FY 2009 R&D Awards


Advanced Fuel Cycle Initiative (AFCI)

Title Organization Final Report
Fundamental Understanding of Ambient and High-Temperature Plasticity Phenomena in Structural Materials in Advanced Reactors Georgia Institute of Technology NEUP 09-806 Final Report
Advanced Elastic/Inelastic Nuclear Data Development Project Idaho State University  
Heterogeneous Recycling in Fast Reactors Massachusetts Institute of Technology NEUP 09-811 Final Report
Thermodynamic Development of Corrosion Rate Modeling in Iron Phosphate Glasses Missouri University of Science and Technology NEUP 09-800 Final Report
Development of Subspace-Based Hybrid Monte Carlo-Deterministic Algorithms for Reactor Physics Calculations North Carolina State University NEUP 09-804 Final Report
SiC Schottky Diode Detectors for Measurement of Actinide Concentrations from Alpha Activities in Molten Salt Electrolyte Ohio State University NEUP 09-842 Final Report
Simulations of Failure via Three-Dimensional Cracking in Fuel Cladding for Advanced Nuclear Fuels Oklahoma State University NEUP 09-818 Final Report
Improvements to Nuclear Data and Its Uncertainties by Theoretical Modeling Rensselaer Polytechnic Institute (Troy, NY) NEUP 09-783 Final Report
Sharp Interface Tracking in Rotating Microflows of Solvent Extraction State University of New York at Stony Brook NEUP 09-791 Final Report
Bulk Nanostructured FCC Steels with Enhanced Radiation Tolerance Texas A&M University NEUP 09-814 Final Report
Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels Texas A&M University NEUP 09-816 Final Report
Computational Design of Advanced Nuclear Fuels University of California, Davis NEUP 09-782 Final Report
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 NEUP 09-809 Final Report
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 NEUP 09-821 Final Report
Quantification of UV-Visible and Laser Spectroscopic Techniques for Materials Accountability and Process Control University of Nevada, Las Vegas NEUP 09-820 Final Report
High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering University of Nevada, Reno NEUP 09-795 Final Report
Advanced Mesh-Enabled Monte Carlo Capability for Multi-Physics Reactor Analysis University of Wisconsin, Madison NEUP 09-786 Final Report
Ab Initio Enhanced Calphad Modeling of Actinide Rich Nuclear Fuels University of Wisconsin, Madison NEUP 09-787 Final Report
Development of Diffusion Barrier Coatings and Deposition Technologies for Mitigating Fuel Cladding Chemical Interactions (FCCI) University of Wisconsin, Madison NEUP 09-779 Final Report
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation University of Wisconsin, Madison NEUP 09-780 Final Report

 

Next Generation Nuclear Plant (NGNP)/Generation IV Nuclear Systems

Title Organization Final Report
Irradiation Creep in Graphite Boise State University NEUP 09-794 Final Report
Modeling the Stress Strain Relationships and Predicting Failure Probabilities For Graphite Core Components Cleveland State University NEUP 09-838 Final Report
TRISO-Coated Fuel Durability Under Extreme Conditions Colorado School of Mines NEUP 09-813 Final Report
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 NEUP 09-764 Final Report
Removal of 14C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction Idaho State University NEUP 09-844 Final Report
Millimeter-Wave Thermal Analysis Development and Application to Gen IV Reactor Materials Massachusetts Institute of Technology NEUP-09-833 Final Report
Accurate Development of Thermal Neutron Scattering Cross Section Libraries North Carolina State University NEUP 09-770 Final Report
Understanding Creep Mechanisms in Graphite with Experiments, Multiscale Simulations, and Modeling North Carolina State University NEUP 09-796 Final Report
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 NEUP 09-798 Final Report
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 NEUP 09-822 Final Report
Investigation of Countercurrent Helium-air Flows in Air-ingress Accidents for VHTRs Ohio State University NEUP 09-784 Final Report
Testing of Performance of Optical Fibers Under Irradiation in Intense Radiation Fields, When Subjected to Very High Temperatures Ohio State University NEUP 09-819 Final Report
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 NEUP 09-831 Final Report
A Distributed Fiber Optic Sensor Network for Online 3-D Temperature and Neutron Fluence Mapping in a VHTR Environment Texas A&M University NEUP 09-808 Final Report
Investigation on the Core Bypass Flow in a Very High Temperature Reactor Texas A&M University NEUP 09-840 Final Report
CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications Texas A&M University NEUP 09-817 Final Report
Study of Air ingress across the duct during the accident conditions Texas A&M University NEUP 09-841 Final Report
Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs University of Arizona NEUP 09-807 Final Report
Integral and Separate Effects Tests for Thermal Hydraulics Code Validation for Liquid-Salt Cooled Nuclear Reactors University of California, Berkeley NEUP 09-789 Final Report
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 NEUP 09-765 Final Report
Experimental Study and Computational Simulations of Key Pebble Bed Thermomechanics Issues for Design and Safety University of Idaho NEUP 09-810 Final Report
Prediction and Monitoring Systems of Creep-Fracture Behavior of 9Cr-1Mo Steels for Reactor Pressure Vessels University of Idaho NEUP 09-835 Final Report
Understanding Fundamental Material Degradation Processes in High Temperature Aggressive Chemomechanical Environments University of Illinois, Urbana-Champaign NEUP 09-826 Final Report
Multi-Scale Multi-physics Methods Development for the Calculation of Hot-Spots in the NGNP University of Michigan NEUP 09-812 Final Report
Corrosion and Creep of Candidate Alloys in High Temperature Helium and Steam Environments for the NGNP University of Michigan NEUP 09-768 Final Report
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 NEUP 09-771 Final Report
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 NEUP 09-803 Final Report
Graphite Oxidation Simulation in HTR Accident Conditions University of New Mexico NEUP 09-830 Final Report
Tritium Sequestration in Gen IV NGNP Gas Stream via Proton Conducting Ceramic Pumps University of South Carolina NEUP 09-801 Final Report
Materials, Turbomachinery and Heat Exchangers for Supercritical CO2 Systems University of Wisconsin, Madison NEUP 09-778 Final Report
Experimental Studies of NGNP Reactor Cavity Cooling System with Water University of Wisconsin, Madison NEUP 09-781 Final Report
Assessment of Embrittlement of VHTR Structural Alloys in Impure Helium Environments University of Wisconsin, Madison NEUP 09-785 Final Report
Modeling Fission Product Sorption in Graphite Structures University of Wisconsin, Madison NEUP 09-788 Final Report
Liquid Salt Heat Exchanger Technology for VHTR Based Applications University of Wisconsin, Madison NEUP 09-777 Final Report
Effect of Post-Weld Heat Treatment on Creep Rupture Properties of Grade 91 Steel Heavy Section Welds Utah State University NEUP 09-799 Final Report

 

Investigator-Initiated Research (IIR)

Title Organization Final Report
Neutron Damage and MAX Phase Ternary Compounds Drexel University NEUP 09-790 Final Report
Maximum Fuel Utilization in Fast Reactors without Chemical Reprocessing University of California, Berkeley NEUP 09-769 Final Report
Developing a High Thermal Conductivity Fuel with Silicon Carbide Additives University of Florida NEUP 09-773 Final Report
Fabrication of Tungsten-Rhenium Cladding Materials via Spark Plasma Sintering for Ultra High Temperature Reactor Applications University of Idaho NEUP 09-775 Final Report
Ionic Liquid and Supercritical Fluid Hyphenated Techniques for Dissolution and Separation of Lanthanides, Actinides, and Fission Products University of Idaho NEUP 09-805 Final Report
Utilization of Methacrylates and Polymer Matrices for the Synthesis of Ion Specific Resins University of Nevada, Las Vegas NEUP 09-824 Final Report
Improved LWR Cladding Performance by EPD Surface Modification Technique University of Wisconsin, Madison NEUP 09-766 Final Report
Atomistic Calculations of the Effect of Minor Actinides on Thermodynamic and Kinetic Properties of UO2+x Georgia Institute of Technology NEUP 09-823 Final Report
Improved Fission Neutron Data Base for Active Interrogation of Actinides University of Michigan NEUP 09-802 Final Report

 

Light Water Reactor Sustainability (LWRS)

Title Organization Final Report
Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-High Fluence Conditions University of California, Santa Barbara NEUP 09-834 Final Report