Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects, Including 7 at NCSU
Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects
WASHINGTON, DC – U.S. Energy Secretary Steven Chu today announced the selection of 71 university research project awards as part of the Department of Energy’s investments in cutting-edge nuclear energy research and development (R&D). Under the Nuclear Energy University Program (NEUP), these 71 projects will receive approximately $44 million over three years to advance new nuclear technologies in support of the nation’s energy goals. By helping to develop the next generation of advanced nuclear technologies, the Nuclear Energy University Program will play a key role in addressing the global climate crisis and moving the nation toward greater use of nuclear energy.
“As a zero-carbon energy source, nuclear power must be part of our energy mix as we work toward energy independence and meeting the challenge of global warming,” said Secretary Chu. “The next generation of nuclear power plants – with the highest standards of safety, efficiency and environmental protection – will require the latest advancements in nuclear science and technology. These research and development university awards will ensure that the United States continues to lead the world in the nuclear field for years to come.”
Selected R&D projects include 31 U.S. universities that will act as lead research institutions for projects in more than 20 states. Other universities, industries, and national laboratories will serve as collaborators and research partners. Under the Nuclear Energy University Program, DOE will support projects in the following nuclear energy research fields: the Advanced Fuel Cycle Initiative (AFCI), the Next Generation Nuclear Plant (NGNP) also known as Generation IV Nuclear Energy Systems, Investigator-Initiated Research (IIR), and Light Water Reactor Sustainability (LWRS).
In keeping with the Obama Administration’s commitment to training the next generation of American scientists, Secretary Chu also announced that DOE is accepting applications for individual nuclear science and engineering scholarships and fellowships under the Nuclear Energy University Program. As part of the Department’s efforts to recruit and train the next generation of nuclear scientists and engineers, DOE is offering approximately $2.9 million in university fellowships and scholarships to support students entering the nuclear science and engineering fields. Further details on the Request for applications are available from the Center for Advanced Energy Studies.
Contracts for the R&D projects are expected to be awarded by September 30, 2009 by the Battelle Energy Alliance, LLC (BEA), a Management and Operating contractor for DOE at the Idaho National Laboratory (INL).
Read more information about the 71 research and development awards.
Advanced Fuel Cycle Initiative (AFCI)
| Title | Organization |
| Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors | Georgia Institute of Technology |
| Advanced Elastic/Inelastic Nuclear Data Development Project | Idaho State University |
| Heterogeneous Recycling in Fast Reactors | Massachusetts Institute of Technology |
| Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses | Missouri University of Science and Technology |
| Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations | North Carolina State University |
| SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte | Ohio State University |
| Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels | Oklahoma State University |
| Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling | Rensselaer Polytechnic Institute (Troy, NY) |
| Sharp Interface Tracking in Rotating Microflows of Solvent Extraction | State University of New York at Stony Brook |
| Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance | Texas A&M University |
| Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels | Texas A&M University |
| Computational Design of Advanced Nuclear Fuels | University of California, Davis |
| Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations | University of Idaho |
| Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials | University of Michigan |
| Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles | University of Missouri, Columbia |
| Development of Alternative Technetium Waste Forms | University of Nevada, Las Vegas |
| Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control | University of Nevada, Las Vegas |
| High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering | University of Nevada, Reno |
| Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis | University of Wisconsin, Madison |
| Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels | University of Wisconsin, Madison |
| Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI) | University of Wisconsin, Madison |
| Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation | University of Wisconsin, Madison |
Next Generation Nuclear Plant (NGNP)/Generation IV Nuclear Systems
| Irradiation Creep in Graphite | Boise State University |
| Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components | Cleveland State University |
| TRISO-Coated Fuel Durability Under Extreme Conditions | Colorado School of Mines |
| An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors | Georgia Institute of Technology |
| Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials | Massachusetts Institute of Technology |
| Accurate Development of Thermal Neutron Scattering Cross Section Libraries | North Carolina State University |
| Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling | North Carolina State University |
| Multiaxial creep-fatigue and creep-ratcheting failures of Grade 91 and Haynes 230 alloys toward addressing the design issues of Gen IV nuclear power plants | North Carolina State University |
| Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids | North Carolina State University |
| Microscale Heat Conduction Models and Doppler Feedback | North Carolina State University |
| Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors | North Carolina State University |
| Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs | Ohio State University |
| Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures | Ohio State University |
| Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy | Rensselaer Polytechnic Institute |
| A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment | Texas A&M University |
| Investigation on the Core Bypass Flow in a Very High Temperature Reactor | Texas A&M University |
| CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications | Texas A&M University |
| Study of Air ingress across the duct during the accident conditions | Texas A&M University |
| Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs | University of Arizona |
| Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors | University of California, Berkeley |
| Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems | University of Cincinnati |
| ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles | University of Colorado, Boulder |
| Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety | University of Idaho |
| Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels | University of Idaho |
| Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments | University of Illinois, Urbana-Champaign |
| Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP | University of Michigan |
| Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP | University of Michigan |
| Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations | University of Michigan |
| Fission Product Sorptivity in Graphite | University of Missouri, Columbia |
| Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 617 | University of Nevada, Las Vegas |
| Graphite Oxidation Simulation in HTR Accident Conditions | University of New Mexico |
| Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps | University of South Carolina |
| Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems | University of Wisconsin, Madison |
| Experimental Studies of NGNP Reactor Cavity Cooling System with Water | University of Wisconsin, Madison |
| Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments | University of Wisconsin, Madison |
| Modeling Fission Product Sorption in Graphite Structures | University of Wisconsin, Madison |
| Liquid Salt Heat Exchanger Technology for VHTR Based Applications | University of Wisconsin, Madison |
| Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds | Utah State University |
Investigator-Initiated Research (IIR)
| Neutron Damage and MAX Phase Ternary Compounds | Drexel University |
| Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing | University of California, Berkeley |
| Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives | University of Florida |
| Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications | University of Idaho |
| Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products | University of Idaho |
| Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins | University of Nevada, Las Vegas |
| Improved LWR Cladding Performance by EPD Surface Modification Technique | University of Wisconsin, Madison |
| Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x | Georgia Institute of Technology |
| Improved Fission Neutron Data Base for Active Interrogation of Actinides | University of Michigan |
Light Water Reactor Sustainability (LWRS)
| Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions | University of California, Santa Barbara |
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Article taken from: http://www.energy.gov/7383.htm
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