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Application of SPS in the fabrication of UN and (U,Th)N pellets from microspheres
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.ORCID iD: 0000-0002-2381-3309
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2020 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 536, article id 152181Article in journal (Refereed) Published
Abstract [en]

In this study, the process involved in the fabrication of a potential accident tolerant fuel is described. Homogeneous uranium nitride microspheres doped with different thorium content were successfully manufactured using an internal gelation process followed by carbothermic reduction, and nitridation. Elemental analysis of the materials showed low carbon and oxygen content, the two major impurities found in the products of carbothermic reduction. Uranium nitride microspheres were pressed and sintered using spark plasma sintering (SPS) to produce pellets with variable density. Final density can be tailored by choosing the sintering temperature, pressure and time. Density values of 77–98% of theoretical density (%TD) were found. As expected, higher temperatures and pressures resulted in a denser material. Furthermore, a direct correlation between the onset sintering temperature and thorium content in the materials was observed. The change of onset temperature has been related to an increment in the activation energy for self-diffusion due to the substitution of uranium atoms by thorium in the crystal structure.

Place, publisher, year, edition, pages
Elsevier, 2020. Vol. 536, article id 152181
Keywords [en]
Doping, Internal gelation, Microspheres, Porosity, Sintering, SPS, Theoretical density, Uranium nitride
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-276299DOI: 10.1016/j.jnucmat.2020.152181ISI: 000540245000003Scopus ID: 2-s2.0-85084598047OAI: oai:DiVA.org:kth-276299DiVA, id: diva2:1445025
Note

QC 20200622

Available from: 2020-06-22 Created: 2020-06-22 Last updated: 2022-06-26Bibliographically approved
In thesis
1. Ab initio driven modeling of advanced nuclear fuels
Open this publication in new window or tab >>Ab initio driven modeling of advanced nuclear fuels
2022 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

With the development of clean energy sources such as nuclear power, it has become more important to use advanced nuclear fuels to improve economic efficiency and expand safety margins. Thanks to the high fissile density, high thermal conductivity, and high melting point, uranium nitride and uranium silicide have been considered accident tolerant or high-performance fuels for commercial light water reactors and for future generation reactor systems. The composite fuel UO2-UN combining the high thermal conductivity and higher fissile density of UN and the excellent oxidation resistance of UO2 is also of interest. Great efforts have to be made to develop the fabrication of the advanced fuels and to qualify their performance. In this thesis, ab initio modeling is performed to contribute to this effort. Density functional theory is the basis for computing the electronic structure of materials in question, and a Hubbard correction term is added to handle the strongly correlated of electron interactions. The first part is focused on calculating or choosing suitable correction parameters, and the effect of the magnetic state of the investigated system is revealed. The second part is focused on the defect properties, including thermodynamics and kinetics. The latter is done by combining the DFT+U calculations with self-consistent mean-field theory. In addition, the stability of multi-phase systems are analyzed based on the defect properties and thermodynamics. Significant connection to experiments is made here. In the third part, the fracture properties of UO2 is modeled using an excess-energy assessment method, where the stress response of the grain boundaries and lattice UO2 is obtained. The impact of the fission products Xe and Mo on the fracture behaviors of both grain boundaries and lattices is discussed.

Place, publisher, year, edition, pages
Stockholm: KTH, 2022. p. 92
Series
TRITA-SCI-FOU ; 2022:03
National Category
Physical Sciences
Research subject
Physics; Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-309532 (URN)978-91-8040-150-0 (ISBN)
Public defence
2022-03-25, Kollegiesalen, Brinellvägen 8 https://kth-se.zoom.us/j/61918233605, Stockholm, 10:00 (English)
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Supervisors
Available from: 2022-03-08 Created: 2022-03-07 Last updated: 2022-06-25Bibliographically approved

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Liu, HuanOlsson, Pär

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