***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...
Uranium is the primary source of fuel for nuclear power plants, which provides large-scale low-carbon baseload electricity for more than 30 countries around the world and is the world’s second larges...
The Materials Modelling and Simulation for Nuclear Fuels (MMSNF) Workshop is a forum for the discussion of state-of-the-art modelling and simulation techniques for nuclear fuels and cladding material...
Figure 1: Generation IV International Forum [gen-4.org]
The Nuclear Energy Agency (NEA) and Natural Resources Canada (NRCan) organised an international workshop on the implementation of radioactive w...
Molten Salt Reactor (MSR) technologies are attracting great interest in the public and private sectors for a broad spectrum of applications worldwide. Most efforts at the international level are devo...
The Nuclear Energy Agency (NEA) and the Nuclear Damage Compensation and Decommissioning Facilitation Corporation (NDF) are organising an international workshop on the characterisation of large quanti...
The Symposium is free of charge for all participants and is scheduled to take place in person at the ONR’s offices near Liverpool in the United Kingdom.
The Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2024) is a long-standing conference that focuses on high-performance software development and use....
Dates: 12-13 April 2023
Location: Online course, 9:00-13:00 (CEST, UTC+02:00, Paris time)