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Accommodation and diffusion of Nd in uranium silicide - U3Si2
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
CEA, IRESNE, DEC, DEs,Cadarache, F-13108 St Paul Les Durance, France..
Westinghouse Elect Sweden, SE-72163 Västerås, Sweden..
Bangor Univ, Nucl Futures Inst, Bangor LL57 1UT, Gwynedd, Wales..ORCID iD: 0000-0003-2537-4001
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2021 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 547, article id 152794Article in journal (Refereed) Published
Abstract [en]

Uranium silicide, U3Si2, is considered as an advanced nuclear fuel for commercial light water reactors with improved accident tolerance as well as competitive economics. Nd is employed as a local burnup indicator for conventional oxide fuels due, among other reasons, to its low mobility in the UO2 fuel matrix and its high fission product yield. As part of the studies necessary to determine whether Nd can be considered as a candidate burnup indicator in the U3Si2 concept fuel, we investigate the mobility of Nd in U3Si2. In this work, density functional theory (DFT) calculations are performed to predict the most stable accommodation sites of Nd in U3Si2, found to be within the uranium sublattice. Based on DFT calculations of binding energies and migration activation energies, we investigate Nd diffusion by computing the transport coefficients within the framework of the self-consistent mean-field method. Our calculations predict that the diffusion ratio of Nd to U is smaller in U3Si2 than in UO2. Moreover, at the individual maximum centerline temperature of the fuel, the diffusion of Nd in U3Si2 is much slower than in UO2. From this perspective, Nd represents a good candidate burnup indicator, in similarity to that in UO2.

Place, publisher, year, edition, pages
Elsevier BV , 2021. Vol. 547, article id 152794
Keywords [en]
First -principle calculations, Diffusion behaviors, U3Si2, Burnup indicator
National Category
Inorganic Chemistry
Identifiers
URN: urn:nbn:se:kth:diva-292176DOI: 10.1016/j.jnucmat.2021.152794ISI: 000620250000007Scopus ID: 2-s2.0-85099807660OAI: oai:DiVA.org:kth-292176DiVA, id: diva2:1540008
Note

QC 20210326

Available from: 2021-03-26 Created: 2021-03-26 Last updated: 2022-06-25Bibliographically 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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