Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients

G. Federici; A. R. Raffray; H. D. Pacher; I. Smid; S. Chiocchio; B. Esser; J. Dietz; Y. Igitkhanov; G. Janeschitz

Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients

G. Federici, A. R. Raffray, H. D. Pacher, I. Smid, S. Chiocchio, B. Esser, J. Dietz, Y. Igitkhanov, G. Janeschitz

Engineering Science and Mechanics

Research output: Contribution to conference › Paper › peer-review

1 Scopus citations

Abstract

This paper presents the results of an analysis carried out to investigate the thermal response of ITER divertor plasma facing components (PFC's) clad with Be, W, and CFC, to high-recycling, high-power thermal transients (i.e. 10-30 MW/m²) which are anticipated to last up to a few seconds. The armour erosion and surface melting are estimated for the different plasma facing materials (PFM's) together with the maximum heat flux to the coolant, and armour/ heat-sink interface temperature. The analysis assumes that intense target evaporation will lead to high radiative power losses in the plasma in front of the target which 'self-protects' the target. The cases analysed clarify the influence of several key parameters such as the plasma heat flux to the target, the loss of the melt layer, the duration of the event, the thickness of the armour, and comparison is made with cases without vapour shielding. Finally, some implications for the performance and lifetime of divertor PFC's clad with different PFM's are discussed.

Original language	English (US)
Pages	430-434
Number of pages	5
State	Published - 1995
Event	Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) - Champaign, IL, USA Duration: Oct 1 1995 → Oct 5 1995

Other

Other	Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)
City	Champaign, IL, USA
Period	10/1/95 → 10/5/95

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Cite this

Federici, G., Raffray, A. R., Pacher, H. D., Smid, I., Chiocchio, S., Esser, B., Dietz, J., Igitkhanov, Y., & Janeschitz, G. (1995). Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients. 430-434. Paper presented at Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2), Champaign, IL, USA.

@conference{a817ac4ef3214e36b2e713bfabfa0f16,

title = "Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients",

abstract = "This paper presents the results of an analysis carried out to investigate the thermal response of ITER divertor plasma facing components (PFC's) clad with Be, W, and CFC, to high-recycling, high-power thermal transients (i.e. 10-30 MW/m2) which are anticipated to last up to a few seconds. The armour erosion and surface melting are estimated for the different plasma facing materials (PFM's) together with the maximum heat flux to the coolant, and armour/ heat-sink interface temperature. The analysis assumes that intense target evaporation will lead to high radiative power losses in the plasma in front of the target which 'self-protects' the target. The cases analysed clarify the influence of several key parameters such as the plasma heat flux to the target, the loss of the melt layer, the duration of the event, the thickness of the armour, and comparison is made with cases without vapour shielding. Finally, some implications for the performance and lifetime of divertor PFC's clad with different PFM's are discussed.",

author = "G. Federici and Raffray, {A. R.} and Pacher, {H. D.} and I. Smid and S. Chiocchio and B. Esser and J. Dietz and Y. Igitkhanov and G. Janeschitz",

year = "1995",

language = "English (US)",

pages = "430--434",

note = "Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2) ; Conference date: 01-10-1995 Through 05-10-1995",

}

Federici, G, Raffray, AR, Pacher, HD, Smid, I, Chiocchio, S, Esser, B, Dietz, J, Igitkhanov, Y & Janeschitz, G 1995, 'Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients', Paper presented at Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2), Champaign, IL, USA, 10/1/95 - 10/5/95 pp. 430-434.

Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients. / Federici, G.; Raffray, A. R.; Pacher, H. D. et al.
1995. 430-434 Paper presented at Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2), Champaign, IL, USA.

Research output: Contribution to conference › Paper › peer-review

TY - CONF

T1 - Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients

AU - Federici, G.

AU - Raffray, A. R.

AU - Pacher, H. D.

AU - Smid, I.

AU - Chiocchio, S.

AU - Esser, B.

AU - Dietz, J.

AU - Igitkhanov, Y.

AU - Janeschitz, G.

PY - 1995

Y1 - 1995

N2 - This paper presents the results of an analysis carried out to investigate the thermal response of ITER divertor plasma facing components (PFC's) clad with Be, W, and CFC, to high-recycling, high-power thermal transients (i.e. 10-30 MW/m2) which are anticipated to last up to a few seconds. The armour erosion and surface melting are estimated for the different plasma facing materials (PFM's) together with the maximum heat flux to the coolant, and armour/ heat-sink interface temperature. The analysis assumes that intense target evaporation will lead to high radiative power losses in the plasma in front of the target which 'self-protects' the target. The cases analysed clarify the influence of several key parameters such as the plasma heat flux to the target, the loss of the melt layer, the duration of the event, the thickness of the armour, and comparison is made with cases without vapour shielding. Finally, some implications for the performance and lifetime of divertor PFC's clad with different PFM's are discussed.

AB - This paper presents the results of an analysis carried out to investigate the thermal response of ITER divertor plasma facing components (PFC's) clad with Be, W, and CFC, to high-recycling, high-power thermal transients (i.e. 10-30 MW/m2) which are anticipated to last up to a few seconds. The armour erosion and surface melting are estimated for the different plasma facing materials (PFM's) together with the maximum heat flux to the coolant, and armour/ heat-sink interface temperature. The analysis assumes that intense target evaporation will lead to high radiative power losses in the plasma in front of the target which 'self-protects' the target. The cases analysed clarify the influence of several key parameters such as the plasma heat flux to the target, the loss of the melt layer, the duration of the event, the thickness of the armour, and comparison is made with cases without vapour shielding. Finally, some implications for the performance and lifetime of divertor PFC's clad with different PFM's are discussed.

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M3 - Paper

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SP - 430

EP - 434

T2 - Proceedings of the 1995 16th IEEE/NPSS Symposium on Fusion Engineering. Part 1 (of 2)

Y2 - 1 October 1995 through 5 October 1995

ER -

Analysis of heat transfer and erosion effects on ITER divertor plasma facing components induced by slow high-power transients

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