Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels
Cr-doped UO<sub>2</sub> as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO<sub>2</sub> nuclear fuels in a deep geological di...
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MDPI AG
2021-10-01
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| Online Access: | https://www.mdpi.com/1996-1944/14/20/6160 |
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| author | Philip Kegler Martina Klinkenberg Andrey Bukaemskiy Gabriel L. Murphy Guido Deissmann Felix Brandt Dirk Bosbach |
| author_facet | Philip Kegler Martina Klinkenberg Andrey Bukaemskiy Gabriel L. Murphy Guido Deissmann Felix Brandt Dirk Bosbach |
| author_sort | Philip Kegler |
| collection | DOAJ |
| description | Cr-doped UO<sub>2</sub> as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO<sub>2</sub> nuclear fuels in a deep geological disposal facility. The investigation of suitable model materials in a step wise bottom-up approach can provide insights into the corrosion behavior of spent Cr-doped nuclear fuels. Here, we present new wet chemical approaches providing the basis for such model systems, namely co-precipitation and wet coating. Both were successfully tested and optimized, based on detailed analyses of all synthesis steps and parameters: Cr-doping method, thermal treatment, reduction of U<sub>3</sub>O<sub>8</sub> to UO<sub>2</sub>, green body production, and pellet sintering. Both methods enable the production of suitable model systems with a similar microstructure and density as a reference sample from AREVA. In comparison with results from the classical powder route, similar trends upon grain size and lattice parameter were determined. The results of this investigation highlight the significance of subtly different synthesis routes on the properties of Cr-doped UO<sub>2</sub> ceramics. They enable a reproducible tailor-made well-defined microstructure, a homogeneous doping, for example, with lanthanides or alpha sources, the introduction of metallic particles, and a dust-free preparation. |
| first_indexed | 2024-03-10T06:25:08Z |
| format | Article |
| id | doaj.art-9ebdd408f0c34eb8a3f222bb84a7ceca |
| institution | Directory Open Access Journal |
| issn | 1996-1944 |
| language | English |
| last_indexed | 2024-03-10T06:25:08Z |
| publishDate | 2021-10-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Materials |
| spelling | doaj.art-9ebdd408f0c34eb8a3f222bb84a7ceca2023-11-22T19:00:01ZengMDPI AGMaterials1996-19442021-10-011420616010.3390/ma14206160Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear FuelsPhilip Kegler0Martina Klinkenberg1Andrey Bukaemskiy2Gabriel L. Murphy3Guido Deissmann4Felix Brandt5Dirk Bosbach6Forschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyForschungszentrum Jülich GmbH, Institute of Energy and Climate Research—Nuclear Waste Management and Reactor Safety (IEK-6), 52428 Jülich, GermanyCr-doped UO<sub>2</sub> as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO<sub>2</sub> nuclear fuels in a deep geological disposal facility. The investigation of suitable model materials in a step wise bottom-up approach can provide insights into the corrosion behavior of spent Cr-doped nuclear fuels. Here, we present new wet chemical approaches providing the basis for such model systems, namely co-precipitation and wet coating. Both were successfully tested and optimized, based on detailed analyses of all synthesis steps and parameters: Cr-doping method, thermal treatment, reduction of U<sub>3</sub>O<sub>8</sub> to UO<sub>2</sub>, green body production, and pellet sintering. Both methods enable the production of suitable model systems with a similar microstructure and density as a reference sample from AREVA. In comparison with results from the classical powder route, similar trends upon grain size and lattice parameter were determined. The results of this investigation highlight the significance of subtly different synthesis routes on the properties of Cr-doped UO<sub>2</sub> ceramics. They enable a reproducible tailor-made well-defined microstructure, a homogeneous doping, for example, with lanthanides or alpha sources, the introduction of metallic particles, and a dust-free preparation.https://www.mdpi.com/1996-1944/14/20/6160UO<sub>2</sub>dopingwet chemical preparationchromiumspent nuclear fuelceramics |
| spellingShingle | Philip Kegler Martina Klinkenberg Andrey Bukaemskiy Gabriel L. Murphy Guido Deissmann Felix Brandt Dirk Bosbach Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels Materials UO<sub>2</sub> doping wet chemical preparation chromium spent nuclear fuel ceramics |
| title | Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels |
| title_full | Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels |
| title_fullStr | Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels |
| title_full_unstemmed | Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels |
| title_short | Chromium Doped UO<sub>2</sub>-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels |
| title_sort | chromium doped uo sub 2 sub based ceramics synthesis and characterization of model materials for modern nuclear fuels |
| topic | UO<sub>2</sub> doping wet chemical preparation chromium spent nuclear fuel ceramics |
| url | https://www.mdpi.com/1996-1944/14/20/6160 |
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