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Monitoring and Recovery of Tritium in a Fusion Test Facility

Masahiro Tanaka, Naoyuki Suzuki, Hiromi Kato, Chie Iwata, Naofumi Akata, Hiroshi Hayashi, Hitoshi Miyake

Fusion Science and Technology / Volume 76 / Number 4 / May 2020 / Pages 475-480

Technical Paper / dx.doi.org/10.1080/15361055.2020.1718840

Received:May 29, 2019
Accepted:January 15, 2020
Published:July 15, 2020

In a large fusion test facility, when a deuterium-plasma experiment is conducted a small amount of tritium is produced by the d(d, p)t reaction. From the viewpoints of radiation management and public acceptance, the tritium monitoring and recovery systems were developed and installed for the fusion test device. As for the tritium monitoring equipment, an expiratory test system of tritium was utilized for the internal dose assessment of workers. Active tritium samplers were operated continuously to monitor the amount of tritium released from the stack. As for the tritium recovery equipment, an exhaust detritiation system (EDS) for the plasma experiment has been developed and installed at the downstream of the vacuum pumping system in the fusion test device. All of the exhausted tritium from the vacuum vessel was treated by the EDS during the deuterium-plasma experimental campaign. Then, the tritium recovery rate achieved was more than 95%.