kth.sePublications
Change search
Refine search result
1 - 9 of 9
CiteExportLink to result list
Permanent link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
Rows per page
  • 5
  • 10
  • 20
  • 50
  • 100
  • 250
Sort
  • Standard (Relevance)
  • Author A-Ö
  • Author Ö-A
  • Title A-Ö
  • Title Ö-A
  • Publication type A-Ö
  • Publication type Ö-A
  • Issued (Oldest first)
  • Issued (Newest first)
  • Created (Oldest first)
  • Created (Newest first)
  • Last updated (Oldest first)
  • Last updated (Newest first)
  • Disputation date (earliest first)
  • Disputation date (latest first)
  • Standard (Relevance)
  • Author A-Ö
  • Author Ö-A
  • Title A-Ö
  • Title Ö-A
  • Publication type A-Ö
  • Publication type Ö-A
  • Issued (Oldest first)
  • Issued (Newest first)
  • Created (Oldest first)
  • Created (Newest first)
  • Last updated (Oldest first)
  • Last updated (Newest first)
  • Disputation date (earliest first)
  • Disputation date (latest first)
Select
The maximal number of hits you can export is 250. When you want to export more records please use the Create feeds function.
  • 1.
    El Jamal, Sawsan
    et al.
    KTH, School of Engineering Sciences in Chemistry, Biotechnology and Health (CBH), Chemistry, Applied Physical Chemistry.
    Mishchenko, Yulia
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT.
    Jonsson, Mats
    KTH, School of Engineering Sciences in Chemistry, Biotechnology and Health (CBH), Chemistry, Applied Physical Chemistry.
    Uranium Nitride Stability in Aqueous Solutions under Anoxic and Oxidizing Conditions– Expected Behaviour under Repository Conditions in Comparison to Alternative Nuclear Fuel MaterialsIn: Article in journal (Other academic)
  • 2.
    Mishchenko, Yulia
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT. KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Engineered microstructure composites as means of improving the oxidation resistance of uranium nitride2023Doctoral 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.

    Download full text (pdf)
    fulltext
  • 3.
    Mishchenko, Yulia
    et al.
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT.
    Johnson, Kyle D.
    Studsvik Nucl AB, Nyköping, Sweden..
    Jadernas, Daniel
    Studsvik Nucl AB, Nyköping, Sweden..
    Wallenius, Janne
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
    Lopes, Denise Adorno
    KTH. KTH Royal Inst Technol, Stockholm, Sweden.;Westinghouse Elect Sweden AB, Västerås, Sweden..
    Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains2021In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 556, article id 153249Article in journal (Refereed)
    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.

  • 4.
    Mishchenko, Yulia
    et al.
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT.
    Johnson, Kyle D.
    Studsvik Nucl AB, Nyköping, Sweden..
    Wallenius, Janne
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
    Lopes, Denise Adorno
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety. KTH Royal Inst Technol, Stockholm, Sweden.;Westinghouse Elect Sweden AB, Västerås, Sweden..
    Design and fabrication of UN composites: From first principles to pellet production2021In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 553, p. 153047-, article id 153047Article in journal (Refereed)
    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.

  • 5.
    Mishchenko, Yulia
    et al.
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT.
    Patnaik, Sobhan
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Charatsidou, Elina
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Wallenius, Janne
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
    Lopes, Denise Adorno
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering. Westinghouse Elect Sweden AB, Västerås, Sweden..
    Potential accident tolerant fuel candidate: Investigation of physical properties of the ternary phase U2CrN32022In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 568, article id 153851Article in journal (Refereed)
    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.

  • 6.
    Mishchenko, Yulia
    et al.
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT. KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Patnaik, Sobhan
    Wallenius, Janne
    Adorno Lopes, Denise
    Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solutionManuscript (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.

  • 7.
    Mishchenko, Yulia
    et al.
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT. KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering. KTH, School of Industrial Engineering and Management (ITM), Materials Science and Engineering, Structures.
    Patnaik, Sobhan
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Wallenius, Janne
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
    Lopes, Denise Adorno
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering. Westinghouse Electric Sweden AB, Västerås, Sweden.
    Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution2023In: Nuclear Materials and Energy, E-ISSN 2352-1791, Vol. 35, article id 101459Article in journal (Refereed)
    Abstract [en]

    Thermophysical properties and oxidation behaviour of the composite pellet UN–20 vol%ZrN were investigated experimentally and compared with the behaviour of the pure UN pellet. A compound of a single 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, similar to pure UN. The obtained value for the average linear thermal expansion coefficient is α¯ = 7.94 × 10-6/K, which compares well to UN (α¯ = 7.95 × 10-6/K) for the same temperature range. The degradation behaviour of the composite pellet UN-20 vol%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.

  • 8.
    Patnaik, Sobhan
    et al.
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Mishchenko, Yulia
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT. KTH, School of Engineering Sciences (SCI), Physics, Nuclear Engineering.
    Stansby, Jennifer
    Fazi, Andrea
    Peterson, Vanessa
    Jadernas, Daniel
    Thuvander, Mattias
    Johnson, Kyle
    Obbard, Edward
    Adorno Lopes, Denise
    Crystallographic Characterization of U2CrN3 Structure and Formation MechanismManuscript (preprint) (Other academic)
  • 9.
    Wallenius, Janne
    et al.
    LeadCold Reactors, Vallhallavägen 79, Stockholm, Sweden.
    Jolkkonen, Mikael
    KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
    Mishchenko, Yulia
    KTH, School of Engineering Sciences (SCI), Centres, Centre for Nuclear Energy Technology, CEKERT.
    Laurin, Daniel
    Promation Nuclear, Oakville, ON, Canada.
    Towards industrial-scale manufacture of UN fuel for water-cooled reactors2020In: GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference, American Nuclear Society , 2020, p. 1144-1146Conference paper (Refereed)
    Abstract [en]

    The use of U15N fuel in water cooled reactors permits to increase the fuel average residence time by 40-60%1,2. This corresponds to a reduced cost for manufacture of fuel assemblies and waste packages, as well as a reduced cost for refuelling. The industrial application of UN fuels requires to improve the resistance of the fuel to steam corrosion and to develop methods for manufacture that are commercially competitive. In this contribution we describe the activities carried out at LeadCold, KTH and Promation Nuclear towards these goals. 

1 - 9 of 9
CiteExportLink to result list
Permanent link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf