One-group neutron diffusion equation (source code)

= One-group neutron diffusion equation
{title2=$-\nabla\cdot(D\nabla\phi)+(\Sigma_a-\nu\Sigma_f)\phi=S$}

= Neutron diffusion equation
{synonym}

A <diffusion approximation> for a scalar <neutron flux>, with one prescribed energy group. Its terms balance current loss, absorption, <nuclear fission> production and a source. A solution also requires appropriate <boundary conditions>.