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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