High flux irradiations of Li coatings on polycrystalline W and ATJ graphite with D, He, and He-seeded D plasmas at Magnum PSI

A. L. Neff, J. P. Allain, F. Bedoya, T. W. Morgan, G. De Temmerman

Research output: Research - peer-reviewArticle

Abstract

Abstract Lithium wall conditioning on PFCs (Plasma Facing Components) on a variety of substrate platforms (e.g. graphite, Mo, etc.) has resulted in improved plasma performance on multiple magnetic fusion devices. On graphite, this improvement occurs through the control of retention and recycling of hydrogen at the plasma-material interface by the chemical bonding of Li, O, and D at the surface. Moderate fluence (1 × 1021 m-2) studies of Li on W, performed in PRIHSM (Particle Radiation in Soft and Hard Matter), demonstrated that H retention is similar to Li on ATJ graphite but He ions, when mixed in a D beam, can inhibit the retention. To expand these studies closer to reactor relevant regimes like inside ITER, irradiations were carried out in Magnum-PSI at DIFFER up to fluences of ∼1025 m-2 with D, He, and He-seeded D plasmas (He 5-10%). Results show that D is still retained at higher fluxes and fluences.

LanguageEnglish (US)
Article number48696
Pages1147-1151
Number of pages5
JournalJournal of Nuclear Materials
Volume463
DOIs
StatePublished - Jul 22 2015

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Graphite
Irradiation
Fluxes
Plasmas
Coatings
graphite
coatings
irradiation
fluence
Lithium
Recycling
Hydrogen
Fusion reactions
Ions
Substrates
conditioning
recycling
platforms
lithium
fusion

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

High flux irradiations of Li coatings on polycrystalline W and ATJ graphite with D, He, and He-seeded D plasmas at Magnum PSI. / Neff, A. L.; Allain, J. P.; Bedoya, F.; Morgan, T. W.; De Temmerman, G.

In: Journal of Nuclear Materials, Vol. 463, 48696, 22.07.2015, p. 1147-1151.

Research output: Research - peer-reviewArticle

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AU - De Temmerman,G.

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AB - Abstract Lithium wall conditioning on PFCs (Plasma Facing Components) on a variety of substrate platforms (e.g. graphite, Mo, etc.) has resulted in improved plasma performance on multiple magnetic fusion devices. On graphite, this improvement occurs through the control of retention and recycling of hydrogen at the plasma-material interface by the chemical bonding of Li, O, and D at the surface. Moderate fluence (1 × 1021 m-2) studies of Li on W, performed in PRIHSM (Particle Radiation in Soft and Hard Matter), demonstrated that H retention is similar to Li on ATJ graphite but He ions, when mixed in a D beam, can inhibit the retention. To expand these studies closer to reactor relevant regimes like inside ITER, irradiations were carried out in Magnum-PSI at DIFFER up to fluences of ∼1025 m-2 with D, He, and He-seeded D plasmas (He 5-10%). Results show that D is still retained at higher fluxes and fluences.

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