#TITLE_ALTERNATIVE#
The distribution of neutron population in nuclear reactor is described by using transport equations. One of possible approximations of neutron transport equation is given by the neutron diffusion equation. The paper presents numerical solution method of multi-group neutron diffusion equation for two...
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| Format: | Final Project |
| Language: | Indonesia |
| Online Access: | https://digilib.itb.ac.id/gdl/view/10767 |
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| Institution: | Institut Teknologi Bandung |
| Language: | Indonesia |
| Summary: | The distribution of neutron population in nuclear reactor is described by using transport equations. One of possible approximations of neutron transport equation is given by the neutron diffusion equation. The paper presents numerical solution method of multi-group neutron diffusion equation for two-dimensional geometry. The multi-group diffusion equation is solved using Successive Over Relaxation numerical method. The geometry considered in this paper is hexagonal geometry, which is divided into triangular mesh. <br />
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