Guérin, Pierre; Baudron, Anne-Marie; Lautard, Jean-Jacques - In: Mathematics and Computers in Simulation (MATCOM) 80 (2010) 11, pp. 2159-2167
The neutronic simulation of a nuclear reactor core is performed using the neutron transport equation, and leads to an eigenvalue problem in the steady-state case. Among the deterministic resolution methods, simplified transport (SPN) or diffusion approximations are often used. The MINOS solver...