The NEA Global Forum on Nuclear Education, Science Technology and Policy (the NEA Global Forum) held a coun...
The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...
The NEA launched the Nuclear Education, Skills and Technology (NEST) Framework in partnership with its member countries to help address important gaps in nuclear skills capacity building, knowledge t...
ISNL 2023 gathered 60 graduate students and professionals from across the world.
Co-organised with the UK Atomic Energy Authority, the course took place on 20-22 June 2023.
Dates: 12-13 April 2023
Location: Online course, 9:00-13:00 (CEST, UTC+02:00, Paris time)
Dates: 3-7 April, 2023Place: OECD Headquarters in Paris, FranceMinimum enrollment required: 12 participants Course fee: 1000 EURThis 4.5-day interactive course is intended to give students a thorough...
This advanced course is designed for people who have experience in running MCNP Monte Carlo calculations, but who would like to advance their skills and develop greater depth of understanding of theo...
The 2023 International Nuclear Law Essentials (INLE) programme will be conducted under the leadership of Paul Bowden, Honorary Professor of Law at the Nottingham La...
***The course is full***
This intermediate course is designed for people who have some experience in running MCNP Monte Carlo calculations, but who would like to refresh or advance their skills. Prov...
Introduction to the International School of Nuclear Law (ISNL)
Courses were held in November 2022 in paris, France.
PHITS (Particle and Heavy Ion Transport code System) is a general purpose Monte Carlo particle transport simulation code developed under a collaboration between Japan Atomic Energy Agency (JAEA) and ...
This training course provides instruction on the use of the KENO-VI Monte Carlo code for criticality safety calculations and the MAVRIC (Monaco with Automated Variance Reduction using Importance Calc...
OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue and subcritical multiplication calculations on models ...