Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen
In accordance with the Belgian "supercontainer design" SNF (spent nuclear fuel) will be encapsulated in carbon steel canisters, surrounded by a concrete overpack for disposal in poorly-indurated clay. After re-saturation of the barriers by porewater interactions with the concrete will result in solutions rich in NaOH, KOH and Ca(OH)2. Corrosion studies of SNF in ECW-(evolved cement water)-type solution and YCWCa-(Young cement water with Ca)-type solution were performed under externally applied H2 overpressures over 426 days. Directly after H2 application, Tc concentrations decreased from >10-8 M to concentrations below detection limit. Based on the fractional release of selected fission products, low matrix dissolution rates or ∼10-8/day were found in both experiments. U concentrations decreased finally to 1.5 × 10-9 M (YCWCa) and to 2.1 × 1010 M (ECW), respectively) Am, Np and Pu concentrations were found throughout the experiments below their detection limits indicating an eflective retention process.
Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen
In accordance with the Belgian "supercontainer design" SNF (spent nuclear fuel) will be encapsulated in carbon steel canisters, surrounded by a concrete overpack for disposal in poorly-indurated clay. After re-saturation of the barriers by porewater interactions with the concrete will result in solutions rich in NaOH, KOH and Ca(OH)2. Corrosion studies of SNF in ECW-(evolved cement water)-type solution and YCWCa-(Young cement water with Ca)-type solution were performed under externally applied H2 overpressures over 426 days. Directly after H2 application, Tc concentrations decreased from >10-8 M to concentrations below detection limit. Based on the fractional release of selected fission products, low matrix dissolution rates or ∼10-8/day were found in both experiments. U concentrations decreased finally to 1.5 × 10-9 M (YCWCa) and to 2.1 × 1010 M (ECW), respectively) Am, Np and Pu concentrations were found throughout the experiments below their detection limits indicating an eflective retention process.
Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen
Loida, A. (Autor:in) / Gens, R. (Autor:in) / Bube, C. (Autor:in) / Lemmens, K. (Autor:in) / Cachoir, C. (Autor:in) / Mennecart, T. (Autor:in) / Kienzler, B. (Autor:in)
2012
6 Seiten, 3 Bilder, 10 Quellen
Aufsatz (Konferenz)
Englisch
Materials Characteristics and Dissolution Behavior of Spent Nuclear Fuel
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Interim Storage for spent Nuclear Fuel Elements
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| British Library Online Contents | 2012