Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC
The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using numerical methods. One of the difficulties in the sol...
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| Principais autores: | , |
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| Format: | Artigo |
| Sprog: | Inglês |
| Udgivet: |
Elsevier
2023-12-01
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| Serier: | Physics Open |
| Fag: | |
| Online adgang: | http://www.sciencedirect.com/science/article/pii/S2666032623000443 |
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