Neutron transport

Neutron transport is the study of the motions and interactions of neutrons with materials. Nuclear scientists and engineers often need to know where neutrons are in an apparatus, what direction they are going, and how quickly they are moving. It is commonly used to determine the behavior of nuclear reactor cores and experimental or industrial neutron beams. Neutron transport is a type of radiative transport.

Neutron transport has roots in the Boltzmann equation, which was used in the 1800s to study the kinetic theory of gases. It did not receive large-scale development until the invention of chain-reacting nuclear reactors in the 1940s. As neutron distributions came under detailed scrutiny, elegant approximations and analytic solutions were found in simple geometries. However, as computational power has increased, numerical approaches to neutron transport have become prevalent. Today, with massively parallel computers, neutron transport is still under very active development in academia and research institutions throughout the world. It remains one of the most computationally challenging problems in the world since it depends on 3-dimensions of space, time, and the variables of energy span several decades (from fractions of meV to several MeV). Modern solutions use either discrete-ordinates or Monte Carlo methods, or even a hybrid of both.

The neutron transport equation is a balance statement that conserves neutrons. Each term represents a gain or a loss of a neutron, and the balance, in essence, claims that neutrons gained equals neutrons lost. It is formulated as follows:

${\displaystyle \quad {\frac {\chi _{p}\left(E\right)}{4\pi }}\int _{0}^{\infty }dE^{\prime }\nu _{p}\left(E^{\prime }\right)\Sigma _{f}\left(\mathbf {r} ,E^{\prime },t\right)\phi \left(\mathbf {r} ,E^{\prime },t\right)+\sum _{i=1}^{N}{\frac {\chi _{di}\left(E\right)}{4\pi }}\lambda _{i}C_{i}\left(\mathbf {r} ,t\right)+\quad }$

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