Developing a reliable approach to estimate the stoichiometric ratio of O/U in UO2 pellets using MCNP-5 and artificial intelligence
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Published:2022
Issue:4
Volume:37
Page:302-307
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ISSN:1451-3994
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Container-title:Nuclear Technology and Radiation Protection
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language:en
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Short-container-title:NUCL TECH RAD PROT
Author:
Shaban Sameh1, Agha Ahmad2, Aladham Karim2
Affiliation:
1. Nuclear Safeguards and Physical Protection Department, Nuclear and Radiological Safety Research Center, Egyptian Atomic Energy Authority, Cairo, Egypt 2. Safety of Nuclear Fuel Cycle Department, Nuclear and Radiological Safety Research Center, Egyptian Atomic Energy Authority, Cairo, Egypt
Abstract
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.
Publisher
National Library of Serbia
Subject
Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering
Reference17 articles.
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