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Nuclear Energy Conference & Expo (NECX)
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.
R. Carrera, W. D. Booth, J. L. Anderson, T. Bauer, D. Coffin, T. A. Parish†
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1629-1633
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29574
Articles are hosted by Taylor and Francis Online.
This paper outlines the preliminary conceptual design of a minimum—cost tritium system for a basic ignition experiment whose objective is to produce and control fusion ignited plasmas for scientific study. A system without tritium recycling and tritium reprocessing is envisioned. The fueling requirements can be satisfied by using a tritium storage tank with 20 kCi absorbed in a uranium bed which will be delivered to the facility every month (about 100 ignition pulses). Fueling needs will be supplied by thermal heating of the uranium bed and subsequent gas puffing of the tritium into the tokamak vacuum vessel. A modular vacuum pumping system is considered (6 × 880 ℓ/sec). Tritiated liquid effluents are eliminated by using oilless—bearing pumps. A thin carbon film is applied by glow discharge over the first wall to contain the tritium in the plasma chamber (by saturating the C film). The overall cost of the tritium system is estimated to be less than $3 million.