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...
***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...
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...
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 ...
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 ...
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
The Working Party on Nuclear Liability and Transport (WPNLT) agreed to prepare and publish specific country sheets presenting provisions related to nuclear transport and transit under the relevant na...
The NEA Working Party on Nuclear Liability and Transport (WPNLT) held a virtual workshop on “The Qualification of Nuclear Substances and Nuclear Liability” on 29-30 March 2021.
The NEA Working Party on Nuclear Liability and Transport (WPNLT) met remotely on 17-18 December 2020.
