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Study on a Method to Recover Tritium from Blanket Sweep Gas

Masabumi Nishikawa, Ken-Ichi Tanaka, Mitsuru Uetake

Fusion Science and Technology / Volume 26 / Number 1 / August 1994 / Pages 17-26

Technical Paper / Tritium System / dx.doi.org/10.13182/FST94-A30298

The tritium bred in a deuterium-tritium fusion reactor is to be extracted from the tritium breeding blanket by sweep gas. To be used as fuel for the reactor, the tritium must be recovered in a form that is easy to transfer to the main fuel cycle. The feasibility of a cryosorption method that uses a porous adsorbent, such as molecular sieves or activated carbon, at liquid nitrogen temperature (77.4 K) is discussed.