Plasma exposure behavior of re-deposited tungsten on structural materials of fusion reactors
Source abstract
Abstract
Abstract To evaluate the effects of re-deposited tungsten (W) on the surface modification and hydrogen isotope retention behavior of fusion structural materials, the plasma exposure behavior of re-deposited W samples prepared by magnetron sputtering on the F82H steel, the V-5Cr-5Ti alloy as well as bare substrate samples was investigated. All the samples were exposed to 367 shots of deuterium plasmas in the 2015 spring EAST campaign. After the plasma exposure, large area of W layer was exfoliated, while big blisters were found at the interface between the remaining W layer and the substrate materials. The deuterium retention behavior of the samples with re-deposited W layer was characterized by thermal desorption spectroscopy and compared with the bare substrate samples.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Metal and Thin Film Mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (19)
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1. Incident energy dependence of blistering at tungsten irradiated by low energy high flux deuterium plasma beams10.1016/j.jnucmat.2005.07.014 ↗
2. Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices10.1088/0029-5515/45/3/007 ↗
3. PSI issues at plasma facing surfaces of blankets in fusion reactors10.1016/S0022-3115(02)01329-6 ↗
4. Hydrogen incorporation in tungsten deposits growing by deuterium plasma sputtering10.1016/j.fusengdes.2011.04.032 ↗
5. Incorporation of hydrogen in carbon-tungsten co-deposition layers formed by hydrogen plasma sputtering10.13182/FST07-A1561 ↗
6. Hydrogen retention in a tungsten re-deposition layer formed by hydrogen RF plasma10.13182/FST05-A992 ↗
7. Overview of plasma-material interaction experiments on EAST employing MAPES10.1016/j.jnucmat.2014.09.017 ↗
8. Deuterium retention in molten salt electrodeposition tungsten coatings10.1016/j.fusengdes.2016.07.023 ↗
9. Hydrogen gas driven permeation through tungsten deposition layer formed by hydrogen plasma sputtering10.1016/j.fusengdes.2015.01.027 ↗
10. High-z dust generation on tungsten surfaces due to synergetic erosion of deuterium/helium plasma exposures10.1585/jspf.81.703 ↗
11. Dust in magnetic fusion devices10.1088/0741-3335/53/8/083001 ↗
12. Dust Part.particles in controlled fusion devices morphology, observations in the plasma and influence on the plasma Perform.performance10.1088/0029-5515/41/8/312 ↗
13. Surface condition effects on tritium permeation through the first wall of a water-cooled ceramic breeder blanket10.1016/j.fusengdes.2016.02.041 ↗
14. The trapping behavior of deuterium in F82H ferritic/martensitic steel10.1016/j.jnucmat.2008.12.124 ↗
15. Deuterium retention in F82H after low energy hydrogen ion irradiation10.1016/j.jnucmat.2010.12.206 ↗
16. Retention of implanted hydrogen and helium in martensitic stainless steels and their effects on mechanical properties10.1016/S0022-3115(01)00545-1 ↗
17. Deuterium retention of V-4Cr-4Ti alloy exposed to the JFT-2M tokamak environment10.1016/S0022-3115(00)00607-3 ↗
18. Deuterium retention and desorption behavior in oxidized ferritic steel10.1016/j.jnucmat.2007.01.136 ↗
19. Deuterium gas-driven permeation and subsequent retention in rolled tungsten foils10.1016/j.jnucmat.2014.06.005 ↗