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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.
Shigeo Numata, Yasuhiko Fujii, Makoto Okamoto
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 466-472
Technical Paper | Safety Environmental Aspect | doi.org/10.13182/FST91-A29387
Articles are hosted by Taylor and Francis Online.
Cleanup of tritiated water in typical reactor-size concrete enclosures is simulated taking into account the soaking of the tritiated water into the concrete. For an enclosure made of concrete with ordinary porosity, the “soaking effect” has little effect on the cleanup time for releases with tritium concentrations of <1 × 108 Bq/m3. If the concrete porosity is reduced to 0.03, the soaking effect has little effect on the cleanup time for a tritium concentration of up to 1 × 109 Bq/m3. An optimum flow rate of between 1 × 104 and 1.5 × 104 m3/h for the tritium removal system minimizes the costs of removal system equipment and facility downtime for releases with a concentration >5 × 108 Bq/m3 in a typical reactor-size enclosure. Estimated total costs to complete the cleanup within 48 and 72 h with these flow rates are within 1.3 times of the minimum total costs. The estimated total costs for a cleanup time of 48 h are comparable to those for a cleanup time of 72 h.