Developing a reliable approach to estimate the stoichiometric ratio of O/U in UO2 pellets using MCNP-5 and artificial intelligence

• Published in: Nuclear technology & radiation protection Vol. 37; no. 4; pp. 302 - 307
• Main Authors: Shaban, Sameh, Agha, Ahmad, Aladham, Karim
• Format: Journal Article
• Language: English
• Published: Belgrade Vinca Institute of Nuclear Sciences 01.01.2022; VINCA Institute of Nuclear Sciences
• Subjects: Artificial intelligence; Germanium; mcnp-5; Nuclear fuels; Partial pressure; Pellets; Stoichiometry; Titration; uo2 pellet; Uranium; Uranium dioxide
• ISSN: 1451-3994; 1452-8185
• DOI: 10.2298/NTRP2204302S

Uranium dioxied is used as a nuclear fuel. Depending on the temperature and oxygen partial pressure, it is incredibly versatile and can accept a wide variety of stoichiometry. Many methods are used to estimate the non-stoichiometric O/U ratio such as the coulometric titration, gravimetric and voltammetric methods. These methods have some disadvantages and may be time and cost-consuming. This work develops an approach to determine the stoichiometric ratio by using MCNP-5 code and hyper pure germanium detector to estimate the count rate at 185.7 keV for UO2 pellets. The studied pellets are proposed to have 235U mass content (3 %, 4 %, and 5 %) and 1 cm away from the detector. The mass of the oxide within the pellets is 7.8995 grams. The relation between volume and density has been studied during different steps in which temperature increases. Finally, a reliable model is established to describe the process of converting green pellets to sintered pellets. The model is supported by employing artificial intelligence to predict some features and the overall correlation equals 0.99929.