Depletion and inventory calculation for the new fuel of IEN's Argonauta reactor

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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Bibliographic Details
Main Authors: Iago Gomes, Victor Lassance, Maria de Lourdes Moreira
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2025-06-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
Argonauta reactor
MCNP
Actinides
Fission products yields
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772
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