WEN Wei, SUN Yu, QIU Yong-mei, DAN Gui-ping. Analysis of Tritium in Stainless Steel of Decommissioned Nuclear Facilities[J]. Journal of Isotopes, 2012, 25(2): 78-81. DOI: 10.7538/tws.2012.25.02.0078
Citation: WEN Wei, SUN Yu, QIU Yong-mei, DAN Gui-ping. Analysis of Tritium in Stainless Steel of Decommissioned Nuclear Facilities[J]. Journal of Isotopes, 2012, 25(2): 78-81. DOI: 10.7538/tws.2012.25.02.0078

Analysis of Tritium in Stainless Steel of Decommissioned Nuclear Facilities

  • A thermal vacuum analytical system was established for the determination of tritium in stainless steel samples.The releas temperature, time, catalyst efficiency and condensed recovery were described in detailed. The results indicated that the condensed recovery,catalyst efficiency,and released coefficient were 99%,98.6%, and more than 95% respectively,when the stainless steel samples were heated for 2 hours at 700 ℃ under the following conditions:the condenser temperature at -20 ℃ and the flow velocity of the compressed air at 60-80 L/h.This system could meet the need for the determination of tritium in stainless steels samples during decommissioning.
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