactor Presented by: James Cahalan
	Very-High-Temperature Reactor Presented by: William Windes
	Gen IV Related Design and Evaluation Methods Presented by: Hussein Khalil
	Materials Presented by: William Corwin
	Energy Conversion Presented by: Carl Sink
	Thermochemical Cycle Presented by: Robert Evans
	High-Temperature Electrolysis Presented by: James O’Brien
	Reactor-Hydrogen Production Process Interface Presented by: Robert Evans