New Approach to Tritium Leak Rate Determination
Conference
·
· IEEE Transactions on Nuclear Science
- Mound Laboratory, Miamisburg, OH (United States)
A method for determining leak rates (on the order of 1 x 10-17 cm3/sec and higher) from containers of tritium waste is described. Each container is sealed in a disposable can. After several days, the accumulated tritium is flushed from the can with compressed air through an ethylene-glycol bubbler where the HTO, but not the HT, is trapped. The output of the bubbler is channeled through a heated palladium catalyst where the HT is oxidized. The oxidized HT is collected in a second ethylene-glycol bubbler. The tritium collected in both bubblers is measured by liquid scintillation counting.
- Research Organization:
- Mound Laboratory, Miamisburg, OH (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(33-1)-GEN-53
- NSA Number:
- NSA-29-008417
- OSTI ID:
- 4409765
- Report Number(s):
- MLM--2087(OP); CONF-731112--8
- Conference Information:
- Journal Name: IEEE Transactions on Nuclear Science Journal Issue: 1 Journal Volume: 21
- Country of Publication:
- United States
- Language:
- English
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