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Visar resultat 1 - 5 av 25 avhandlingar som matchar ovanstående sökkriterier.

  1. 1. Radiation Induced Oxidative Dissolution of UO2

    Författare :Ella Ekeroth; Mats Jonsson; Bernd Grambow; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; radiation; radiolysis; UO2; spent nuclear fuel; radicals; oxidants; reductants; rate constants; dissolution; H2O2; H2; Nuclear chemistry; Kärnkemi;

    Sammanfattning : Sammanfattning Denna doktorsavhandling berör oxidativ upplösning av UO2 (som modellsubstans för utbränt kärnbränsle) orsakad av radiolys av vatten samt effekten av H2 på denna denna process. Hastighetskonstanter för oxidation av UO2-pulver med olika oxidanter såsom H2O2 har bestämts experimentellt. LÄS MER

  3. 2. Physical and Chemical Aspects of Radiation Induced Oxidative Dissolution of UO2

    Författare :Olivia Roth; Mats Jonsson; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; UO2; spent nuclear fuel; dissolution; oxidation; radiolysis; irradiation; particle size; modeling; Chemistry; Kemi;

    Sammanfattning : Denna licensiatavhandling behandlar oxidativ upplösning av UO2. Upplösning av UO2 studeras huvudsakligen då UO2-matrisen hos använt kärnbränsle förväntas fungera som en barriär mot frigörande av radionuklider i ett framtida djupförvar. LÄS MER

  4. 3. Radiation induced dissolution of model compounds for spent nuclear fuel : mechanistic understanding of oxidative dissolution and its inhibition

    Författare :Sara Nilsson; Mats Jonsson; Lara Duro; KTH; []
    Nyckelord :;

    Sammanfattning : This doctoral thesis is focused on radiation induced oxidative dissolution of UO2, Pd-doped UO2, SIMFUEL (as model substances for spent nuclear fuel) and UN (a possible future fuel) and inhibition of the oxidative dissolution. H2O2 is assumed to be the most important oxidant for spent nuclear fuel dissolution under deep repository conditions. LÄS MER

  5. 4. Oxidative Dissolution of Spent Fuel and Release of Nuclides from a Copper/Iron Canister : Model Developments and Applications

    Författare :Longcheng Liu; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; model; oxidative dissolution; spent fuel; radiolysis; release; mass transport; radionuclide; hydrogen; corrosion; canister; near field; repository; Chemical engineering; Kemiteknik;

    Sammanfattning : Three models have been developed and applied in the performance assessment of a final repository. They are based on accepted theories and experimental results for known and possible mechanisms that may dominate in the oxidative dissolution of spent fuel and the release of nuclides from a canister. LÄS MER

  7. 5. Experimental studies of radiation-induced dissolution of UO2 : The effect of intrinsic solid phase properties and external factors

    Författare :Alexandre Barreiro Fidalgo; Mats Jonsson; David Shoesmith; KTH; []
    Nyckelord :NATURVETENSKAP; NATURAL SCIENCES; Oxidation; dissolution; uranium dioxide; gadolinium; bentonite; sulfide; hydrogen; gamma radiation; radiolysis; hydrogen peroxide; hydroxyl radical; repository; Kemi; Chemistry;

    Sammanfattning : Dissolution of the UO2 matrix is one of the potential routes for radionuclide release in a future deep geological repository for spent nuclear fuel. This doctoral thesis focuses on interfacial reactions of relevance in radiation-induced dissolution of UO2 and is divided in two parts:In the first part, we sought to explore the effects of solid phase composition:The impact of surface stoichiometry on the reactivity of UO2 towards aqueous radiolytic oxidants was studied. LÄS MER