Burn‐up calculation of the neutronic and safety parameters of thorium‐uranium mixed oxide fuel cycle in a Westinghouse small modular reactor

Summary Thorium fuel is presently a globally known future nuclear fuel alternative, having good neutronic, physical and chemical properties in addition to its spent nuclear fuel characteristic proliferation resistance. This research focused on the neutronic and safety parameters of thorium‐uranium m...

Ausführliche Beschreibung

Gespeichert in:

Bibliographische Detailangaben
Veröffentlicht in:	International journal of energy research 2021-06, Vol.45 (8), p.12013-12028
Hauptverfasser:	Uguru, Edwin H., Abdul Sani, Siti F., Khandaker, Mayeen U., Rabir, Mohamad H., Karim, Julia A., Onah, Daniel U., Bradley, David A.
Format:	Artikel
Sprache:	eng
Schlagworte:	Chemical properties Chemicophysical properties coefficient of reactivity Core making Depletion Enriched fuel reactors Enrichment fissile enrichment zones Mathematical analysis neutronic Nuclear engineering Nuclear fuels Nuclear reactors Nuclear safety Operating temperature Parameters Proliferation Reactors Safety safety parameters small modular reactor Spent nuclear fuels Temperature Thermal nuclear reactors Thorium thorium fuel cycle Thorium isotopes Uranium Uranium dioxide
Online-Zugang:	Volltext
Tags:	Tag hinzufügen Keine Tags, Fügen Sie den ersten Tag hinzu!

Schreiben Sie den ersten Kommentar!