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Home / Publications / Journals / Fusion Science and Technology / Volume 54 / Number 2

Recovery of Tritium Dissolved in Sodium at the Steam Generator of Fast Breeder Reactor

Yasuhisa Oya, Takuji Oda, Satoru Tanaka, Kenji Okuno

Fusion Science and Technology / Volume 54 / Number 2 / August 2008 / Pages 337-340

Technical Paper / Tritium in Fission

The tritium recovery technique in steam generators for fast breeder reactors using the double pipe concept was proposed. The experimental system for developing an effective tritium recovery technique was developed and tritium recovery experiments using Ar gas or Ar gas with 10-10000 ppm oxygen gas were performed using D2 gas instead of tritium gas. It was found that deuterium permeation through two membranes decreased by installing the double pipe concept with Ar gas. By introducing Ar gas with 10000 ppm oxygen gas, the concentration of deuterium permeation through two membranes decreased by more than 1/200, compared with the one pipe concept, indicating that most of the deuterium was scavenged by Ar gas or reacted with oxygen to form a hydroxide. However, most of the hydroxide was trapped at the surface of the membranes because of the short duration of the experiment.

 
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