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Engineered microstructure composites as means of improving the oxidation resistance of uranium nitride
KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT. KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
2023 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Owing to its high uranium density and good thermophysical properties,

uranium nitride (UN) fuel has been considered as a potential Accident Tolerant

Fuel (ATF) candidate for use in Light Water Reactors (LWRs). However,

the main disadvantage of UN is its low oxidation resistance in water/steam

containing atmospheres at the operating temperatures of LWRs.

The main objective of this thesis is to investigate a concept of engineered

microstructure composites as means of improving the response of UN to waterside

corrosion. The methodology for incorporating the corrosion resistant

additives in the form of metals, nitrides and oxides into the UN matrix has

been developed and tested. The additives were proposed to produce coated

(no interaction with UN) or doped (incorporation of the additive into the

UN bulk) grains, which will be able to shield the UN from the oxidising environment

and slow down the oxygen diffusion through the bulk. The UN

composite pellets containing the selected additives were sintered using the

Spark Plasma Sintering (SPS) technique. The resulting microstructures of

the composite pellets were well characterised prior to subjecting some of the

engineered microstructure representative samples to oxidation testing in air

and steam containing environments.

The obtained results indicate that the response to air and steam oxidation

of the composite samples differs from that of pure UN. Moreover, a delay in

the oxidation onset was observed for the composite samples UN-20CrNpremix

and UN-20ZrNpremix in steam and for UN-20CrNpremix pellet in air. The

improved response to oxidation was accompanied by the formation of the

ternary oxides, an observation that could be applied to the screening process

of the additive candidates for waterproofing of UN.

Abstract [sv]

På grund av dess höga urandensitet och goda termofysiska egenskaper

har urannitrid (UN) ansetts vara ett potentiellt Accident Tolerant Fuel (ATF)

kandidat för användning i lättvattenreaktorer (LWR). Dock, den största nackdelen

med UN är dess låga oxidationsbeständighet i vatten/ånga-innehållande

atmosfärer vid driftstemperaturer för LWR.

Huvudsyftet med denna avhandling är att undersöka ett koncept för konstruerade

mikrostrukturkompositer som ett sätt att förbättra urannitridens

korrosionstolerans på vattensidan. Metodik för att införliva korrosionsbeständiga

tillsatser i form av metaller, nitrider och oxider i UN-matrisen har utvecklats

och testats. Tillsatserna föreslogs för att skapa en effekt av belagda

(ingen interaktion med UN) eller dopade (inkorporering av tillsatsen i

UN-matrisen) korn, som kommer att kunna skydda UN från den oxiderande

miljön eller bromsa syrediffusionen genom matrisen. UN kompositkutsar

innehållande de utvalda tillsatser har sintrats med tekniken Spark Plasma

Sintering (SPS). De resulterande mikrostrukturerna hos kompositkutsarna

karakteriserades väl innan några av de mikrostrukturrepresentativa proverna

utsattes för oxidationstestning i luft- och ångainnehållande miljöer.

De erhållna resultaten indikerar att svaret på luft- och ångaoxidation av

de sammansatta proverna skiljer sig från det för UN. Dessutom observerades

fördröjningen i oxidationsstarten för kompositproverna UN-20CrNförblandning

och UN-20ZrNförblandning  i  ånga och för UN-20CrNföblandning kutsar i luft.

Det förbättrade svaret på oxidation åtföljdes av bildningen av ternära oxider,

en observation som kunde tillämpas på screeningsprocessen av tillsatskandidaterna

för vattentätning av UN.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2023. , p. 77
Series
TRITA-SCI-FOU ; 2023:02
National Category
Other Materials Engineering
Research subject
Physics
Identifiers
URN: urn:nbn:se:kth:diva-324614ISBN: 978-91-8040-483-9 (print)OAI: oai:DiVA.org:kth-324614DiVA, id: diva2:1742121
Public defence
2023-03-31, Kollegiesalen, Brinellvägen 8, Stockholm, 10:00 (English)
Opponent
Supervisors
Funder
Swedish Foundation for Strategic Research
Note

QC 230910

Available from: 2023-03-10 Created: 2023-03-08 Last updated: 2023-03-13Bibliographically approved
List of papers
1. Design and fabrication of UN composites: From first principles to pellet production
Open this publication in new window or tab >>Design and fabrication of UN composites: From first principles to pellet production
2021 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 553, p. 153047-, article id 153047Article in journal (Refereed) Published
Abstract [en]

In this study the composite UN-AlN, UN-Cr, UN-CrN and UN-AlN-CrN pellets were fabricated, and the advanced microstructure with different modes of interaction between the phases was obtained. The dopants for this study were selected based on the results of the ab-initio modeling calculations, that identified the AlN phase as insoluble and CrN and Cr as soluble in the UN matrix. This method allowed to investigate the possibility of improving the corrosion resistance of UN by protecting the grain boundaries with insoluble AlN and by hindering the diffusion of oxygen through the bulk by adding soluble CrN and Cr. The UN powder was produced by hydriding-nitriding method and mixed with the AlN, CrN and Cr powders. High density (>90 %TD) composite pellets were sintered by Spark Plasma Sintering (SPS). The microstructure of the pellets was analysed using SEM coupled with EDS. The phase purity was determined by XRD. For the first time the presence of the ternary U2CrN3 phase was observed in the composite pellets containing Cr and CrN dopants. The results obtained in this study allowed to assess the methodology for fabrication of the UN composites with controlled microstructure.

Place, publisher, year, edition, pages
Elsevier BV, 2021
Keywords
Nuclear, Nuclear fuel, Uranium nitride
National Category
Other Materials Engineering
Identifiers
urn:nbn:se:kth:diva-298545 (URN)10.1016/j.jnucmat.2021.153047 (DOI)000663795400006 ()2-s2.0-85107435072 (Scopus ID)
Note

QC 20210714

Available from: 2021-07-14 Created: 2021-07-14 Last updated: 2023-03-08Bibliographically approved
2. Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains
Open this publication in new window or tab >>Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains
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2021 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 556, article id 153249Article in journal (Refereed) Published
Abstract [en]

The oxidation behaviour of the composite UN-AlN, UN-Cr 2 N/CrN and UN-AlN-Cr 2 N/CrN pellets in air and anoxic steam under thermal transient conditions was investigated and compared with the pure UN pellet. The composite pellets were manufactured to contain the engineered microstructure of coated (the addition of matrix-insoluble AlN) and doped (the addition of matrix-soluble Cr 2 N/CrN) grains. The composite powders were produced by powder metallurgy and sintered into pellets using the SPS method. Sintered composite pellets were subjected to a thermal transient up to 1273 K in an STA-EGA (TGA-DSC-Gas-MS) system, followed by crystallographic characterization by XRD and morphological and elemental analysis by FEG-SEM. Improved oxidation behaviour in air compared to pure UN was demonstrated by the UN-Cr 2 N/CrN composite pellet. The formation of the ternary oxide UCrO 4 from the ternary (U 2 Cr)N 3 phase (doped grain) was observed, consistent with the delayed oxidation onset and slower reaction rates. In an anoxic steam environment UN-Cr 2 N/CrN exhibited a higher onset oxidation temperature relative to UN, although the reaction progressed faster than for UN sample. Composite UN-AlN pellet oxidised at a lower temperature in both air and steam, compared to pure UN, due to internal stresses in the fuel matrix. A mechanism for degradation of the composite materials is proposed and the influence of the individual phases on the oxidation behaviour of the composites is discussed.

Place, publisher, year, edition, pages
Elsevier BV, 2021
Keywords
Nuclear fuel, Uranium nitride, Accident Tolerant fuel, Composites
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-303752 (URN)10.1016/j.jnucmat.2021.153249 (DOI)000703520700007 ()2-s2.0-85113384985 (Scopus ID)
Note

QC 20211103

Available from: 2021-11-03 Created: 2021-11-03 Last updated: 2023-03-08Bibliographically approved
3. Potential accident tolerant fuel candidate: Investigation of physical properties of the ternary phase U2CrN3
Open this publication in new window or tab >>Potential accident tolerant fuel candidate: Investigation of physical properties of the ternary phase U2CrN3
Show others...
2022 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 568, article id 153851Article in journal (Refereed) Published
Abstract [en]

In the present study, physical properties of the ternary phase U2CrN3 are evaluated experimentally and by modeling methods. High density pellets containing the ternary phase were prepared by spark plasma sintering (SPS). The microstructural and crystallographic analyses of the composite pellets were performed using scanning electron microscopy (SEM), standardised energy dispersive spectroscopy (EDS) and electron backscatter diffraction (EBSD). Evaluation of the mechanical properties was performed by nanoindentation test. The impact of temperature on lattice properties was evaluated using high temperature X-ray diffraction (XRD) coupled with modeling. Progressive change in the lattice parameters was obtained from room temperature (RT) to 673 K, and the result was used to calculate average linear thermal expansion coefficients, as well as an input for the density functional theory (DFT) modeling to reassess the degradation of the mechanical properties. The ab-initio calculation provides an initial assessment of electronic configuration of this ternary phase in a direct comparison with one of UN phase. For this goal, modeling was also employed to evaluate point defect formation energies and electronic charge distribution in the ternary phase. Results indicate that the U2CrN3 phase has similar mechanical properties to UN (Young's, bulk, shear moduli, hardness). No preferential crystallographic orientation was observed in the composite pellet. However, charge electron density distribution highlights the significant directionality of chemical bonds, which is in agreement with the anisotropy and non-linear behaviour of the obtained thermal expansion (α¯(aa) = 9.12 × 10−6/K, α¯(ab) = 5.81 × 10−6/K and α¯(ac) = 6.08 × 10−6/K). As a consequence, uranium was found to be more strongly bound in the ternary structure which may delay diffusion and vacancy formation, promising an acceptable performance as nuclear fuel.

Place, publisher, year, edition, pages
Elsevier BV, 2022
National Category
Materials Chemistry
Identifiers
urn:nbn:se:kth:diva-321965 (URN)10.1016/j.jnucmat.2022.153851 (DOI)000879440400008 ()2-s2.0-85132727972 (Scopus ID)
Note

QC 20221128

Available from: 2022-11-28 Created: 2022-11-28 Last updated: 2023-03-08Bibliographically approved
4. Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution
Open this publication in new window or tab >>Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution
(English)Manuscript (preprint) (Other academic)
Abstract [en]

Thermophysical properties and oxidation behaviour of the composite pellet UN-20vol%ZrN were investigated experimentally and compared with the behaviour of the pure UN pellet. A compound of one phase, a solid solution of the average composition U0.8Zr0.2N, was obtained by Spark Plasma Sintering (SPS) of the powders UN and ZrN. Crystallographic and microstructural characterisation of the composite was performed using Scanning Electron Microscopy (SEM), standardised Energy Dispersive Spectroscopy (EDS) and Electron Backscatter Diffraction (EBSD). Nano hardness and Young’s modulus were also measured by the nanoindentation method. High Temperature X-ray diffraction (XRD) was applied to obtain the lattice expansion as a function of temperature (room temperature to 673 K). Thermogravimetric Analysis (TGA) was applied to evaluate oxidation behaviour in air. Results demonstrate that the fabrication method results in a matrix of solid solution with homogeneous composition averaged to U0.8Zr0.2N. The mechanical properties of such solution are uniform, with variation only due to the crystallographic orientation of the grains of the solution phase, similarly to pure UN. The obtained value for the average linear thermal expansion coefficient is  = 7.94*10-6/K, which compares well to UN ( = 7.95*10-6/K) for the same temperature range. The degradation behaviour of the composite pellet UN-20vol%ZrN in air shows a lower oxidation onset temperature, compared to pure UN, with the final product of oxidation being mainly U3O8. Smaller crystallites in the product of corrosion of the composite pellet indicate that the mechanism of degradation of the solid solution phase U0.8Zr0.2N is accompanied by the formation of two distinct oxides and their interaction.

National Category
Other Materials Engineering
Identifiers
urn:nbn:se:kth:diva-324612 (URN)
Funder
Swedish Foundation for Strategic Research
Note

QC 20230308

Available from: 2023-03-08 Created: 2023-03-08 Last updated: 2023-03-08Bibliographically approved
5. Crystallographic Characterization of U2CrN3 Structure and Formation Mechanism
Open this publication in new window or tab >>Crystallographic Characterization of U2CrN3 Structure and Formation Mechanism
Show others...
(English)Manuscript (preprint) (Other academic)
National Category
Other Materials Engineering
Identifiers
urn:nbn:se:kth:diva-324613 (URN)
Note

QCR 20230308

Available from: 2023-03-08 Created: 2023-03-08 Last updated: 2023-03-08Bibliographically approved

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Mishchenko, Yulia

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