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...
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Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2025-06-01
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| Series: | Brazilian Journal of Radiation Sciences |
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| Online Access: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772 |
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| author | Iago Gomes Victor Lassance Maria de Lourdes Moreira |
| author_facet | Iago Gomes Victor Lassance Maria de Lourdes Moreira |
| author_sort | Iago Gomes |
| collection | DOAJ |
| description | 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 generated for hypothetical scenarios involving the reactor's new fuel under development (U3Si2). The U3Si2 analysis indicated a mass increase for all highlighted actinides across the hypothetical scenarios. Regarding fission product yields, results showed that after 20 years of operation at 1000 W (the new estimated operating power), the mass of all highlighted isotopes was higher than for the same period at 340 W (the current power). These findings are relevant for licensing procedures of the new fuel and for assessing potential accident scenarios, since transitioning to U3Si2 fuel and increasing reactor power may impact the isotopic inventory.
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| format | Article |
| id | doaj-art-eac044cf532c49b08a262df003fac5de |
| institution | DOAJ |
| issn | 2319-0612 |
| language | English |
| publishDate | 2025-06-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| spelling | doaj-art-eac044cf532c49b08a262df003fac5de2025-08-20T03:12:31ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122025-06-01124B (Suppl.)10.15392/2319-0612.2024.27722397Depletion and inventory calculation for the new fuel of IEN's Argonauta reactorIago Gomes0Victor Lassance1Maria de Lourdes Moreira2PPGIENIENIENThis 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 generated for hypothetical scenarios involving the reactor's new fuel under development (U3Si2). The U3Si2 analysis indicated a mass increase for all highlighted actinides across the hypothetical scenarios. Regarding fission product yields, results showed that after 20 years of operation at 1000 W (the new estimated operating power), the mass of all highlighted isotopes was higher than for the same period at 340 W (the current power). These findings are relevant for licensing procedures of the new fuel and for assessing potential accident scenarios, since transitioning to U3Si2 fuel and increasing reactor power may impact the isotopic inventory. https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772Argonauta reactorMCNPActinidesFission products yields |
| spellingShingle | Iago Gomes Victor Lassance Maria de Lourdes Moreira Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor Brazilian Journal of Radiation Sciences Argonauta reactor MCNP Actinides Fission products yields |
| title | Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor |
| title_full | Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor |
| title_fullStr | Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor |
| title_full_unstemmed | Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor |
| title_short | Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor |
| title_sort | depletion and inventory calculation for the new fuel of ien s argonauta reactor |
| topic | Argonauta reactor MCNP Actinides Fission products yields |
| url | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772 |
| work_keys_str_mv | AT iagogomes depletionandinventorycalculationforthenewfuelofiensargonautareactor AT victorlassance depletionandinventorycalculationforthenewfuelofiensargonautareactor AT mariadelourdesmoreira depletionandinventorycalculationforthenewfuelofiensargonautareactor |