We are seeking an instructor with proven practical experience in OpenMC to deliver a basic technical training course focused on neutron transport simulation and introductory reactor physics applications.
The course is intended for technical professionals and should emphasize practical use of OpenMC with clear, structured instruction for beginners.
Required profile:
Proven hands-on experience with OpenMC
Experience using OpenMC in real neutron transport or reactor physics applications
Strong command of:
geometry modeling (CSG)
materials definition
k-effective / criticality
tallies
post-processing in Python
Previous teaching or technical training experience in OpenMC
Ability to teach clearly to non-specialist participants
Course scope:
Introductory / basic level
Practical examples in Python / Jupyter
Clear explanation of workflow, execution, and interpretation of results
Focus on applied use, not only theory
Remote delivery preferred.
Please share:
Brief background
Relevant OpenMC experience
Teaching experience
Availability
Proposed rate