1. Monitoring and Recovery of Tritium in a Fusion Test Facility
- Author
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Hiroshi Hayashi, Chie Iwata, Hiromi Kato, Naofumi Akata, Naoyuki Suzuki, Masahiro Tanaka, and Hitoshi Miyake
- Subjects
inorganic chemicals ,Nuclear and High Energy Physics ,Fusion ,Test facility ,Mechanical Engineering ,Nuclear engineering ,organic chemicals ,education ,Exhaust gas ,tritium recovery ,tririum monitoring ,Radiation management ,fusion test facility ,Nuclear Energy and Engineering ,polycyclic compounds ,cardiovascular system ,Environmental science ,General Materials Science ,Tritium ,exhaust gas ,Civil and Structural Engineering - Abstract
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%.
- Published
- 2020
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