COMPETENCES
REACTOR PHYSICS
- ALTS Methodology for cross sections generation and modeling for Transient applications
- NEM Core Nodal Diffusion and SP3 Simulator for staedy state and atrsnient applications
- MCOR - Monte Carlo based steady state and deplition calculation
- Scale based methodology for propagation of nuclear data uncertainty
- Iterative Transport Diffusion Methology (ITDM) for Next Generation High Fidelity Core Analysis Tools
- Methodology for optimum mulit-group and few-group energy selection for different reactor designs
- Methodology for implementation of resonance upscatering effects in cross-section generation
CORE THERMAL-HYDRAULIC ANALYSIS
- Development and Maintenance of CTF and CTFFuel Code
- Methodology for High (CFD) to Low (CTF) Model Information for Spacer Grid Applications
- Methodology and Interface for coupling Core Thermal-Hydraulics (CTF) to System Thermal-Hydraulics
- Methodology for Uncertainty Quantification of Core Thermal-Hydraulics Code using statistical Methods
IN-CORE FUEL MANAGMENT
- GARCO: Methodology and Software for Loading pattern and burnable poisons placement in PWR and VVER using Genetic Algorithms
- Methodology for Fuel Assembly design optimization for Small Modular Reactors (SMRs)
- Methodology and Software for Fuel Cycle cost evaluation
- Methodology for multi-cycle loading pattern and burnable poison optimization
ADVANCED REACTOR DESIGNS
- Design and Safety Analysis and Evaluation of Small Modular Reactors
- Design and Safety Analysis and Evaluation of High Temperature Reactors/Prismatic and Pebble Bed
- Design and Safety Analysis and Evaluation of Fast Liquid Cooled Reactors
- Design and Safety Analysis and Evaluation of Molten Salt Reactors
MULTIPHYSICS CODE AND METHODOLOGIES DEVELOPMENT AND APPLICATIONS
- Multi-Physics Methodologies and Codes for LWR Design and Safety Assessment
- Multi-Physics Methodologies and Codes for HTR Design and Safety Assessment
- Multi-Physics Methodologies and Codes for Fast Liquid Reactors Design and Safety Assessment
- Open-Foam based Multi-Physics Methodologies and Codes for Molten Salt Reactors
- Development of Hierarchical Multi-Physics V&V Methodology
- Uncertainty Quantification and Propagation for Multi-Physics applications
BIG DATA, DATA ANALYTICS AND ARTIFICIAL INTELLIGENCY FOR NUCLEAR ENGINEERING APPLICATIONS
- Core and Experimental Design
- Model Development and Validation
- Characterization and Optimization of Test Conditions in test/research reactors
- Optimization of Operating and Safety Margins in Operating and Advanced Nuclear Plants
- Management and Control Systems for different types of reactors
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1201 Twin Branches Way, Unit 100 - Raleigh, NC 27606, US |
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Phone: +1 814-880-1487 |