Neutron Transport and Diffusion Models for Molten-Salt Reactor Dynamics

Аннотация

The steady state and time dependent equations for a molten-salt reactor are numerically solved adopting the multigroup diffusion and transport models for neutrons. The motion of the multiplying material is properly accounted for in the balance equations for delayed neutron precursors. Non-linear feedback phenomena are also taken into account by coupling the neutron equations with a simplified zero-dimensional thermal model. The analy sis of the results presented allows the identification of physical situations for which transport effects can play an important role and thus must be properly described in the study of realistic system configurations.

Темы

Цитирования и источники