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Temperature-dependent thermal conductivity and fuel performance of UN-UO2 and UN-X-UO2 (X=Mo, W) composite nuclear fuels by finite element modeling
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0003-3414-8911
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering. Westinghouse Elect Sweden AB, S-72163 Västerås, Sweden..ORCID iD: 0000-0003-1628-3001
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0002-2381-3309
2024 (English)In: Journal of Materiomics, ISSN 2352-8478, E-ISSN 2352-8486, Vol. 10, no 4, p. 937-946Article in journal (Refereed) Published
Abstract [en]

The temperature-dependent effective thermal conductivity of UN-X-UO2 (X = Mo, W) nuclear fuel composite was estimated. Following the experimental design, the thermal conductivity was calculated using Finite Element Modeling (FEM), and compared with analytical models for 10%, 30%, 50%, and 70% (in mass) uncoated/coated UN microspheres in a UO2 matrix. The FEM results show an increase in the fuel thermal conductivity as the mass fraction of the UN microspheres increases from 1.2 to 4.6 times the UO2 reference at 2,000 K. The results from analytical models agree with the thermal conductivity estimated by FEM. The results also show that Mo and W coatings have similar thermal behaviors, and the coating thickness influences the thermal conductivity of the composite. At higher weight fractions, the thermal conductivity of the fuel composite at room temperature is substantially influenced by the high thermal conductivity coatings approaching that of UN. Thereafter, the thermal conductivity from FEM was used in the fuel thermal performance evaluation during LWR normal operation to calculate the maximum centerline temperature. The results show a significant decrease in the fuel maximum centerline temperature ranging from -94 K for 10% UN to -414 K for 70% (in mass) UN compared to UO2 under the same operating conditions.

Place, publisher, year, edition, pages
Elsevier BV , 2024. Vol. 10, no 4, p. 937-946
Keywords [en]
Accident tolerant fuel, UN-X-UO 2, Composite nuclear fuel, Thermal conductivity, Finite element modeling, Thermal performance
National Category
Materials Engineering
Identifiers
URN: urn:nbn:se:kth:diva-348594DOI: 10.1016/j.jmat.2024.02.007ISI: 001244283600001Scopus ID: 2-s2.0-85189951186OAI: oai:DiVA.org:kth-348594DiVA, id: diva2:1877795
Note

QC 20240626

Available from: 2024-06-26 Created: 2024-06-26 Last updated: 2024-06-26Bibliographically approved

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Sweidan, FarisCosta, Diogo RibeiroLiu, HuanOlsson, Pär

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