The Probabilistic System Assessment Group (PSAG) (formerly the Probabilistic System Assessment Code (PSAC) User Group was established in 1985 by the Nuclear Energy Agency (NEA) of the Organisation fo...
INTRAVAL was set up as an international project concerned with the use of mathematical models for predicting the potential transport of radioactive substances in the geosphere. Such models are used t...
The international study INTRAVAL addressed the validation of models of the transport of radioactive substances through groundwater in the geosphere. The project started in 1987 on the initiative of t...
This report examines the predisposal phase of radioactive waste management programmes in NEA member countries for all types of waste from high-level to intermediate- and low-level waste, and spent fu...
An evaluation of the occurrence of fluid flow through faults and fractures is of primary importance for the performance assessment of radioactive waste repositories located in argillaceous settings.
One of the initiatives of the Clay Club has been to launch a compilation and a review of the relevant literature on the basic concepts and mechanisms which control the movement of water, solute and g...
3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
The NEA Working Party on Nuclear Liability and Transport (WPNLT) met remotely on 17-18 December 2020.
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.
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...
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 ...
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 ...
***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...
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...
Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...
The Nuclear Law Committee (NLC) established the Working Party on Nuclear Liability and Transport (WPNLT) in 2016 to address the practical challenges related to the nuclear liability regime(s) applica...
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...
Photo credit: Joel A. Kulesza, Roger Lee Martz, LANL LA-UR-17-23854
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
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...
