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1Univ Orléans, Univ Tours, INSA CVL, Lamé, EA 7494, France; 2Andra, 92298 Chatenay-Malabry, France
5:20pm - 5:40pm ID: 222 / PS #12: 004
Comparing uncertainty quantification methods in the context of safety analyses for high-level nuclear waste disposal systems
Merle Marie Bjorge1,2, Aqeel Afzal Chaudhry2, Kata Kurgyis2, Wolfram Rühaak1,3, Thomas Nagel2,4
1Bundesgesellschaft für Endlagerung mbH (BGE), Peine, Germany; 2Geotechnical Institute, Technische Universität Bergakademie Freiberg, Freiberg, Germany; 3Technische Universität Darmstadt, Department of Geothermal Science and Technology, Darmstadt, Germany; 4Freiberg Center for Water Research (ZeWaF), Freiberg, Germany
5:40pm - 6:00pm ID: 232 / PS #12: 005
Modelling the impact of design variations in a spent nuclear fuel repository on near-field sulfide fluxes and Cu canister corrosion depths
Jin Ma1, Peter Alt-Epping1, Mika Niskanen2, Barbara Pastina2, Paul Wersin1
1University of Bern, Switzerland; 2Posiva Oy, Finland