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Gamma radiation effects on tritium permeation through stainless steel

Conference · · Nucl. Technol./Fusion; (United States)
OSTI ID:6025664
Experiments were conducted in the gamma irradiation facility of the Advanced Test Reactor at the Idaho National Engineering Laboratory to determine whether gamma radiation has an appreciable effect on the normal permeation of tritium through stainless steel. Low concentrations of HT were allowed to diffuse through a 0.071-cm-thick tube of 316 stainless steel, heated between 590 and 733 K. Gamma irradiation intensities were varied from 1.3 to 155 C/kgXh (5 X 10/sup 3/ to 6 X 10/sup 5/ R/h). Ion chamber detectors were used to measure tritium concentrations on both sides of the tube. It was found that in the presence of excess H/sub 2/, the higher gamma irradiation intensity exhibited slightly higher permeation rates of tritium. When the walls of the permeation tube and the HT were highly oxidized, the permeation rates were much more scattered, and the gamma irradiation seemed to have no observable effect. It was concluded that the effect of gamma radiation on tritium permeation through stainless steel in a fusion reactor environment should be small. However, the relative ease with which tritium from HTO was seen to permeate the material raises questions regarding tritium management in breeder blankets.
Research Organization:
EG and G Idaho, Inc./Fusion Technology, P.O. Box 1625, Idaho Falls, ID 83415
OSTI ID:
6025664
Report Number(s):
CONF-830406-
Conference Information:
Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
Country of Publication:
United States
Language:
English

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