Deuterium reclamation from C-Si codeposits using thermo-oxidation

SiC exhibits a remarkable resistance to neutron irradiation damage and, being a low-Z material, is seen as a potential material candidate for plasma-facing components in magnetic confinement fusion reactors. The current work investigates the reclamation of deuterium from C-Si codeposits produced by...

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Main Authors: Adam W. Cruse, James W. Davis
Format: Article
Language:English
Published: Elsevier 2024-03-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179124000516
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author Adam W. Cruse
James W. Davis
author_facet Adam W. Cruse
James W. Davis
author_sort Adam W. Cruse
collection DOAJ
description SiC exhibits a remarkable resistance to neutron irradiation damage and, being a low-Z material, is seen as a potential material candidate for plasma-facing components in magnetic confinement fusion reactors. The current work investigates the reclamation of deuterium from C-Si codeposits produced by sputter-deposition at temperatures from 300 K to 700 K using thermo-oxidation at 350 °C and 400 °C (623 or 673 K). While initial D content was found to be close to that of similarly-produced pure carbon codeposits, hydrogen removal from the investigated C-Si codeposits was significantly reduced comparatively. This reduced removal behaviour was found to follow closely with that observed for B-C codeposits from the DIII-D tokamak. This suggests that hydrogen removal via thermo-oxidation, where a non-carbon inclusion is known to form a stable oxide, is unlikely to be effective.
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spelling doaj.art-bf53c920bc0f423e9b1c56d09c4cc4e22024-03-14T06:15:01ZengElsevierNuclear Materials and Energy2352-17912024-03-0138101629Deuterium reclamation from C-Si codeposits using thermo-oxidationAdam W. Cruse0James W. Davis1University of Toronto Institute for Aerospace Studies, 4925 Dufferin St., Toronto, ON M3H5T6, CanadaCorresponding author.; University of Toronto Institute for Aerospace Studies, 4925 Dufferin St., Toronto, ON M3H5T6, CanadaSiC exhibits a remarkable resistance to neutron irradiation damage and, being a low-Z material, is seen as a potential material candidate for plasma-facing components in magnetic confinement fusion reactors. The current work investigates the reclamation of deuterium from C-Si codeposits produced by sputter-deposition at temperatures from 300 K to 700 K using thermo-oxidation at 350 °C and 400 °C (623 or 673 K). While initial D content was found to be close to that of similarly-produced pure carbon codeposits, hydrogen removal from the investigated C-Si codeposits was significantly reduced comparatively. This reduced removal behaviour was found to follow closely with that observed for B-C codeposits from the DIII-D tokamak. This suggests that hydrogen removal via thermo-oxidation, where a non-carbon inclusion is known to form a stable oxide, is unlikely to be effective.http://www.sciencedirect.com/science/article/pii/S2352179124000516Silicon CarbideCodepositionLaser thermal desorption spectroscopyThermo-oxidationDeuterium removal
spellingShingle Adam W. Cruse
James W. Davis
Deuterium reclamation from C-Si codeposits using thermo-oxidation
Nuclear Materials and Energy
Silicon Carbide
Codeposition
Laser thermal desorption spectroscopy
Thermo-oxidation
Deuterium removal
title Deuterium reclamation from C-Si codeposits using thermo-oxidation
title_full Deuterium reclamation from C-Si codeposits using thermo-oxidation
title_fullStr Deuterium reclamation from C-Si codeposits using thermo-oxidation
title_full_unstemmed Deuterium reclamation from C-Si codeposits using thermo-oxidation
title_short Deuterium reclamation from C-Si codeposits using thermo-oxidation
title_sort deuterium reclamation from c si codeposits using thermo oxidation
topic Silicon Carbide
Codeposition
Laser thermal desorption spectroscopy
Thermo-oxidation
Deuterium removal
url http://www.sciencedirect.com/science/article/pii/S2352179124000516
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