Reactor Simulation Project

Project Overview

This project is a comprehensive reactor simulation tool developed in Fortran, designed to model and analyze various aspects of nuclear reactor physics. It employs one-group diffusion theory to simulate neutron behavior in different reactor geometries, providing insights into critical reactor parameters and neutron flux distributions.

Features

• One-group diffusion calculations for multiple reactor geometries:
  • Slab reactor
  • Cylindrical reactor
  • Spherical reactor
  • Reflected reactor
• Critical dimension calculations
• Neutron flux distribution analysis
• K-infinity and effective multiplication factor (k-eff) calculations
• Parametric studies for reactor design optimization
• Data output for visualization of results

Computational Neutronics Skills Demonstrated

• Implementation of one-group diffusion theory
• Numerical solutions to neutron diffusion equations
• Modeling of neutron behavior in various reactor geometries
• Criticality calculations and analysis
• Neutron flux and power distribution computations
• Application of boundary conditions in neutron transport problems

Nuclear Engineering Concepts Applied

• Reactor core design principles
• Understanding of neutron lifecycle in fission reactors
• Analysis of moderator and reflector effects on reactor performance
• Fuel utilization and burnup considerations
• Control rod worth calculations
• Temperature effects on reactor behavior

Technical Skills Developed

• Fortran programming for scientific computing
• Command-line interface design for user interaction
• Modular code structure for complex scientific applications
• Numerical methods for solving differential equations
• Data processing and output for scientific visualization
• Version control using Git for project management

Future Enhancements

• Multi-group diffusion calculations
• Time-dependent analysis for transient behavior
• Monte Carlo methods for more accurate neutron transport simulations
• Integration with thermal-hydraulic models for coupled neutronic-thermal analysis

Software Architecture

Roadmap

Reactor Calculations

This project demonstrates a practical application of nuclear engineering principles and computational methods, showcasing skills relevant to the field of reactor physics and design.