Date |
Class |
Registration |
Fees |
Location |
| 4 - 7 November 2025 |
SERPENT-2 in-person training course for beginners Course description |
The course is full |
800 EUR |
NEA, Paris, France |
| 17-21 November 2025 |
SCALE/ORIGEN Course description |
The course is full |
1500 EUR |
NEA, Paris, France |
| 24-28 November 2025 |
Analytical Benchmarks: Case Studies in Neutron Transport Theory (ABNTT) Course description |
The course is full |
750 EUR |
NEA, Paris, France |
| 24 - 28 November 2025 |
OpenMC in-person Course description |
The course is full |
2000 EUR |
NEA, Paris, France |
| 1-5 December 2025 |
NJOY Course Course description |
The course is full |
700 EUR |
NEA, Paris, France |
| 16-20 March 2026 |
MCNP6® Intermediate Course description |
Register |
2000 EUR |
NEA, Paris, France |
| 23-27 March 2026 |
MCNP6® Advanced Course description |
Register |
2000 EUR |
NEA, Paris, France |
For in-person courses, the fee includes the training course, luncheons and coffee breaks.
Class sizes are limited and workshops may be cancelled if minimum enrollment is not obtained one month prior to the workshop. Workshop fees paid are refundable up to one month before each class.
For participants working in France: the NEA is not a training centre ("centre de formation"), no training agreement ("convention de formation") will be established.
What the NEA offers - Catalogue of courses
Training courses and interactive workshops are offered on the most widely used computer programs, by the authors of the codes. They are held in person (at the NEA Headquarters in Paris or in NEA Data Bank participating countries) or online. The language of these events is English. Courses are held in different formats, from half a day to five days of training.
- 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
- FRENDY, Nuclear Data Processing System for Evaluated Nuclear Data File
- FUDGE/(MC)GIDI/GNDS, open-source codes FUDGE and GIDIplus (available from https://github.com/LLNL/fudge and https://github.com/LLNL/gidiplus) to generate and use nuclear data in the Generalised Nuclear Database Structure or GNDS
- MCNP, Monte Carlo N-Particle Transport Code System
- Introduction
- Intermediate
- Advanced
- NJOY2016, a nuclear data processing system for converting evaluated nuclear data into libraries for applications calculations
- OpenMC, a community-developed Monte Carlo neutron and photon transport simulation code
- Electron-photon transport modelling with PENELOPE physics, code structure and operation. The PENELOPE manual is available here
- PHITS, a Monte-Carlo particle and heavy ion transport code system
- SCALE
- 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
- Nuclear Data Fundamentals and AMPX Libraries Generation
- SERPENT V2.2.X, 3-D continuous-energy Monte Carlo reactor physics burnup calculation, lattice physics applications
