Experimental investigation of uranium release from spent nuclear fuels under conditions expected in a deep geological repository

Abstract 2 and mixed-oxide, MOX, fuels) under geochemical conditions (pH, redox milieu, gas atmosphere and ionic strength) representative of various repository concepts and radiolytic reactions on SNF dissolution mechanisms. 2 and MOX fuels during up to 1629 d of leaching in salt brines, granitic/bentonitic or cementitious groundwaters under Ar or Ar/H2 atmospheres. 2 and MOX fuels). A similar behaviour is observed for other redox-sensitive actinides. The release rate of uranium decreases significantly in all experiments within first 400 d of leaching. Although the rate is very low, it is > 0, and a continuous release is observed. A comparison of the results from SNF experiments under various redox conditions demonstrates that oxidative matrix dissolution is inhibited due to the presence of hydrogen. Our results are discussed in the context of the outcome of international research programmes on SNF corrosion. These findings are considered to be of relevance for the definition of source terms for various irradiated LWR fuels in safety investigations for a DGR in Germany.

Object Details

• Location: Deutsche Nationalbibliothek Frankfurt am Main
• Extent: Online-Ressource
• Language: Englisch

References and Relationships

• Bibliographic citation: Experimental investigation of uranium release from spent nuclear fuels under conditions expected in a deep geological repository ; volume:2 ; year:2023 ; pages:149-150 ; extent:2 ; Safety of nuclear waste disposal ; 2 (2023), 149-150 (gesamt 2)

Contributors, Places and Time

• Creator: Herm, Michel ; Walschburger, Arndt ; König, Tobias ; Metz, Volker ; Geckeis, Horst

Further information

• DOI: 10.5194/sand-2-149-2023
• URN: urn:nbn:de:101:1-2023090704311973204696
• Rights: Open Access; Der Zugriff auf das Objekt ist unbeschränkt möglich.
• Last update: 14.08.2025, 10:48 AM CEST