The Solution of Two-Dimensional Neutron Diffusion Equation with Delayed Neutrons
نویسندگان
چکیده
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 one group neutron diffusion equation with one group of delayed neutrons.
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ورودعنوان ژورنال:
- Informatica, Lith. Acad. Sci.
دوره 12 شماره
صفحات -
تاریخ انتشار 2001