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 theory and use techniques. Provided examples will be assembled, executed, and examined. Time will be available throughout the week to discuss individual questions and problems with MCNP experts. If time permits, details on more advanced features in the code can be discussed at the attendee’s request.
Topics to be covered include:
- New features in MCNP6.3
- Brief refresher of basic concepts
- Geometry: unstructured mesh (UM) and hybrid (CSG+UM) geometry
- Source definitions: k-eigenvalue-to-fixed-source bootstrapping
- Variance reduction: tally diagnostics and biasing, weight-window generation
- Criticality: eigenvalue convergence acceleration & assessment; benchmarking
- Python-based quantitative and qualitative post-processing techniques
The class will be based on version 6.2 or later of the MCNP code and will include discussion of broadly accessible MCNP 6.3 topics and resources (e.g., the MCNP 6.3 manual).
Students are expected to have experience with the MCNP code.
The course will take place at the OECD Nuclear Energy Agency headquarters near Paris.
46, Quai Alphonse Le Gallo
Minimum enrollment required: 12 participants
Participants are required to bring their own laptops with MCNP6.2 installed and are strongly recommended to bring the installation media (DVDs, installation files, etc.) and a way to read the media in case reinstallation is necessary.
10 March 2023