The DOE says it is going to be shipping off $44 million over the next three years to 31 schools for 71 nuclear energy R&D projects. The funding is coming under the auspices of DOE’s Nuclear Energy University Program. The goal, of course, is to figure out a way to improve the use of nuclear power to mitigate the climatic changes. Actual funding is expected to start flowing in the fourth quarter of 2009.

“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,” said DOE Secretary Steven Chu.

The monies are targeting three specific areas of research:

  • Advanced Fuel Cycle Initiative
  • Next Generation Nuclear Plant/Generation IV Nuclear Systems
  • Light Water Reactor Sustainability
  • Investigator-Initiated Research

DOE also announced that is accepting applications for individual nuclear science and engineering scholarships and fellowships under the NEUP.  The agency has set aside a $2.9 million pot, via its Center for Advanced Energy Studies, for these fellowships and scholarships. CAES is now accepting application requests.

Contracts for the R&D projects are expected to be awarded by September 30, 2009 by the Battelle Energy Alliance, LLC, a Management and Operating contractor for DOE at the Idaho National Laboratory.

More information about the 71 research and development awards is available HERE.

1Advanced Fuel Cycle Initiative projects

School Project
Boise State Univ. Irradiation Creep in Graphite1
Cleveland State Univ. Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components1
Colorado School of Mines TRISO-Coated Fuel Durability Under Extreme Conditions1
Drexel Univ. Neutron Damage and MAX Phase Ternary Compounds3
Georgia Institute of Technology Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors1
An Innovative and Advanced Coupled Neutron Transport and Thermal Hydraulic Method (Tool) for the Design, Analysis and Optimization of VHTR/NGNP Prismatic Reactors2
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x3
Idaho State Univ. Advanced Elastic/Inelastic Nuclear Data Development Project1
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction2
MIT Heterogeneous Recycling in Fast Reactors1
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials2
Missouri Univ. of Science and Technology Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses1
North Carolina State Univ. Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations1
Accurate Development of Thermal Neutron Scattering Cross Section Libraries2
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling2
Multiaxial creep-fatigue and creep-ratcheting failures of Grade 91 and Haynes 230 alloys toward addressing the design issues of Gen IV nuclear power plants2
Verification & Validation of High-Order Short-Characteristics-Based Deterministic Transport Methodology on Unstructured Grids2
Microscale Heat Conduction Models and Doppler Feedback2
Optimizing Neutron Thermal Scattering Effects in Very High Temperature Reactors2
Ohio State Univ. SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte1
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs2
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures2
Oklahoma State Univ. Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels1
Rensselaer Polytechnic Institute Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling1
Non Destructive Thermal Analysis and In Situ Investigation of Creep Mechanism of Graphite and Ceramic Composites using Phase-sensitive THz Imaging & Nonlinear Resonant Ultrasonic Spectroscopy2
SUNY-Stony Brook Sharp Interface Tracking in Rotating Microflows of Solvent Extraction1
Texas A&M University Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance1
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels1
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment2
Investigation on the Core Bypass Flow in a Very High Temperature Reactor2
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System Applications2
Study of Air ingress across the duct during the accident conditions2
Univ. of Arizona Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs2
Univ. of California, Berkeley Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors2
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing3
Univ. of California, Davis Computational Design of Advanced Nuclear Fuels1
Univ. of California, Santa Barbara Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions4
Univ. of Cincinnati Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems2
Univ. of Colorado, Boulder ALD Produced B2O3, Al2O3 and TiO2 Coatings on Gd2O3 Burnable Poison Nanoparticles2
Univ. of Florida Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives3
Univ. of Idaho Data Collection Methods For Validation of Advanced Multi-Resolution Fast Reactor Simulations1
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety2
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels2
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications3
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products3
Univ. of Illinois, Urbana-Champaign Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments2
Univ. of Michigan Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials1
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP2
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP2
Creation of a Full-Core HTR Benchmark with the Fort St. Vrain Initial Core and Validation of the DHF Method with Helios for NGNP Configurations2
Improved Fission Neutron Data Base for Active Interrogation of Actinides3
Univ. of Missouri, Columbia Adsorptive Separation and Sequestration of Krypton, I and C14 on Diamond Nanoparticles1
Fission Product Sorptivity in Graphite2
Univ. of Nevada, Las Vegas Development of Alternative Technetium Waste Forms1
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control1
Identifying and Understanding Environment-Induced Crack Propagation Behavior in Ni-Based Superalloy INCONEL 6172
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resin3
Univ. of Nevada, Reno High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering1
Univ. of New Mexico Graphite Oxidation Simulation in HTR Accident Conditions2
Univ. of South Carolina Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps2
Univ. of Wisconsin, Madison Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis1
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels1
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding
Chemical Interactions (FCCI)1
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation2
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems2
Experimental Studies of NGNP Reactor Cavity Cooling System with Water2
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments2
Modeling Fission Product Sorption in Graphite Structures2
Liquid Salt Heat Exchanger Technology for VHTR Based Applications2
Improved LWR Cladding Performance by EPD Surface Modification Technique3
Utah State University Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds2

1Advanced Fuel Cycle Initiative   2Next Generation Nuclear Plant/Generation IV Nuclear Systems 3Investigator-Initiated Research   4Light Water Reactor Sustainability