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Trapping and depth profile of tritium in surface layers of metallic materials
- Source :
- Journal of Nuclear Materials. 417:900-903
- Publication Year :
- 2011
- Publisher :
- Elsevier BV, 2011.
-
Abstract
- Tritium amount retained in surface layers and release behavior from surface layers were examined using SS316L samples exposed to plasmas in the Large Helical Device and a commercial Cu–Be alloy plate. BIXS analyses and observation by SEM indicate that carbon and titanium deposited on the plasma-facing surface of the SS316L samples. Larger amount of tritium was trapped in the plasma-facing surface in comparison with the polished surface. Higher enrichment of tritium in surface layers was similarly found in the polished surface of both samples. The amount of surface tritium in both samples was almost same, while the bulk concentration of tritium in Cu–Be was much lower than that in SS316L. Tritium release from the SS316L and Cu–Be samples into water was examined by immersion experiments. Tritium elution was observed for both samples, but changes in the residual tritium amount in surface layers were different from each other.
- Subjects :
- inorganic chemicals
Nuclear and High Energy Physics
Materials science
Elution
organic chemicals
Alloy
Analytical chemistry
chemistry.chemical_element
Plasma
Trapping
engineering.material
Large Helical Device
Nuclear Energy and Engineering
chemistry
cardiovascular system
polycyclic compounds
engineering
General Materials Science
Tritium
Carbon
Titanium
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 417
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........8e3ab74f7b59bcbaa6166ae183db2094
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2011.04.005