FRINK Linked Data Fragments server

Matches in SemOpenAlex for { <https://semopenalex.org/work/W4386479248> ?p ?o ?g. }

• W4386479248 endingPage "150" @default.
• W4386479248 startingPage "149" @default.
• W4386479248 abstract "Abstract. Direct disposal of spent nuclear fuel (SNF) in a deep geological repository is planned for the long-term management of the highly radioactive waste discharged from the light water reactors (LWRs) of nuclear power plants in Germany. The aim is to safely isolate the radionuclide inventory from the biosphere, ad infinitum, making use of a multi-barrier system consisting of technical, geotechnical and geological barriers interposed between the emplaced waste and the environment. Still, reversibility measures including retrievability of the waste products are considered in this concept. Internationally, in safety assessments for deep underground repositories (DGRs), the access of groundwater, followed by failure of canisters and finally loss of the SNF's cladding integrity is considered in the long term. Hence, the evaluation of the performance of SNF in the near field of a deep geological repository requires process understanding of SNF dissolution and rates, in addition to the quantification of the radionuclide release from SNF under reducing conditions of a breached container. With the aim to derive a radionuclide source term, the SNF dissolution and alteration processes can be assigned to two steps, namely the (i) instantaneous release of radionuclides upon cladding failure from gap and grain boundaries and (ii) a long-term release that results from the dissolution of the fuel grains themselves (Ewing, 2015). Since most radionuclides produced during irradiation of nuclear fuel in a reactor are trapped within the SNF matrix, understanding the processes leading to the dissolution of the matrix and its dissolution rates are of particular interest for post-closure safety assessments (Pastina and LaVerne, 2021). Research at the Institute for Nuclear Waste Disposal (INE) at the Karlsruhe Institute of Technology (KIT) has focused, for more than 25 years, on the behaviour of SNF (irradiated UO2 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. This contribution will give an overview on the radionuclide release from dissolving SNFs under repository conditions. In particular, uranium released into solution from UO2 and MOX fuels during up to 1629 d of leaching in salt brines, granitic/bentonitic or cementitious groundwaters under Ar or Ar/H2 atmospheres. As observed in other published studies on SNF dissolution under reducing conditions, a large scatter of the uranium concentration is seen in the initial stages of our experiments. After about 1 year of leaching, the aqueous concentration of uranium slowly approaches the solubility limit of U(IV), independent of the type of studied SNF samples (various irradiated UO2 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." @default.
• W4386479248 created "2023-09-07" @default.
• W4386479248 creator A5029581609 @default.
• W4386479248 creator A5047075064 @default.
• W4386479248 creator A5051402183 @default.
• W4386479248 creator A5060056588 @default.
• W4386479248 creator A5079041687 @default.
• W4386479248 date "2023-09-06" @default.
• W4386479248 modified "2023-10-01" @default.
• W4386479248 title "Experimental investigation of uranium release from spent nuclear fuels under conditions expected in a deep geological repository" @default.
• W4386479248 cites W2047796389 @default.
• W4386479248 cites W3201375966 @default.
• W4386479248 doi "https://doi.org/10.5194/sand-2-149-2023" @default.
• W4386479248 hasPublicationYear "2023" @default.
• W4386479248 type Work @default.
• W4386479248 citedByCount "0" @default.
• W4386479248 crossrefType "journal-article" @default.
• W4386479248 hasAuthorship W4386479248A5029581609 @default.
• W4386479248 hasAuthorship W4386479248A5047075064 @default.
• W4386479248 hasAuthorship W4386479248A5051402183 @default.
• W4386479248 hasAuthorship W4386479248A5060056588 @default.
• W4386479248 hasAuthorship W4386479248A5079041687 @default.
• W4386479248 hasBestOaLocation W43864792481 @default.
• W4386479248 hasConcept C116915560 @default.
• W4386479248 hasConcept C121332964 @default.
• W4386479248 hasConcept C127313418 @default.
• W4386479248 hasConcept C127413603 @default.
• W4386479248 hasConcept C147789679 @default.
• W4386479248 hasConcept C158973077 @default.
• W4386479248 hasConcept C185544564 @default.
• W4386479248 hasConcept C185592680 @default.
• W4386479248 hasConcept C187320778 @default.
• W4386479248 hasConcept C191897082 @default.
• W4386479248 hasConcept C192562407 @default.
• W4386479248 hasConcept C21553396 @default.
• W4386479248 hasConcept C2779819667 @default.
• W4386479248 hasConcept C36456112 @default.
• W4386479248 hasConcept C39432304 @default.
• W4386479248 hasConcept C513653683 @default.
• W4386479248 hasConcept C548081761 @default.
• W4386479248 hasConcept C555451288 @default.
• W4386479248 hasConcept C7083945 @default.
• W4386479248 hasConcept C76177295 @default.
• W4386479248 hasConcept C88380143 @default.
• W4386479248 hasConcept C89690796 @default.
• W4386479248 hasConceptScore W4386479248C116915560 @default.
• W4386479248 hasConceptScore W4386479248C121332964 @default.
• W4386479248 hasConceptScore W4386479248C127313418 @default.
• W4386479248 hasConceptScore W4386479248C127413603 @default.
• W4386479248 hasConceptScore W4386479248C147789679 @default.
• W4386479248 hasConceptScore W4386479248C158973077 @default.
• W4386479248 hasConceptScore W4386479248C185544564 @default.
• W4386479248 hasConceptScore W4386479248C185592680 @default.
• W4386479248 hasConceptScore W4386479248C187320778 @default.
• W4386479248 hasConceptScore W4386479248C191897082 @default.
• W4386479248 hasConceptScore W4386479248C192562407 @default.
• W4386479248 hasConceptScore W4386479248C21553396 @default.
• W4386479248 hasConceptScore W4386479248C2779819667 @default.
• W4386479248 hasConceptScore W4386479248C36456112 @default.
• W4386479248 hasConceptScore W4386479248C39432304 @default.
• W4386479248 hasConceptScore W4386479248C513653683 @default.
• W4386479248 hasConceptScore W4386479248C548081761 @default.
• W4386479248 hasConceptScore W4386479248C555451288 @default.
• W4386479248 hasConceptScore W4386479248C7083945 @default.
• W4386479248 hasConceptScore W4386479248C76177295 @default.
• W4386479248 hasConceptScore W4386479248C88380143 @default.
• W4386479248 hasConceptScore W4386479248C89690796 @default.
• W4386479248 hasFunder F4320320300 @default.
• W4386479248 hasLocation W43864792481 @default.
• W4386479248 hasOpenAccess W4386479248 @default.
• W4386479248 hasPrimaryLocation W43864792481 @default.
• W4386479248 hasRelatedWork W1499129449 @default.
• W4386479248 hasRelatedWork W1566831221 @default.
• W4386479248 hasRelatedWork W1987241747 @default.
• W4386479248 hasRelatedWork W2087121801 @default.
• W4386479248 hasRelatedWork W2181594058 @default.
• W4386479248 hasRelatedWork W2275223214 @default.
• W4386479248 hasRelatedWork W2360458116 @default.
• W4386479248 hasRelatedWork W2561702579 @default.
• W4386479248 hasRelatedWork W2699525619 @default.
• W4386479248 hasRelatedWork W298091470 @default.
• W4386479248 hasVolume "2" @default.
• W4386479248 isParatext "false" @default.
• W4386479248 isRetracted "false" @default.
• W4386479248 workType "article" @default.