There are two very different ways to get numerical answers for neutron transport:

Deterministic Methods

1. You write down the transport equation for the neutron angular flux

2. You discretize the phase space (space, energy, angle, and time)

3. You assemble a big linear system for the flux coefficients

4. You solve it by some numerical method, usually iterative

Monte-Carlo Simulations

1. You simulate a neutron's life, from birth (by fission or external source) to termination (by absorption or leakage), according to interaction probabilities

2. Repeat a large number of times

3. Use the histories you have collected to estimate macroscopic quantities: flux, reaction rates, leakage, etc.

TODO

The Monte-Carlo lecture is still missing 🙁.  But users can go to the Monte-Carlo section to get advice 🙂