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...
Spremljeno u:
| Glavni autori: | , |
|---|---|
| Format: | Artigo |
| Jezik: | Inglês |
| Izdano: |
Elsevier
2023-12-01
|
| Serija: | Physics Open |
| Teme: | |
| Online pristup: | http://www.sciencedirect.com/science/article/pii/S2666032623000443 |
| Oznake: |
Bez oznaka, Budi prvi tko označuje ovaj zapis!
|