Register

Teaching of the GRE@T-PIONEeR courses will be fully online or hybrid (i.e., combination of online and in-person). Specialised facilities allow for both online and physical interactions, such as the hybrid Active Learning Classrooms at Chalmers University of Technology, Gothenburg, Sweden and at Universitat Politècnica de València, Valencia, Spain. For online learning, a Learning Management System (LMS) is used by the teachers for course delivery and management, providing 24/7 access to all teaching resources.

The courses are free of charge. Nevertheless, if one participates to the interactive sessions in-person, the participants need to cover their travel and accommodation costs.


  • Hands-on exercises on the AKR-2 training reactor: Registration opens on May 20, 2024.
  • Hands-on exercises on the CROCUS training reactor: Registrations are currently closed.
  • Course on “Nuclear data for energy and non-energy applications”: Registrations are currently closed.
  • Course on “Neutron transport at the fuel cell and assembly levels”: Registrations are currently closed.
  • Course on “Core Modelling for Core Design”: Registrations are currently closed.
  • Course on “Core modelling for transients”: Registrations are currently closed.
  • Hands-on exercises on the BME training reactor: Registrations are currently closed.
  • Course on “Reactor transients, nuclear safety and uncertainty and sensitivity analysis”: Registrations are currently closed.
  • Course on “Radiation protection in nuclear environment”: Registrations are currently closed.

The planned dates for the interactive sessions are listed below.

The participants to the interactive sessions are expected to complete some preparatory amounting to ca. 40 hours of self-studying prior to the interactive sessions.

September 4-8, 2023 (at UPV, Valencia, Spain, for the onsite participants or online for the remote participants)

October 16-20, 2023 (at Chalmers University of Technology, Gothenburg, Sweden, for the onsite participants or online for the remote participants)

November 27-December 1, 2023 (at UPV, Valencia, Spain, for the onsite participants or online for the remote participants)

January 8-12, 2024 (at UPV, Valencia, Spain, for the onsite participants or online for the remote participants)

January 23 – February 1, 2024 (at BME, Budapest, Hungary, for the onsite participants or online for the remote participants)

February 19-23, 2024 (at UPV, Valencia, Spain, for the onsite participants or online for the remote participants)

April 8-12, 2024 (at BME, Budapest, Hungary, for the onsite participants or online for the remote participants)

September 02 – 14, 2024 (at TUD, Dresden, Germany, for the onsite participants or online for the remote participants)

Dates to be announced later.

Nuclear Data For Energy And Nonenergy Applications

The generation and evaluation of nuclear data libraries.

  • The processing of nuclear data libraries for use in energy and non-energy applications.
  • The assessment of nuclear data uncertainties.
Neutron Transport At The Fuel Cell And Assembly Levels
  • The principles of probabilistic methods in steady-state conditions for fuel cell and assembly calculations.
  • The principles of deterministic methods in steady-state conditions, their approximations, and their range of validity for fuel cell and assembly calculations.
  • The use of those methods for macroscopic cross-section generation.
Core Modelling For Core Design
  • The principles of probabilistic methods in steady-state conditions for core calculations.
  • The principles of deterministic methods in steady-state conditions, their approximations, and their range of validity for core calculations.
  • The use of those methods for reference calculations or for core design, operation and safety analysis.
Core Modelling For transients
  • The principles of deterministic methods in non-steady-state conditions, their approximations, and their range of validity for core calculations.
  • The principles of macroscopic modelling of nuclear thermal-hydraulics and fuel thermo-mechanics.
  • The numerical techniques used for multi-physics coupling.
Reactor Transients, Nuclear Safety And Uncertainty And Sensitivity Analysis
  • The principles of nuclear reactor safety and system behaviour.
  • The principles of uncertainty and sensitivity analysis applied to reactor transients.
Radiation Protection In Nuclear Environment
  • The principles of health physics and radiation protection regulation.
  • The instrumentation for radiation protection in nuclear installations.
  • The shielding calculation methods (both deterministic and probabilistic methods), neutron and gamma transport, and deep penetration problems.