Master practical Monte Carlo methods for neutron transport with clear, actionable techniques you can apply in reactor modeling.
This book explains how Monte Carlo simulations are used to study shielding and neutron behavior in fuel and moderator lattices. It covers key ideas like how to model scattering, absorption, and energy changes, and how to choose velocity and direction for particles in a realistic way. You’ll see how different sampling strategies affect accuracy and computing time, including real-world results from early computer implementations.
- How to set up neutron transport problems in a lattice of fuel rods and moderator material.
- Techniques for sampling particle states and accelerating convergence, such as weight management and Russian roulette termination.
- Ways to interpret cross-sections and how they influence absorption and scattering calculations.
- Practical considerations for using early computers to run complex simulations and read results.
Ideal for readers with interests in nuclear engineering, reactor physics, or computational methods who want a hands-on view of Monte Carlo approaches to shielding and reactor analysis.