Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 48 / Number 1 / Pages 401-404
Y. Asakura et al.
Fusion Science and Technology / Volume 48 / Number 1 / Pages 401-404
Format:electronic copy (download)
In order to realize the deuterium plasma experiments by using the Large Helical Device (LHD), NIFS is planning to install the system for tritium recovery from exhaust gas and effluent liquid. With the case of adopting generally used tritium recovery systems, NIFS has also made the development plans for the compact and less waste generating recovery system by applying the latest technologies such as tritium gas extraction with a proton conducting ceramic and tritiated water vapor removal with a membrane type dehumidifier. Applicability of these new technologies on the tritium recovery system for the LHD deuterium plasma experiment are evaluated quantitatively using the latest experimental data.Mock-up tests of the membrane type dehumidifier are carried out and verified the way of automated operation and stable dehumidifier performance during a long time operation.
Customers who purchased this article also purchased the following:
Your cart is empty.
Home|Invoice Payment|Nuclear Links