The Center for Reactor Core Design was established in 1999 within the framework of the Ukraine Nuclear Fuel Qualification Project (UNFQP). Its main areas of activity include:
  • Preparation of two-group cross sections for design and operational nuclear calculations
  • Cycle safety substantiation based on the core boundary parameters
  • Analysis of mixed cores with different vendors' fuel
  • Design-Basis Accident Analysis in compliance with Ukrainian and international standards
  • Revision of safety limits and conditions based on statistical errors of analysis methodologies, manufacturing tolerances, and errors in determining reactor parameters
  • Design of fuel assembly components
  • Mechanical calculations and analyses using various codes, including Solidworks and ANSYS
  • Development of test programs
  • Support for fuel assembly and component fabrication
  • Criticality calculations for nuclear fuel storage systems using the codes MCNP5/MCNPX and SCALE 5.1
  • Thermal physical analysis of different systems, including reactors and nuclear steam supply systems, dry and wet spent nuclear fuel storage facilities using CFD code Solidworks Flow
  • Safety substantiation for nuclear fuel storage systems
  • Thermal physical analysis of reactor cores using 3-D lattice physics codes
  • Training of NPP ad research organization specialists in design of nuclear fuel and core components
Nuclear Fuel Design Laboratory The Reactor Core Design Laboratory design Safety Analysis and Licensing Laboratory


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