Training Courses and Workshops

The Computer Program Service organises training courses and workshops on the widely used computer programs. Additional training courses on nuclear data processing and thermodynamic data collection and assessment are organised by the NEA Data Bank.

Upcoming events

Date	Class	Registration	Fees	Location
12-16 May 2025	MCNP6® Intermediate Only applications from participants already holding a personal MCNP6.2® or later licence will be considered. If not licensee, please contact RSICC Course description	Registration closed	2000 EUR	NEA, Paris, France
19-23 May 2025	MCNP6® Advanced Only applications from participants already holding a personal MCNP6.3® or later licence will be considered. If not licensee, please contact RSICC Course description	Registration closed	2000 EUR	NEA, Paris, France
10-13 June 2025	FUDGE/(MC)GIDI/GNDS introductory Course description	Register	50 EUR	Online event
17-19 June 2025	FISPACT-II Course description	Registration closed	600 EUR	NEA, Paris, France
30 June-3 July	OpenMC Course description	Register	450 EUR	Online event
24-28 November 2025	Analytical Benchmarks: Case Studies in Neutron Transport Theory (ABNTT) Course description	Register	750 EUR	NEA, Paris, France
1-5 December 2025	NJOY Course description	Register	700 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.

NEA Data Bank training courses and workshop offerings

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 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