Change search
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0
Forschungszentrum Julich, Inst Energie & Klimaforsch, Plasmaphys, Partner Trilateral Euregio Cluster TEC, D-5242 Julich, Germany.;Forschungszentrum Julich GmbH, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany..
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Fusion Plasma Physics.
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Fusion Plasma Physics.
KTH, School of Electrical Engineering and Computer Science (EECS), Electrical Engineering, Fusion Plasma Physics.
Show others and affiliations
Number of Authors: 12342019 (English)In: Nuclear Materials and Energy, E-ISSN 2352-1791, Vol. 18, p. 331-338Article in journal (Refereed) Published
Abstract [en]

The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium (Be) erosion and deposition is simulated and compared to experimental results from passive spectroscopy. For the limiter configuration, it is demonstrated that Be self-sputtering is an important contributor (at least 35%) to the Be erosion. Taking this contribution into account, the ERO2.0 modelling confirms previous evidence that high deuterium (D) surface concentrations of up to similar to 50% atomic fraction provide a reasonable estimate of Be erosion in plasma-wetted areas. For the divertor configuration, it is shown that drifts can have a high impact on the scrape-off layer plasma flows, which in turn affect global Be transport by entrainment and lead to increased migration into the inner divertor. The modelling of the effective erosion yield for different operational phases (ohmic, L- and H-mode) agrees with experimental values within a factor of two, and confirms that the effective erosion yield decreases with increasing heating power and confinement.

Place, publisher, year, edition, pages
Elsevier, 2019. Vol. 18, p. 331-338
Keywords [en]
Beryllium, Erosion, ER02.0, JET ITER-like wall
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-270863DOI: 10.1016/j.nme.2019.01.015ISI: 000460107500056Scopus ID: 2-s2.0-85061047660OAI: oai:DiVA.org:kth-270863DiVA, id: diva2:1414967
Note

QC 20200316

Available from: 2020-03-16 Created: 2020-03-16 Last updated: 2020-05-11Bibliographically approved

Open Access in DiVA

No full text in DiVA

Other links

Publisher's full textScopus

Search in DiVA

By author/editor
Bergsåker, HenrikBykov, IgorFrassinetti, LorenzoGarcia Carrasco, AlvaroHellsten, TorbjörnJohnson, ThomasRachlew, ElisabethRatynskaia, SvetlanaRubel, MarekStefániková, EsteraStröm, PetterTholerus, EmmiTolias, PanagiotisOlivares, Pablo VallejosWeckmann, Armin
By organisation
Fusion Plasma PhysicsFusion Plasma PhysicsParticle and Astroparticle PhysicsSpace and Plasma Physics
In the same journal
Nuclear Materials and Energy
Physical Sciences

Search outside of DiVA

GoogleGoogle Scholar

doi
urn-nbn

Altmetric score

doi
urn-nbn
Total: 2 hits
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf