Non-Free Swelling of Uranium Dioxide Fuel at Burnup 8–13% h.a.
Sign Up to like & getrecommendations! Published in 2017 at "Atomic Energy"
DOI: 10.1007/s10512-017-0192-5
Abstract: The porosity and rate of non-free swelling of the fuel in fast-reactor fuel elements with EK-164ID c.d. steel cladding were measured by hydrostatic and metallographic methods. It was shown that the rate of swelling of… read more here.
Keywords: swelling uranium; free swelling; uranium dioxide; non free ... See more keywords
Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
Sign Up to like & getrecommendations! Published in 2018 at "Atomic Energy"
DOI: 10.1007/s10512-018-0446-x
Abstract: A quantitative assessment is made of the possibilities of the SOKRAT code to model the dissolution of uranium dioxide fuel by zirconium cladding melt at the initial stage of a serious accident at NPP with… read more here.
Keywords: dissolution; uranium dioxide; dioxide fuel; model ... See more keywords
Assessment of Uncertainties in Using Raman Thermometry Techniques to Determine the Local Thermal Conductivity of Uranium Dioxide (UO2)
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DOI: 10.1007/s10765-021-02879-w
Abstract: Uranium dioxide (UO2) is the standard fuel in light water, nuclear reactors, and its material properties, such as thermal conductivity, bear a great influence on the heat transfer efficiencies of the system. Laser flash analysis… read more here.
Keywords: raman thermometry; uranium dioxide; thermal conductivity; conductivity ... See more keywords
Modelling uranium dioxide corrosion under repository conditions: A pore-scale study of the chemical and thermal processes
Sign Up to like & getrecommendations! Published in 2020 at "Corrosion Science"
DOI: 10.1016/j.corsci.2020.108530
Abstract: Abstract This paper investigates the corrosion behaviors of spent uranium dioxide (UO2) fuel when placed in geological repositories. We performed pore-scale reactive transport simulations of the UO2 corrosion process in a defective fuel rod with… read more here.
Keywords: uranium dioxide; uo2 corrosion; corrosion; rate ... See more keywords
Comparative chemical and structural analyses of two uranium dioxide fuel pellets
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DOI: 10.1016/j.jnucmat.2019.02.038
Abstract: Abstract A comparative investigation of the trace element, U and Pb isotopic compositions, and structural attributes of two uranium dioxide fuel pellets was conducted for nuclear forensic applications. One fuel pellet consists of natural UO2… read more here.
Keywords: two uranium; spectroscopy; fuel; dioxide fuel ... See more keywords
Influence of strain conditions on the grain sub-structuration in crept uranium dioxide pellets
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DOI: 10.1016/j.jnucmat.2019.02.052
Abstract: Abstract Stoichiometric uranium dioxide (UO2) pellets were deformed by uniaxial compression creep tests at 1500 °C. Strains comprised between 3% and 11% were applied at strain rates ranging from ∼ 5 × 10−6 s−1 to 70 × 10−6 s−1 to… read more here.
Keywords: sub; sub boundaries; uranium dioxide; influence strain ... See more keywords
In-pile thermal conductivity of uranium dioxide at low burnup
Sign Up to like & getrecommendations! Published in 2020 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2020.152210
Abstract: Abstract In-pile thermal conductivity of uranium dioxide (UO2) was investigated at low burnup levels ( read more here.
Keywords: low burnup; uranium dioxide; conductivity uranium; thermal conductivity ... See more keywords
Numerical analysis of the dissolution of uranium dioxide by molten zircaloy using MPS method
Sign Up to like & getrecommendations! Published in 2017 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2017.05.022
Abstract: Abstract Dissolution of uranium dioxide by molten zircaloy at high temperatures is an important chemical process affecting the fuel melting during nuclear reactor severe accidents. In this study, the dissolution model, based on the mass… read more here.
Keywords: molten zircaloy; uranium dioxide; dissolution uranium; dioxide molten ... See more keywords
What Is the Actual Local Crystalline Structure of Uranium Dioxide, UO2? A New Perspective for the Most Used Nuclear Fuel.
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DOI: 10.1021/acs.inorgchem.6b02111
Abstract: Up to now, uranium dioxide, the most used nuclear fuel, was said to have a Fm3̅m crystalline structure from 30 to 3000 K, and its behavior was modeled under this assumption. However, recently X-ray diffraction… read more here.
Keywords: uranium dioxide; nuclear fuel; crystalline structure; crystalline ... See more keywords
On Morphological and Microstructural Changes in Uranium Dioxide Powder during Binder-Free Hot Pressing
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DOI: 10.4028/www.scientific.net/ddf.375.114
Abstract: Plasticity of oxide fuel based on uranium dioxide is one of the less-covered topics in nuclear materials science. A useful tool to study the deformation mechanisms in this material at elevated temperatures is hot pressing.… read more here.
Keywords: uranium dioxide; microstructural changes; 600 textdegree; powder ... See more keywords