Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-like Wall Project at JET

T. Hirai (Corresponding Author), J. Linke, M. Rubel, J. P. Coad, Jari Likonen, C. P. Lungu, G. F. Matthews, V. Phillips, E. Wessel, JET-EFDA Contributors

Research output: Contribution to journalArticleScientificpeer-review

11 Citations (Scopus)

Abstract

ITER-Like Wall Project has been launched at JET in order to perform a fully integrated test of plasma-facing materials. During the next major shutdown a full metal wall will be installed: tungsten in the divertor and beryllium in the main chamber. Beryllium erosion is one of key issues to be addressed. Special marker tiles have been designed for this purpose. Test coupons of such markers have been manufactured and examined. The performance test under high power deposition was carried in the electron beam facility JUDITH. The results of material characterization before and after high heat flux loads are presented. The samples survived, without macroscopic damage, power loads of up to 4.5 MW/m2 for 10 s (surface temperature ∼650 °C) and 50 cyclic loads at 3.5 MW/m2 lasting 10 s each (surface temperature ∼600 °C).
Original languageEnglish
Pages (from-to)1072 - 1076
Number of pages5
JournalFusion Engineering and Design
Volume83
Issue number7-9
DOIs
Publication statusPublished - 2008
MoE publication typeA1 Journal article-refereed

Fingerprint

Load testing
Beryllium
Thermal load
Tile
Erosion
Facings
Cyclic loads
Monitoring
Tungsten
Heat flux
Electron beams
Plasmas
Temperature
Metals

Keywords

  • Beryllium
  • Coating
  • High heat flux
  • ITER
  • JET

Cite this

Hirai, T. ; Linke, J. ; Rubel, M. ; Coad, J. P. ; Likonen, Jari ; Lungu, C. P. ; Matthews, G. F. ; Phillips, V. ; Wessel, E. ; JET-EFDA Contributors. / Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-like Wall Project at JET. In: Fusion Engineering and Design. 2008 ; Vol. 83, No. 7-9. pp. 1072 - 1076.
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abstract = "ITER-Like Wall Project has been launched at JET in order to perform a fully integrated test of plasma-facing materials. During the next major shutdown a full metal wall will be installed: tungsten in the divertor and beryllium in the main chamber. Beryllium erosion is one of key issues to be addressed. Special marker tiles have been designed for this purpose. Test coupons of such markers have been manufactured and examined. The performance test under high power deposition was carried in the electron beam facility JUDITH. The results of material characterization before and after high heat flux loads are presented. The samples survived, without macroscopic damage, power loads of up to 4.5 MW/m2 for 10 s (surface temperature ∼650 °C) and 50 cyclic loads at 3.5 MW/m2 lasting 10 s each (surface temperature ∼600 °C).",
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author = "T. Hirai and J. Linke and M. Rubel and Coad, {J. P.} and Jari Likonen and Lungu, {C. P.} and Matthews, {G. F.} and V. Phillips and E. Wessel and {JET-EFDA Contributors}",
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Hirai, T, Linke, J, Rubel, M, Coad, JP, Likonen, J, Lungu, CP, Matthews, GF, Phillips, V, Wessel, E & JET-EFDA Contributors 2008, 'Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-like Wall Project at JET', Fusion Engineering and Design, vol. 83, no. 7-9, pp. 1072 - 1076. https://doi.org/10.1016/j.fusengdes.2008.05.007

Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-like Wall Project at JET. / Hirai, T. (Corresponding Author); Linke, J.; Rubel, M.; Coad, J. P.; Likonen, Jari; Lungu, C. P.; Matthews, G. F.; Phillips, V.; Wessel, E.; JET-EFDA Contributors.

In: Fusion Engineering and Design, Vol. 83, No. 7-9, 2008, p. 1072 - 1076.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Thermal load testing of erosion-monitoring beryllium marker tile for the ITER-like Wall Project at JET

AU - Hirai, T.

AU - Linke, J.

AU - Rubel, M.

AU - Coad, J. P.

AU - Likonen, Jari

AU - Lungu, C. P.

AU - Matthews, G. F.

AU - Phillips, V.

AU - Wessel, E.

AU - JET-EFDA Contributors,

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AB - ITER-Like Wall Project has been launched at JET in order to perform a fully integrated test of plasma-facing materials. During the next major shutdown a full metal wall will be installed: tungsten in the divertor and beryllium in the main chamber. Beryllium erosion is one of key issues to be addressed. Special marker tiles have been designed for this purpose. Test coupons of such markers have been manufactured and examined. The performance test under high power deposition was carried in the electron beam facility JUDITH. The results of material characterization before and after high heat flux loads are presented. The samples survived, without macroscopic damage, power loads of up to 4.5 MW/m2 for 10 s (surface temperature ∼650 °C) and 50 cyclic loads at 3.5 MW/m2 lasting 10 s each (surface temperature ∼600 °C).

KW - Beryllium

KW - Coating

KW - High heat flux

KW - ITER

KW - JET

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DO - 10.1016/j.fusengdes.2008.05.007

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