THE RTT PROGRAM PACKAGE FOR NEUTRON AND THERMOPHYSICAL CALCULATIONS OF A NUCLEAR REACTOR WITH SOLID COOLANTS

V. T. Gukov, R. P. Fedorenko, I. L. Chihladse
VANT. Ser. Metodiki i Programmy Chislennogo Resheniya Zadach Matematicheskoy Fiziki 1984. Вып.1. С. 14-17.

      The RTT package is designed to accomplish 3-D neutron, thermal, and combined neutron-thermophysical calculations, to compute the critical core size, and to evaluate the campaign depending on fuel burn out in solid coolant reactor systems using the BESM-6 computer. To describe a neutron field a two-group diffusion approximation is introduced and two-group constant space-dependence on the fuel temperature and burn out is taken into account. The temperature distribution is described by a heat conduction equation with respect to the solid coolant reactor specific features. Two-group constants such as temperature, initial concentration, and burn out depth functions are provided in a tabular form using a 69-group constant library. The RTT package is a specialized one, that is oriented only to a solid coolant reactor calculation which is due to its geometry and physical features and also to the computer limitations.