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...
Kaydedildi:
| Asıl Yazarlar: | , , |
|---|---|
| Materyal Türü: | Artigo |
| Dil: | Inglês |
| Baskı/Yayın Bilgisi: |
Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2025-06-01
|
| Seri Bilgileri: | Brazilian Journal of Radiation Sciences |
| Konular: | |
| Online Erişim: | https://bjrs.org.br/revista/index.php/REVISTA/article/view/2772 |
| Etiketler: |
Etiket eklenmemiş, İlk siz ekleyin!
|