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British researchers test concrete method for Sr-90 treatment
Researchers from the University of Manchester, the U.K. National Nuclear Laboratory, and Clemson University have studied using crushed concrete at legacy nuclear facilities as a long-term sink for strontium-90, a radioactive contaminant found at many such sites. Their research has been published in the American Chemical Society journal ACS ES&T Water.
R. G. Clemmer, R. F. Malecha, I. T. Dudley
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 83-92
Tritium | doi.org/10.13182/FST83-A22849
Articles are hosted by Taylor and Francis Online.
The TRIO-01 experiment is a comprehensive test of in-situ tritium recovery from a miniaturized solid breeder blanket assembly. Other solid breeder blanket performance factors such as thermal hydraulics, tritium permeation, and gas phase chemistry will be tested as well. The capsule assembly is irradiated in the A2 core position of the Oak Ridge Research Reactor (ORR). Tritium release and recovery is tested by passing a He sweep gas through the solid breeder capsule measuring and collecting the tritium in the sweep stream. The TRIO-01 experiment has extensive on-line monitoring including sweep gas analysis, temperatures, neutron flux, and tritium permeation.