Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

This paper presents a comparative analysis when transitioning from fuel meat based on uranium zirconium hydride (U-ZrH1.65) to one based on thorium-uranium-233 zirconium hydride ((Th-233U)-ZrH1.65) as an alternative option for TRIGA reactors. The aim of this study was to investigate the neutronic ch...

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Bibliographic Details
Main Authors: Fadi El Banni, Ouadie Kabach, Aka A. Koua, Bogbe L.H. Gogon, Georges A. Monnehan, Abdelfettah Benchrif, Hamid Amsil, Abdelouahed Chetaine
Format: Article
Language:English
Published: Elsevier 2022-02-01
Series:Journal of King Saud University: Science
Subjects:
Neutronic analysis
TRIGA reactor
Fuel
Burnup characteristics
MCNP6.2
Online Access:http://www.sciencedirect.com/science/article/pii/S1018364721004316

Internet

http://www.sciencedirect.com/science/article/pii/S1018364721004316

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