The following proposals were selected for award pending negotiation. To view an abstract of the project, click on the project title:
| 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 |
| 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)
