Unstructured Grids and the Multigroup Neutron Diffusion Equation
The neutron diffusion equation is often used to perform core-level neutronic calculations. It consists of a set of second-order partial differential equations over the spatial coordinates that are, both in the academia and in the industry, usually solved by discretizing the neutron leakage term usin...
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| Format: | Article |
| Language: | English |
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Hindawi Limited
2013-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2013/641863 |