INTRODUCTION The physics design of nuclear reactors requires the determination of the gross statistical behaviour of the neutron population in the reactor system. This in turn calls for the solution of the Boltzmann equation of neutron transport theory which forms the subject matter of reactor theory. It is however not easy to solve this equation by a direct discretization process even on the largest computers because of the presence of too many independent variables, complicated energy variations of the macroscopic crosssections and the complex geometrical arrangement of the core materials such as fuel, coolant, moderator, reflectors, etc, in a reactor. This thesis describes the mathematical model used to analyze the Miniature Neutron Source Reactor (MNSR) and the method of creation of a data base for the reactor. In Chapter Two, a brief description of the reactor for which the present analysis is conducted is presented. Basic work in reactor theory which includes the study of the mathematical properties of the relevant equations is discussed. A review of the Boltzmann neutron transport theory and the neutron diffusion approximation to the transport theory, specifically to twodimensional, two-group theory which is concerned with the dependence of the neutron flux on spatial coordinates (radial and axial) and the direction of neutron motion, are presented. Finally the various methods of solution are also discussed.
ANIM-SAMPONG, S (2021). Numerical Solution Of A Two-Dimensional Multigroup Diffusion Equation For The Analysis Of The Miniature Neutron Source Reactor (MNSR). Afribary. Retrieved from https://track.afribary.com/works/numerical-solution-of-a-two-dimensional-multigroup-diffusion-equation-for-the-analysis-of-the-miniature-neutron-source-reactor-mnsr
ANIM-SAMPONG, S. "Numerical Solution Of A Two-Dimensional Multigroup Diffusion Equation For The Analysis Of The Miniature Neutron Source Reactor (MNSR)" Afribary. Afribary, 18 Apr. 2021, https://track.afribary.com/works/numerical-solution-of-a-two-dimensional-multigroup-diffusion-equation-for-the-analysis-of-the-miniature-neutron-source-reactor-mnsr. Accessed 13 Nov. 2024.
ANIM-SAMPONG, S. . "Numerical Solution Of A Two-Dimensional Multigroup Diffusion Equation For The Analysis Of The Miniature Neutron Source Reactor (MNSR)". Afribary, Afribary, 18 Apr. 2021. Web. 13 Nov. 2024. < https://track.afribary.com/works/numerical-solution-of-a-two-dimensional-multigroup-diffusion-equation-for-the-analysis-of-the-miniature-neutron-source-reactor-mnsr >.
ANIM-SAMPONG, S. . "Numerical Solution Of A Two-Dimensional Multigroup Diffusion Equation For The Analysis Of The Miniature Neutron Source Reactor (MNSR)" Afribary (2021). Accessed November 13, 2024. https://track.afribary.com/works/numerical-solution-of-a-two-dimensional-multigroup-diffusion-equation-for-the-analysis-of-the-miniature-neutron-source-reactor-mnsr