@article{oai:toyama.repo.nii.ac.jp:00006446, author = {松山, 政夫 and 芦田, 完 and 波多野, 雄治 and 舒, 衛民 and 渡辺, 国昭 and 原, 正憲}, journal = {富山大学水素同位体機能研究センター研究報告}, month = {}, note = {application/pdf, A tritium experimental system for 100Ci/run was established at the Hydrogen Isotope Research Center, Toyama University. This system consisted of two distinct experimental chambers for tritium experiments and backup components such as tritium storage-supply, gas purification, isotope separation and exhaust-gas detritiation. To confirm the reliability of the detritiation device, which is an important factor of the system, the basic performance of the detritiation device was assessed using a small amount of tritium. Two different methods were examined: one is based on conventional oxidation-adsorption (wet method) and the other gettering (dry method). The wet method is advantageous if exhaust gases include large amounts of impurities such as oxygen, water, hydrocarbon and so on. The dry method is applicable for processing exhaust gases which mainly include elemental tritium with a small amount of impurities. The wet method showed excellent performance for tritium removal from exhaust gases with impurity oxygen, the initial tritium concentration was reduced below 1/10 within 20 min. Similar performance was also obtained by dry method. In addition, the absorption bed loaded with molecular sieves could be regenerated by applying the dry method. Accordingly, it was concluded that the performance of the detritiation device satisfies requirement for performing tritium experiments., Article, 富山大学水素同位体機能研究センター研究報告 18, 33-41.(1998)}, pages = {33--41}, title = {100Ciトリチウム実験装置の性能試験(1) -排ガス処理装置-}, volume = {18}, year = {1998} }