IAEA Webinar
Introduction to Basic Simulations with OpenMC:
Getting Started
Register here to attend
The International Atomic Energy Agency (IAEA) is pleased to announce a webinar "Introduction to Basic Simulations with OpenMC: Getting Started”. This webinar will provide a hands-on introduction to OpenMC, a modern open-source tool for Monte Carlo neutron transport simulations. Participants will learn how to set up and run simple neutronics calculations, interpret results, and become familiar with OpenMC’s workflow and user interface. The session is designed to enable newcomers to approach more advanced topics with confidence.
The purpose of the event is to
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present a hands-on introduction to OpenMC, a modern open-source tool for neutron transport simulations, and
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guide participants how to set up and run simple neutronics calculations, interpret results, and become familiar with OpenMC’s workflow and user interface.
The Webinar is a part of the ongoing IAEA initiative “Open-source Nuclear Codes for Reactor Analysis (ONCORE)”, which is aimed to facilitate international collaboration framework for the development and application of open-source multi-physics simulation tools to support research, education and training for the analysis of advanced nuclear power reactors.
We invite professionals, researchers, and stakeholders in the nuclear industries to join us for this webinar, which promises to be a valuable platform for knowledge exchange and discussion on application of the open-source software for modelling and simulation of nuclear reactors.
