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...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2023-12-01
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| Series: | Physics Open |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2666032623000443 |