Requirements for Attendees: General knowledge of MCNP6

Summary Paragraph: This tutorial focuses on using MCNP6.3 to perform criticality calculations for criticality safety and reactor physics applications and promoting use of MCNP version 6.3 at DOE sites. Lectures provide an overview of Monte Carlo simulation methods and highlight state-of-the-art in criticality simulations, eigenvalue calculations, convergence analysis and bias in k-effective. New features and physics improvements in MCNP6.3 will be covered including adaptive meshing, fission-matrix, accelerated fission convergence of neutron distribution, and new statistical tests for convergence. Sensitivity and uncertainty analysis using Whisper-1.1 will be discussed and calculation examples demonstrated.