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September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Deep geologic repository progress—2025 Update
Editor's note: This article has was originally published in November 2023. It has been updated with new information as of June 2025.
Outside my office, there is a display case filled with rock samples from all over the world. It contains a disk of translucent, orange salt from the Waste Isolation Pilot Plant near Carlsbad, N.M.; a core of white-and-bronze gneiss from the site of the future deep geologic repository in Eurajoki, Finland; several angular chunks of fine-grained, gray claystone from the underground research laboratory at Bure, France; and a piece of coarse-grained granite from the underground research tunnel in Daejeon, South Korea.
Martin Lochter, Reinhard Uhlemann, Jochen Linke
Fusion Science and Technology | Volume 19 | Number 4 | July 1991 | Pages 2101-2111
Technical Paper | Carbon Material Special | doi.org/10.13182/FST91-A29346
Articles are hosted by Taylor and Francis Online.
The high heat flux ion beam test facility at Forschungszentrum Jülich can produce peak power densities of 0.14 to 12 kW/cm2 for pulse lengths of 10 ms to 15 s. Longer pulses up to steady-state operation are possible with reduced power. The total ion beam power can be varied between 70 kW and 6 MW at particle energies of 10 to 60 keV. The particles are hydrogen and helium. The beam illuminates a 1300-cm2 area, which allows a large area for materials tests. The rise time of the beam pulses can be adjusted between 2 and 200 ms, and the pulse repetition rate is between 1 and 5 min. The test facility is equipped with a sample manipulator with a vacuum lock that allows a sample size of 15 × 10 cm with active or passive cooling. The extensive diagnostic system of the test stand, originally designed for developing and conditioning the neutral beam ion sources for the Tokamak Experiment for Technology Oriented Research (TEXTOR), and the diagnostic system of the sample manipulator are described. The results of a materials test series performed for the development of wall materials for the Next European Torus/International Thermonuclear Experimental Reactor (NET/ITER) are shown. Possible upgrades of the facility are also discussed.