Deuterium retention in tungsten used in ASDEX Upgrade: comparison of tokamak and laboratory studies

Sugiyama, K.; Mayer, M.; Herrmann, A.; Krieger, K.; Rohde, V.; Balden, M.; Lindig, S.; Neu, R.; Müller, H. W.

doi:10.1088/0031-8949/2014/t159/014043

Cited by 13 publications

(5 citation statements)

References 33 publications

(41 reference statements)

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“…We can compare the D retention in RAFM steels with that in W which is another plasma-facing material widely investigated in the laboratory conditions [17,18,33], used in the present tokamaks [34,35] and proposed to be used in ITER [36]. The comparison of the D retention in polycrystalline W ITER grade and ODS steels is shown in figure 12.…”

Section: Deuterium Retentionmentioning

confidence: 99%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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Section: Deuterium Retentionmentioning

confidence: 99%

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

et al. 2016

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“…Deuterium retention studies with coatings simulating such layers are usually carried out with linear plasma devices. In the case of bulk tungsten used in the plasmafacing components of the reactor divertor, it has been shown that deuterium retention depends on the W grade [3,18,19]. The retention increases considerably for nanocrystalline compact and porous W coatings [6,9].…”

Section: Introductionmentioning

confidence: 99%

LIBS study of ITER relevant tungsten–oxygen coatings exposed to deuterium plasma in Magnum-PSI

Jõgi

Paris

Laan

et al. 2021

Journal of Nuclear Materials

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“…With the coherently averaged transients for particle and heat flux footprints of the discharges, the derived recycling coefficient during the ELM R ELM can be of the order unity [31]. The trap-concentration in W or W-coated CFC materials can be as high as 10% within the first couple of µm [32]. With this high level of trap-concentration in the W-solute the calculated ratio ξ = effusing/implanted flux may vary between 0.4-2.0.…”

Section: Fast Outgassing From Bulk-w/w-coated Cfcmentioning

confidence: 99%

Impact of the JET ITER-like wall on H-mode plasma fueling

et al. 2017

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JET ITER-like wall (ILW) experiments show that the edge density evolution is strongly linked with the poloidal distribution of the ionization source. The fueling profile in the JET-ILW is more delocalized as compared to JET-C (JET with carbon-based plasma-facing components PFCs). Compared to JET-C the H-mode pedestal fueling cycle is dynamically influenced by a combination of plasma-wall interaction features, in particular: (1) edgelocalized modes (ELMs) induced energetic particles are kinetically reflected on W divertor PFCs leading to distributed refueling away from the divertor depending on the divertor plasma configuration, (2) delayed molecular re-emission and outgassing of particles being trapped in W PFCs (bulk-W at the high field side and W-coated CFCs at the low field side) with different fuel content and (3) outgassing from Be co-deposits located on top of the highfield side baffle region shortly after the ELM. In view of the results of a set of well diagnosed series of JET-ILW type-I ELMy H-mode discharges with good statistics, the aforementioned effects are discussed in view of H-mode pedestal fueling capacity. The ongoing modelling activities with the focus on coupled core-edge plasma simulations and plasma-wall interaction are described and discussed also in view of possible code improvements required.

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Deuterium retention in tungsten used in ASDEX Upgrade: comparison of tokamak and laboratory studies

Cited by 13 publications

References 33 publications

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

Surface modification and deuterium retention in reduced-activation steels under low-energy deuterium plasma exposure. Part I: undamaged steels

LIBS study of ITER relevant tungsten–oxygen coatings exposed to deuterium plasma in Magnum-PSI

Impact of the JET ITER-like wall on H-mode plasma fueling

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