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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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Energy Secretary to speak at the 2025 ANS Winter Conference & Expo
In less than two weeks, the American Nuclear Society’s second annual conference of the year, the 2025 ANS Winter Conference & Expo, will come to Washington, D.C.
Today, ANS is announcing that Energy Secretary Chris Wright will be joining the list of nuclear leaders slated to speak at the conference.
Click here to register for the meeting, which will take place November 9–12 in Washington, D.C., at the Washington Hilton. Be sure to do so before November 7 to take advantage of priority pricing.
Junghee Kim, P. Andrew, R. Reichle
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 185-196
Technical Paper by Monaco ITER Postdoctoral Fellows | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13386
Articles are hosted by Taylor and Francis Online.
Plasma-wall interaction in fusion devices is unavoidable and leads to material erosion, dust formation, and tritium retention. Erosion of plasma-facing material and generation of dust inside ITER can significantly affect the operation. This is because the total in-vessel dust and tritium inventories during an operational campaign are required to be below limits of 1000 and 1 kg, respectively, imposed by safety considerations. To ensure respect of these limits, dust and tritium inventories should be monitored during the operational campaign of ITER. The level of erosion will be monitored by laser ranging techniques. To manage the dust inventory, local dust monitors from a number of locations will measure local dust concentration and accumulation. An additional important issue is dust lying on hot surfaces. In terms of safety, "hot dust" inventory is also strictly limited. Several techniques have been proposed to monitor the hot dust amount. Finally, the in-vessel tritium inventory must be limited and monitored. Assessment of the deficit in the tritium fuel supply is a way of measuring in-vessel tritium retention; however, this will have to be complemented by local surface analysis. Several diagnostic methods are introduced and compared with each other in order to find the most promising ITER-relevant concepts.