Bernal-Garcia, Alvaro; Román Moltó, José Enrique; Miró Herrero, Rafael; Verdú Martín, Gumersindo Jesús(Elsevier Masson, 2016-11)
The neutron flux spatial distribution in Boiling Water Reactors (BWRs) can be calculated by means of the Neutron Diffusion Equation (NDE), which is a space- and time-dependent differential equation. In steady state conditions, ...
Numerical methods are usually required to solve the neutron diffusion equation applied to nuclear reactors due to its heterogeneous nature. The most popular numerical techniques are the Finite Difference Method (FDM), the ...