A5014723088- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Nuclear Physics and Applications
- Fusion materials and technologies
- Advanced X-ray and CT Imaging
- Advanced materials and composites
- Heat transfer and supercritical fluids
- Gamma-ray bursts and supernovae
- Radiation Effects and Dosimetry
- Radiative Heat Transfer Studies
- Solar and Space Plasma Dynamics
- Radioactive contamination and transfer
- Thermal and Kinetic Analysis
- Advanced X-ray Imaging Techniques
- Fiber-reinforced polymer composites
- Inertial Sensor and Navigation
- Geophysics and Gravity Measurements
- Nuclear materials and radiation effects
- Astronomy and Astrophysical Research
- Industrial Vision Systems and Defect Detection
- Risk and Safety Analysis
- Iron and Steelmaking Processes
- Structural Analysis of Composite Materials
Idaho National Laboratory
2016-2025
Massachusetts Institute of Technology
2013-2016
Three advanced nuclear power systems use liquid salt coolants that generate tritium and thus face the common challenges of containing capturing to prevent its release environment. The fluoride salt–cooled high-temperature reactor (FHR) uses clean same graphite-matrix coated-particle fuel as gas-cooled reactors. Molten reactors (MSRs) dissolve in a or chloride with fission product into salt. In most FHR MSR systems, baseline salts contain lithium where isotopically separated 7Li is proposed...
AbstractSilicon carbide possesses a high melting point, low chemical activity, no appreciable creep at temperatures, and neutron absorption cross section, making it an attractive material to investigate for use as fuel cladding in light water reactors. The design investigated herein consists of three layers: inner monolith SiC, central composite layer SiC fibers infiltrated with outer coating protect against corrosion. provides strength hermeticity the tube, adds while providing...
Tristructural isotropic (TRISO) coated fuel particles are a nuclear form under extensive study for use in advanced reactor concepts. TRISO fuels subjected to high temperature neutron irradiations and then examined assess their performance by determining fission product retention studying morphological changes. Micro X-ray computed tomography is one method of nondestructively the effects performance. This work addresses need image processing remove tomographic reconstruction artifacts that...
Abstract Research characterizing hydrogen behavior on carbon has been primarily focused collecting data at near-ambient temperatures and pressures for storage or high volume applications such as fusion. Transport models of a pre-conceptual 236 MWt pebble-bed fluoride-salt-cooled, high-temperature reactor (PB-FHR) estimate that the production tritium is relatively low resulting in partial ranging between 0 20 Pa. Operating an FHR range from 600 to 700°C. Under these operating conditions,...
Abstract The oxidation behavior of matrix‐grade graphite in air‐ or steam‐ingress accident scenarios is great interest for high‐temperature gas reactors (HTGRs). In this study, the microstructures two variants based on German A3‐3 and A3‐27 formulations were characterized with scanning electron microscopy (SEM), transmission (TEM), Raman spectroscopy, correlated to observed through thermogravimetric analysis (TGA) differential calorimetry (DSC). Through TEM imaging selected area diffraction...
Fluoride salt–cooled High-temperature Reactors (FHRs) are a new type of power reactor that delivers heat to the cycle between 600°C and 700°C. The FHR uses High-Temperature Gas-cooled Reactor (HTGR) graphite-matrix coated-particle fuel with failure temperatures ~1650°C. coolants clean fluoride salts have melting points above 350°C boiling 1400°C. This combination may enable design large will not significant thus radionuclide releases environment even in beyond-design-basis accident (BDBA)...