Tritium monitoring in the GCFR sweep gas fuel irradiation capsule BG-10

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:5591880

Gat, U; Pruitt, M E; Longest, A W; Epstein, B D

The release of tritium and its transport pathways were studied in a vented, pressure-equalized fuel rod which simulated a fuel rod in a Gas-Cooled Fast Reactor (GCFR). The purpose was to determine the fraction of total tritium production transported via the various pathways and to determine its chemical form (tritiated hydrogen or water). It was concluded that the fuel rod and its effluent venting lines retained low concentrations of HT (or T/sub 2/) and any HTO (or T/sub 2/O) present. However, the addition of 1% hydrogen to the helium carrier gas quantitatively eluted the tritium from the charcoal trap integral to the fuel rod and from the effluent lines. The chemical composition of the tritium arriving at the monitoring system could be determined by means of converters which convert HT to HTO and vice versa. Ht was the dominant species in the samples measured.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5591880
• Report Number(s): CONF-800427-4
• Country of Publication: United States
• Language: English

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