Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor
This paper presents fuel depletion simulations for the Argonauta research reactor using the MCNP6® 1.0 code. The actinide fission yield inventory for the reactor's current U3O8 fuel was conducted from 1965 to 2018 using operating parameters obtained from a previous study. Inventories were also gener...
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| Główni autorzy: | , , |
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| Format: | Artigo |
| Język: | Inglês |
| Wydane: |
Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2025-06-01
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| Seria: | Brazilian Journal of Radiation Sciences |
| Hasła przedmiotowe: | |
| Dostęp online: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772 |
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