SOLUTION OF THE 2D IAEA PWR BENCHMARK WITH THE NEUTRONIC CODE MILONGA

THELER, GERMAN; CLAUSSE, ALEJANDRO; BONETTO, FABIAN

Conferencia; XXXVIII Reunion Anual de la Asociacion Argentina de Tecnologıa Nuclear; 2011

Milonga is a digital computer code developed to solve the steady-state neutron diffusion equation with an arbitrary macroscopic cross section spatial distribution, optionally allowing for coupled calculations with external codes. Milonga is free software developed as part of a PhD thesis in Nuclear Engineering whose main subject is power reactor design parameter optimization. Although currently under development, a first usable version—the one utilized in this work—has been distributed amongst colleagues for evaluation and comments under the terms of the GNU General Public License. In the present work, an example of application of milonga is given. The problem solved is a benchmark case for numerical schemes applied to a two-dimensional steady-state multigroup neutron diffusion equation proposed by IAEA for PWR-type reactors. Not only is the original problem solved by obtaining all the requested results, but a minor extension to the problem is also presented. This work is particularly focused on illustrating the code’s flexibility, one of the main vectors in milonga’s design basis—which was discussed during last year’s meeting.