Tritium permeation through oxidized 304 and 316 stainless steel
This work was completed during the course of a cooperative program on Tritium Transport in Liquid Metal Cooled Reactors. This work considers conditions encountered in operating reactors. It involves hydrogen, deuterium and tritium permeation measurements on ''clean'' and oxidized surfaces. The tritium measurements were restricted to permeation rates from sodium and through the test membrane at concentrations typical of EBR-II reactor experience. The hydrogen and deuterium work measured permeation rates at gas pressures from 13-1300 Pa (0.1 to 10 Torr). Permeation rates were measured for tritium permeation through oxidized 304 and 316 stainless steel. The tritium was injected into hot flowing sodium at concentrations near present sodium cooled reactor operating levels. Permeation data are presented as a function of temperature, oxidation time and tritium activity level in the sodium. Permeation rates were determined at 590, 540 and 480/sup 0/C and at tritium concentrations varying from 1 to 40 x 10/sup -9/ CiT/sub 2//gmNa (3.4 x 10/sup -8/ to 1 x 10/sup -6/ ppM). At 540/sup 0/C tritium diffusion rates for both ozidized steels were in the range 1-2 x 10/sup -4/ cc-mm/hr-cm/sup 2/-atm/sup 1///sub 2/. Response at this concentration varied as the square root of pressure. However hydrogen (H/sub 2/) and deuterium permeation tests at 1300 to 13 Pa (10 to 0.1 Torr.) showed linear response to changes in this higher pressure range.
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6805886
- Report Number(s):
- HEDL-SA-1326; CONF-780213-10
- Resource Relation:
- Conference: 107. AIME meeting, Denver, CO, USA, 26 Feb 1978
- Country of Publication:
- United States
- Language:
- English
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