Coupled neutronics/thermal-hydraulic analysis of ANTS-100e using MCS/RAST-F two-step code system
The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper. The performance of the MCS/RAST-F code system is assessed using steady-state simulations of the ANTS-100e core....
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| Autores principales: | , , |
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| Formato: | Artigo |
| Lenguaje: | Inglês |
| Publicado: |
Elsevier
2023-11-01
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| Colección: | Nuclear Engineering and Technology |
| Materias: | |
| Acceso en línea: | http://www.sciencedirect.com/science/article/pii/S1738573323003352 |
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