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DTEND;TZID=Europe/Zurich:20200709T190000
UID:7e6f5c192c05cb2be86ccd96e3c8792c
DTSTAMP:1776324880
LOCATION:ONLINE VIA ZOOM
ORGANIZER:Alumni Community of the FUSION-EP Master Program
DESCRIPTION:Hydrogen is one of the key ingredients for fusion energy. During operations, tokamak walls are under bombardment of highly energetic hydrogen ions, which can penetrate the materials. Knowing the hydrogen content of these plasma-facing materials is crucial for several reasons. First from a safety point of view, the tritium content in the inner-vessel of the tokamak is limited to 700 g. Secondly, tritium penetrating the first wall material could reach the cooling system which must then be purified. Finally, hydrogen can brittle the materials and therefore reduce the lifetime of plasma facing components. The behaviour of hydrogen can be investigated by lab experiments but also simulated with thermokinetic models which is the topic of this talk. We’ll present the finite element code FESTIM developed by CEA and CNRS. A particular focus is made on ITER divertor and tungsten monoblocks and hydrogen retention is estimated in the whole divertor.
URL;VALUE=URI:https://fusionep-talks.egyplasma.com/calender/event.php?variableName=7e6f5c192c05cb2be86ccd96e3c8792c
SUMMARY:Tracking hydrogen in ITER\'s tungsten plasma facing components 
DTSTART;TZID=Europe/Zurich:20200709T180000
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