@article{oai:toyama.repo.nii.ac.jp:00006351,
 author = {松山, 政夫 and 三宅, 均 and 市村, 憲司 and 芦田, 完 and 渡辺, 国昭},
 journal = {富山大学トリチウム科学センター研究報告 = Annual Report of Tritium Research Center, Toyama University},
 month = {},
 note = {application/pdf, Supply and recovery techniques of tritium gas (T2) on a laboratory scale is important for experimental studies using a large amount of tritium gas. From this view point, we examined the potential of the Zr-V-Fe alloy as material for the supply and recovery of tritium gas.  The amount of tritium gas used was 5 Ci in each run, and that of the alloy used was 47mg. It was revealed that the alloy was excellent for purifying tritium gas containing such impurities as 3He, tritiated water and methane: the gas released by heating from the alloy consisted of T2 (85%), HT (15%) and trace amounts of water and hydrocarbons.  The pressure (P) of tritium gas released from the alloy obeyed the following equation, Log P=2.7+log q2-6300/T, where q and T denote the amount of absorption and temperature, respectively. This equation agree with that obtained by using ultra-high vacuum systems. It indicates that the alloy is applicable to recover tritium gas from even conventional vacuum systems that not so good.  An absorption-desorption cycle of over 40 times confirmed the durability of the alloy against residual gases mainly consisting of water and carbon monoxide. These results indicate that the Zr-V-Fe alloy is excellent for the purification, recovery, storage, and supply of tritium gas in conventional vacuum systems., Article},
 pages = {39--46},
 title = {Zr-V-Fe合金による実験室規模でのトリチウムガスの供給と回収},
 volume = {6},
 year = {1986}
}