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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מידע ביבליוגרפי

Principais autores:	Iago Gomes, Victor Lassance, Maria de Lourdes Moreira
פורמט:	Artigo
שפה:	Inglês
יצא לאור:	Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2025-06-01
סדרה:	Brazilian Journal of Radiation Sciences
נושאים:	Argonauta reactor MCNP Actinides Fission products yields
גישה מקוונת:	https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772
תגים:	הוספת תג אין תגיות, היה/י הראשונ/ה לתייג את הרשומה!