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Secretary Chu Announces Funding for 71 University-Led Nuclear Research and Development Projects

May 6, 2009 - 1:49pm

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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 towards 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 develop ment 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 at:http://www.caesenergy.org.

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).

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

 

Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction

 

Idaho State University

 

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

 

 

Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions

 

University of California, Santa Barbara

 

 

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