Project Overview

Core Design @OpenMC Assignments.

Activity 4: Fuel Assembly Modeling

• Models a standard $17 \times 17$ PWR-style fuel assembly.
• Includes detailed geometry for fuel pins, guide tubes, instrument tubes, and control rods (AgInCd).
• Implements burnable poisons using Gadolinia ($Gd_{2}O_{3}$).
• Performs eigenvalue calculations ($k_{eff}$) and generates plots for neutron flux and fission rate distributions.

Activity 5: Homogenized Mixture Analysis

• Models a homogenized mixture of fuel and moderator in a spherical geometry.
• Analyzes the effect of moderator-to-fuel volume ratios on criticality.

Activity 6: Depletion and Burnup

• Focuses on fuel assembly depletion calculations over time.
• Tracks the change in isotopic composition and reactivity ($k_{eff}$) as a function of burnup.