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Johnson, Kyle
Publications (7 of 7) Show all publications
Liu, J., Gasparrini, C., White, J. T., Johnson, K., Lopes, D. A., Peterson, V. K., . . . Obbard, E. G. (2023). Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction. Journal of Nuclear Materials, 575, 154215, Article ID 154215.
Open this publication in new window or tab >>Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction
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2023 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 575, p. 154215-, article id 154215Article in journal (Refereed) Published
Abstract [en]

In situ neutron powder diffraction experiments are applied to physical, kinetic, and microstructural characterization of uranium mononitride as a promising light water reactor fuel material. The temperaturevariable coefficient of thermal expansion and isotropic Debye Waller factors are obtained by sequential Rietveld refinement over 499-1873 K. Oxidation of a UN pellet (95.2% density) under flow of 11 mg/min D 2 O is observed to initiate above 623 K and the rate increases by a factor of approximately 10 from 673 to 773 K, with activation energy 50.6 +/- 1.3 kJ/mol; uranium oxide is the only solid corrosion product.Crown Copyright

Place, publisher, year, edition, pages
Elsevier BV, 2023
National Category
Materials Chemistry
Identifiers
urn:nbn:se:kth:diva-324456 (URN)10.1016/j.jnucmat.2022.154215 (DOI)000920761900001 ()2-s2.0-85145208346 (Scopus ID)
Note

QC 20230315

Available from: 2023-03-15 Created: 2023-03-15 Last updated: 2023-03-15Bibliographically approved
Obbard, E. G., Johnson, K. D., Burr, P. A., Lopes, D. A., Gregg, D. J., Liss, K.-D. -., . . . Middleburgh, S. C. (2018). Anisotropy in the thermal expansion of uranium silicide measured by neutron diffraction. Journal of Nuclear Materials, 508, 516-520
Open this publication in new window or tab >>Anisotropy in the thermal expansion of uranium silicide measured by neutron diffraction
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2018 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 508, p. 516-520Article in journal (Refereed) Published
Abstract [en]

In-situ neutron diffraction patterns were collected for a sample of as-cast U3Si2 during heating to 1600 degrees C. Anomalous changes were observed above 1000 degrees C, including the formation of a new diffraction peak not belonging to P4/mbm U3Si2, unequal changes in the peak intensities and onset of anisotropic lattice expansion. The large data-set enabled derivation of a function-fitted isotropic thermal expansion coefficient to high precision, in close agreement with previous dilatometry results but reducing linearly with temperature over the studied interval. Anisotropy in the instantaneous lattice thermal expansion corresponded to anomalies reported by White et al. (2015) at a similar temperature.

Place, publisher, year, edition, pages
Elsevier, 2018
Keywords
Accident tolerant fuel, In-situ neutron diffraction, Thermal expansion, Uranium silicide, Phase transformation
National Category
Physical Sciences
Identifiers
urn:nbn:se:kth:diva-232746 (URN)10.1016/j.jnucmat.2018.04.049 (DOI)000439134500057 ()2-s2.0-85048301414 (Scopus ID)
Note

QC 20180807

Available from: 2018-08-07 Created: 2018-08-07 Last updated: 2024-03-18Bibliographically approved
Lopes, D. A., Uygur, S. & Johnson, K. (2017). Degradation of UN and UN-U3Si2 pellets in steam environment. Journal of Nuclear Science and Technology, 54(4), 405-413
Open this publication in new window or tab >>Degradation of UN and UN-U3Si2 pellets in steam environment
2017 (English)In: Journal of Nuclear Science and Technology, ISSN 0022-3131, E-ISSN 1881-1248, Vol. 54, no 4, p. 405-413Article in journal (Refereed) Published
Abstract [en]

In this work, a systematic study of the degradation of UN pellets (density range 96%-99.9% and grain size of 6-24 mu m) and UN-10%U3Si2 (wt%) composite in a steam environment is presented. Static steam autoclave tests were performed at 300 degrees C and 9 MPa for period of 0.5-1.5 hours. Microstructural analyses of UN pellets show that, in a high-pressure atmosphere, the fuel collapses principally by intergranular cracking generated by the precipitation of an oxide phase in the grain boundaries. This mechanism leads to a premature mechanical collapse of the fuel pellet, exposing fresh surfaces to steam, and ultimately accelerating the oxidation process. Increasing density (specifically eliminating open porosity) was found to delay the oxidation process, while increasing grain size was found to accelerate the degradation process due to a greater susceptibility to mechanical fracture by way of intergranular oxidation. The performance of the UN-10%U3Si2 composite proved to be better when compared to UN. The U3Si2 phase served to stabilize the UN grain boundary interface and reacted preferentially with the steam, thereby altering the failure mechanism. In this composite material, the cracking was predominantly intra-granular and the exposure of fresh surfaces was limited, resulting in a slower degradation process.

Place, publisher, year, edition, pages
Taylor & Francis, 2017
Keywords
Fuel, nuclear fuel, accident
National Category
Ceramics and Powder Metallurgical Materials
Identifiers
urn:nbn:se:kth:diva-205441 (URN)10.1080/00223131.2016.1274689 (DOI)000395711100001 ()2-s2.0-85014802142 (Scopus ID)
Note

QC 20170522

Available from: 2017-05-22 Created: 2017-05-22 Last updated: 2025-02-09Bibliographically approved
Johnson, K., Ström, V., Wallenius, J. & Lopes, D. A. (2017). Oxidation of accident tolerant fuel candidates. Journal of Nuclear Science and Technology, 54(3), 280-286
Open this publication in new window or tab >>Oxidation of accident tolerant fuel candidates
2017 (English)In: Journal of Nuclear Science and Technology, ISSN 0022-3131, E-ISSN 1881-1248, Vol. 54, no 3, p. 280-286Article in journal (Refereed) Published
Abstract [en]

In this study, the oxidation of various accident tolerant fuel candidates produced under different conditions have been evaluated and compared relative to the reference standard–UO2. The candidates considered in this study were UN, U3Si2, U3Si5, and a composite material composed of UN–U3Si2. With the spark plasma sintering (SPS) method, it was possible to fabricate samples of UN with varying porosity, as well as a high-density composite of UN–U3Si2 (10%). Using thermogravimetry in air, the oxidation behaviors of each material and the various microstructures of UN were assessed. These results reveal that it is possible to fabricate UN to very high densities using the SPS method, such that its resistance to oxidation can be improved compared to U3Si5 and UO2, and compete favorably with the principal ATF candidates, U3Si2, which shows a particularly violent reaction under the conditions of this study, and the UN–U3Si2 (10%) composite.

Place, publisher, year, edition, pages
Taylor & Francis, 2017
Keywords
accident tolerant fuel, Nuclear fuel, oxidation, SPS sintering, uranium nitride, uranium nitride silicide composite, uranium silicide
National Category
Physical Sciences
Identifiers
urn:nbn:se:kth:diva-201127 (URN)10.1080/00223131.2016.1262297 (DOI)000394716500002 ()2-s2.0-85001948816 (Scopus ID)
Note

QC 20170208

Available from: 2017-02-08 Created: 2017-02-08 Last updated: 2023-12-05Bibliographically approved
Johnson, K. D., Raftery, A. M., Lopes, D. A. & Wallenius, J. (2016). Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications. Journal of Nuclear Materials, 477, 18-23
Open this publication in new window or tab >>Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications
2016 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 477, p. 18-23Article in journal (Refereed) Published
Abstract [en]

In this study, U3Si2 was synthesized via the use of arc-melting and mixed with UN powders, which together were sintered using the SPS method. The study revealed a number of interesting conclusions regarding the stability of the system - namely the formation of a probable but as yet unidentified ternary phase coupled with the reduction of the stoichiometry in the nitride phase - as well as some insights into the mechanics of the sintering process itself. By milling the silicide powders and reducing its particle size ratio compared to UN, it was possible to form a high density UN-U3Si2 composite, with desirable microstructural characteristics for accident tolerant fuel applications.

Place, publisher, year, edition, pages
Elsevier, 2016
Keywords
Nuclear fuel, Accident tolerant fuel, Uranium nitride, Uranium silicide, SPS, U-N-Si system
National Category
Mineral and Mine Engineering
Identifiers
urn:nbn:se:kth:diva-189348 (URN)10.1016/j.jnucmat.2016.05.004 (DOI)000377327000002 ()2-s2.0-84966271209 (Scopus ID)
Note

QC 20160707

Available from: 2016-07-07 Created: 2016-07-04 Last updated: 2024-03-15Bibliographically approved
Jolkkonen, M., Johnson, K. & Wallenius, J. (2016). Fuel for water-cooled nuclear reactors. WIPO (PCT) WO2016122374A1.
Open this publication in new window or tab >>Fuel for water-cooled nuclear reactors
2016 (English)Patent (Other (popular science, discussion, etc.))
National Category
Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-249117 (URN)
Patent
WIPO (PCT) WO2016122374A1
Note

Endast publicerat, QC 20210224

Available from: 2019-04-10 Created: 2019-04-10 Last updated: 2022-06-26Bibliographically approved
Johnson, K. D., Wallenius, J., Jolkkonen, M. & Claisse, A. (2016). Spark plasma sintering and porosity studies of uranium nitride. Journal of Nuclear Materials, 473, 13-17
Open this publication in new window or tab >>Spark plasma sintering and porosity studies of uranium nitride
2016 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 473, p. 13-17Article in journal (Refereed) Published
Abstract [en]

In this study, a number of samples of UN sintered by the SPS method have been fabricated, and highly pure samples ranging in density from 68% to 99.8%TD-corresponding to an absolute density of 14.25 g/cm3 out of a theoretical density of 14.28 g/cm3-have been fabricated. By careful adjustment of the sintering parameters of temperature and applied pressure, the production of pellets of specific porosity may now be achieved between these ranges. The pore closure behaviour of the material has also been documented and compared to previous studies of similar materials, which demonstrates that full pore closure using these methods occurs near 97.5% of relative density.

Place, publisher, year, edition, pages
Elsevier, 2016
Keywords
Generation IV, Nuclear fuel, Pore closure, Sintering, SPS, Uranium nitride, Nitrides, Nuclear fuels, Porosity, Spark plasma sintering, Uranium, Uranium compounds, Number of samples, Relative density, Sintering parameters, Specific porosity, Theoretical density
National Category
Mineral and Mine Engineering Physical Sciences
Identifiers
urn:nbn:se:kth:diva-186981 (URN)10.1016/j.jnucmat.2016.01.037 (DOI)000373490700003 ()2-s2.0-84959376726 (Scopus ID)
Note

QC 20160518

Available from: 2016-05-18 Created: 2016-05-16 Last updated: 2024-03-18Bibliographically approved
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