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 |