- Immobilized High-Level Waste (IHLW) Transport System . Performed fire condition accident analysis for Immobilized High-Level Waste (IHLW) transport system using ANSYS.
- FuelSolutions Shipping Cask. Performed thermal analyses that included steady state conditions and transient analysis for fire accident conditions using ANSYS and hand calculations. Developed thermal profiles for subsequent structural analysis.
- FuelSolutions TS125 Transportation Cask Vacuum Drying Heat-Up Thermal Analysis. Performed thermal analysis calculations to determine the time it takes for the system to heat-up until the peak temperature of the fuel cladding reaches the fuel cladding temperature limit.
- VCC Storage Cask Thermal Analysis. Performed thermal analysis to determine the time required for the maximum
concrete temperature to reach the governing allowable, off-normal and accident temperature limits in the event of vent blockage accident.
- Transtor PWR Basket Thermal Analysis. Performed thermal analysis calculations to verify that the TranStor™ PWR Fuel Basket, when transported within the TranStor™ Shipping Cask, meets the thermal criteria defined in 10CFR71.
- Grout Vault Facility. Performed thermal and subsequent structural analysis of 100’ X 50’ X 50’ concrete vault used to store low-level liquid waste suspended in a grout mixture.
- Transtor Shipping Cask Thermal Analysis. Performed thermal analysis calculations to confirm the TranStor™ Shipping Cask internals are within allowable temperature limits during all specified ambient conditions for Normal Conditions for Transport and during specified hypothetical accident conditions.
- Nuclear Transportation Shipping Cask. Performed Thermal Analysis using ANSYS.
- Hanford Site Double Shell Tanks. Developed a finite element model of the tank that was defined in such a way as to facilitate the transfer of geometry to various computer codes. SASSI for Soil Structure Interaction, ANSYS for the Stress Analysis, P-THERMAL for Thermal Analysis, and AUTOCAD for drawings. By using the same node and element numbers, different load cases could be combined directly. The model originated from an IGES format export of the AutoCad drawing file, which insured all models matched the controlled drawing files.
- In-Line Sodium Heater in the Fuel Storage Facility. Developed a set of equations for the In-Line Sodium Heater in the Fuel Storage Facility that characterized thermal radiation and convection from heating elements at 1600°F to a wound coil of 4-inch stainless steel pipe containing liquid sodium flowing at various rates.
- Sodium Transfer System. Engineered all trace heat and insulation involved with transferring sodium from a storage tank into the Fuel Storage Facility (FSF) Liquid Sodium System. Liquid sodium is used as a coolant in the Fast Flux Test Facility (FFTF) and solidifies at 208°F. The trace heat and insulation was designed to maintain the sodium in a liquid state during the transfer process.
- Fast Flux Test Facility and Clinch River Breeder Reactor Program. Performed pressure boundary stress analysis of in-core and above-core test assemblies. Conducted detailed stress analysis of high-temperature (Code Case N-47) ASME Boiler and Pressure Vessel limits involving mechanical, seismic, flow-induced vibration thermal striping and dynamic impact loading. Applied environmental effects of radiation and sodium to stainless and Alloy 718 material limits. Special post-processing routines were required for finite element computer programs, ANSYS, utilizing inelastic and creepstrains.
- A4W Vessels, Babcock & Wilcox. Prepared reports involving operating thermal, shock, pressure and vibration loads of risers on A4W vessels.
- NAC-1 Fire Analysis. Thermal analysis was performed to determine the maximum temperature of the seals in the cask lid during and after a postulated 30-minute fire. The initial conditions of the cask were set for a 266 Btu/(hr ft3) heat source in the fuel to an ambient temperature surrounding the cast of 140°F. The fire was simulated by applying a 1475°F temperature to the ambient air for a period of 30 minutes. The transient analysis cool down was then continued for 20 hours after the fire simulation with an ambient air temperature of 140°F.