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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.
K. R. O'Kula, W. H. Horton
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 1130-1135
Tritium Safety | doi.org/10.13182/FST88-A25290
Articles are hosted by Taylor and Francis Online.
The Probabilistic Risk Assessment (PRA) of Savannah River Plant (SRP) reactor operation is evaluating the offsite risk due to tritium releases during postulated full or partial loss of heavy water moderator accidents. Preliminary determination of the frequency of average partial moderator loss (including incidents with leaks as small as 0.5 kg) yields an estimate of ∼1 per reactor-year. The full moderator loss frequency is conservatively chosen as 5×10−3 per reactor-year. Conditional consequences, determined with a version of the MACCS code modified to handle tritium, are found to be insignificant. The 95th percentile individual cancer risk is 2×10−8 per reactor-year within 16 km of the release point. The full moderator loss accident contributes about 80% of the evaluated risks. “Nuclear Power Safety Goals in Light of the Chernobyl Accident,” Nucl. Safety, 29(1), 20 (1988).