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Response of ZrC to swift heavy ion irradiation

Minnette, Jacob ; Williams, Evan ; Cureton, William ; Solomon, Alexandre ; O’Quinn, Eric ; Kurley, Matthew ; Hunt, Rodney D. ; Park, Changyong ; Schubert, Ina ; Trautmann, Christina ; Lang, Maik (2023)
Response of ZrC to swift heavy ion irradiation.
In: Journal of Applied Physics, 134 (18)
doi: 10.1063/5.0165821
Artikel, Bibliographie

Kurzbeschreibung (Abstract)

Zirconium carbide (ZrC) is commonly used for energy sector research, as well as a surrogate for the proposed advanced nuclear fuel candidate uranium carbide. This study investigates structural modifications to nanocrystalline and microcrystalline ZrC resulting from dense electronic excitations induced by swift heavy ion exposure. Samples were irradiated with 946 MeV Au ions to various fluences up to 6 x 10(13) ions cm(-2) and characterized using synchrotron-based x-ray diffraction. The evolution of the unit-cell parameter and heterogeneous microstrain were evaluated as a function of fluence and compared with those of nanocrystalline and microcrystalline CeO2 (a surrogate for UO2 fuel) irradiated under identical conditions. Distinct differences were observed in the radiation responses of the carbide and oxide across both grain sizes. Most notably, microcrystalline ZrC exhibits swelling characterized by two distinct regimes, which does not result in saturation at the ion fluences achieved. This contrasts with CeO2, which exhibits the well-documented direct-impact defect accumulation mechanism, reaching a steady-state saturation of swelling at higher fluences. Nanocrystalline CeO2 undergoes more pronounced swelling compared with microcrystalline CeO2, in contrast to nanocrystalline ZrC, which exhibits only minimal unit-cell changes. These results demonstrate that swift heavy ion-induced structural changes can be quite different in carbides and oxides, which must be considered when extrapolating fission-fragment type damage in current fuels to advanced fuels.

Typ des Eintrags: Artikel
Erschienen: 2023
Autor(en): Minnette, Jacob ; Williams, Evan ; Cureton, William ; Solomon, Alexandre ; O’Quinn, Eric ; Kurley, Matthew ; Hunt, Rodney D. ; Park, Changyong ; Schubert, Ina ; Trautmann, Christina ; Lang, Maik
Art des Eintrags: Bibliographie
Titel: Response of ZrC to swift heavy ion irradiation
Sprache: Englisch
Publikationsjahr: 2023
Verlag: AIP Publishing
Titel der Zeitschrift, Zeitung oder Schriftenreihe: Journal of Applied Physics
Jahrgang/Volume einer Zeitschrift: 134
(Heft-)Nummer: 18
DOI: 10.1063/5.0165821
Kurzbeschreibung (Abstract):

Zirconium carbide (ZrC) is commonly used for energy sector research, as well as a surrogate for the proposed advanced nuclear fuel candidate uranium carbide. This study investigates structural modifications to nanocrystalline and microcrystalline ZrC resulting from dense electronic excitations induced by swift heavy ion exposure. Samples were irradiated with 946 MeV Au ions to various fluences up to 6 x 10(13) ions cm(-2) and characterized using synchrotron-based x-ray diffraction. The evolution of the unit-cell parameter and heterogeneous microstrain were evaluated as a function of fluence and compared with those of nanocrystalline and microcrystalline CeO2 (a surrogate for UO2 fuel) irradiated under identical conditions. Distinct differences were observed in the radiation responses of the carbide and oxide across both grain sizes. Most notably, microcrystalline ZrC exhibits swelling characterized by two distinct regimes, which does not result in saturation at the ion fluences achieved. This contrasts with CeO2, which exhibits the well-documented direct-impact defect accumulation mechanism, reaching a steady-state saturation of swelling at higher fluences. Nanocrystalline CeO2 undergoes more pronounced swelling compared with microcrystalline CeO2, in contrast to nanocrystalline ZrC, which exhibits only minimal unit-cell changes. These results demonstrate that swift heavy ion-induced structural changes can be quite different in carbides and oxides, which must be considered when extrapolating fission-fragment type damage in current fuels to advanced fuels.

Zusätzliche Informationen:

Artikel-ID: 185901

Fachbereich(e)/-gebiet(e): 11 Fachbereich Material- und Geowissenschaften
11 Fachbereich Material- und Geowissenschaften > Materialwissenschaft
11 Fachbereich Material- und Geowissenschaften > Materialwissenschaft > Fachgebiet Ionenstrahlmodifizierte Materialien
Hinterlegungsdatum: 26 Feb 2024 06:34
Letzte Änderung: 26 Feb 2024 10:14
PPN: 515808512
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