{"id":15150,"date":"2017-08-11T16:21:42","date_gmt":"2017-08-11T16:21:42","guid":{"rendered":"http:\/\/sitepourvtc.com\/?page_id=15150"},"modified":"2022-10-27T10:54:34","modified_gmt":"2022-10-27T10:54:34","slug":"neutron-diffusion-theory","status":"publish","type":"page","link":"https:\/\/sitepourvtc.com\/nuclear-power\/reactor-physics\/neutron-diffusion-theory\/","title":{"rendered":"Neutron Diffusion Theory"},"content":{"rendered":"
In the previous section, we dealt with the multiplication system and defined the infinite<\/a> and finite multiplication factors<\/a><\/strong>. This section was about conditions for a stable, self-sustained fission chain reaction <\/strong><\/a>and maintaining such conditions. This problem contains no information about the spatial distribution of neutrons<\/a><\/strong> because it is a point geometry problem. We have characterized the effects of the global distribution of neutrons simply by a non-leakage probability\u00a0(thermal<\/a> or fast<\/a>), which, as stated earlier, increases toward a value of one as the reactor core becomes larger.<\/p>\n