“TDMGDSA” A Two Dimensional Multigroup Diffusion Synthetic Accelerated Transport Code
Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes implement an iterative technique that suffers from slow convergence while solving highly scattering problems. This necessitated the development of acceleration methods, among which, the diffusion syn...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
1994-01-01
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| Series: | Journal of King Saud University: Engineering Sciences |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1018363918305993 |