NEA Data Bank training

The NEA Data Bank Computer Program Service (CPS) has been conducting training activities for more than 30 years. These courses provide a unique opportunity to bring together code users from around the world, facilitating exchanges on the use of computer codes on nuclear data.

Additional training courses on nuclear data processing and thermodynamic data collection and assessment are also organised by the NEA Data Bank.

What the NEA offers

Training courses and interactive workshops are offered on the most widely used computer programs, by the authors of the codes. They are held both at the NEA headquarters in Paris and in participating countries.

Several training sessions in English are held each year. It includes different formats ranging from groups of 10 to 20 people, mainly for 5 days or in some cases 3 days of training.

Class sizes are limited (up to 20  people) and workshops may be cancelled if minimum enrollment is not obtained one month prior to the workshop. Workshop fees are to be paid in advance and are refundable up to one month before each class.

The fee includes the training course, luncheons and coffee breaks.

For participants working in France: the NEA is not a training centre ("centre de formation"), no training agreement ("convention de formation") will be established.


Codes covered by the training courses and workshops

  • ABNTT, analytical benchmarks: case studies in neutron transport theory
  • FISPACT-II, inventory simulation platform for nuclear observables and materials science
  • FLUKA, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter
  • MCNP
    • Introduction
    • Intermediate
    • Advanced
  • NJOY2016, a nuclear data processing system for converting evaluated nuclear data into libraries for applications calculations
  • Electron-photon transport modelling with PENELOPE physics, code structure and operation. The PENELOPE manual is available here
  • PHITS Monte-Carlo particle and heavy ion transport code system
    • SCALE/KENO: criticality safety calculations
    • SCALE/KENO-MAVRIC: criticality safety and radiation shielding
    • SCALE/ORIGEN: standalone fuel depletion, activation, and source term analysis
    • SCALE/TRITON: lattice physics and depletion
    • SCALE/TSUNAMI: sensitivity and uncertainty calculations
  • Thermodynamic data collection and assessment, more information on the Thermochemical Database Project here
  • TRIPOLI 3D general purpose continuous energy Monte Carlo transport code