Share my knowledge and help with the use of MCNP

JFB
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Hello everyone,
After more than 32 years working in nuclear engineering and learning everything there is to know about numerical simulation related to radiation protection, I've compiled some of my knowledge into a web application dedicated to radiation protection calculations. Through various interfaces and using simple (or slightly more than simple) 3D models, this application allows you to produce good quality MCNP files that you can download and use locally on your computing server. It's free, a user guide is available, and the website is multilingual. I can also help you if anything is unclear. I can even, if necessary, modify the application or fix any bugs you might find. For neutron calculations, there's a Source4C-type interface that allows you to evaluate the neutrons emitted by alpha/n réeaction . I hope this will be helpful to beginners and others as well.
Best regards.
https://jfbconsulting.3utilities.com/
 

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