Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

A. Widdowson; S. Aleiferis; E. Alves; L. Avotina; A. Baron-Wiechec; N. Catarino; J. P. Coad; V. Corregidor; K. Heinola; I. Jepu; C. Makepeace

doi:10.1088/1402-4896/ab5350

Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

A. Widdowson^*, S. Aleiferis, E. Alves, L. Avotina, A. Baron-Wiechec, N. Catarino, J. P. Coad, V. Corregidor, K. Heinola, I. Jepu, C. Makepeace

^*Corresponding author for this work

Materials Science and Engineering

Research output: Contribution to journal › Conference article › peer-review

20 Scopus citations

Abstract

Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is ∼0.01. Global fuel retention attributed to limiters is <0.01% of injected fuel. Marker coatings reveal a rapid transition from strong erosion to deposition within 15 mm. This work highlights the need to carefully consider the requirements of marker coatings for long exposure studies in high erosion areas.

Original language	English
Article number	014051
Journal	Physica Scripta
Volume	2020
Issue number	T171
DOIs	https://doi.org/10.1088/1402-4896/ab5350
State	Published - 1 Jan 2020
Event	17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands Duration: 20 May 2019 → 24 May 2019

Keywords

Beryllium
Deposition
Erosion
Fuel retention
Jet ITER-like wall
Material migration

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10.1088/1402-4896/ab5350

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Widdowson, A., Aleiferis, S., Alves, E., Avotina, L., Baron-Wiechec, A., Catarino, N., Coad, J. P., Corregidor, V., Heinola, K., Jepu, I., & Makepeace, C. (2020). Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods. Physica Scripta, 2020(T171), Article 014051. https://doi.org/10.1088/1402-4896/ab5350

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title = "Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods",

abstract = "Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is ∼0.01. Global fuel retention attributed to limiters is <0.01% of injected fuel. Marker coatings reveal a rapid transition from strong erosion to deposition within 15 mm. This work highlights the need to carefully consider the requirements of marker coatings for long exposure studies in high erosion areas.",

keywords = "Beryllium, Deposition, Erosion, Fuel retention, Jet ITER-like wall, Material migration",

author = "A. Widdowson and S. Aleiferis and E. Alves and L. Avotina and A. Baron-Wiechec and N. Catarino and Coad, {J. P.} and V. Corregidor and K. Heinola and I. Jepu and C. Makepeace",

note = "Publisher Copyright: {\textcopyright} Culham Centre for Fusion Energy.; 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 ; Conference date: 20-05-2019 Through 24-05-2019",

year = "2020",

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doi = "10.1088/1402-4896/ab5350",

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T1 - Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

AU - Widdowson, A.

AU - Aleiferis, S.

AU - Alves, E.

AU - Avotina, L.

AU - Baron-Wiechec, A.

AU - Catarino, N.

AU - Coad, J. P.

AU - Corregidor, V.

AU - Heinola, K.

AU - Jepu, I.

AU - Makepeace, C.

N1 - Publisher Copyright: © Culham Centre for Fusion Energy.

PY - 2020/1/1

Y1 - 2020/1/1

N2 - Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is ∼0.01. Global fuel retention attributed to limiters is <0.01% of injected fuel. Marker coatings reveal a rapid transition from strong erosion to deposition within 15 mm. This work highlights the need to carefully consider the requirements of marker coatings for long exposure studies in high erosion areas.

AB - Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles are presented for three operating periods. Ion beam analysis results support the general picture of erosion during limiter configurations with local deposition on tile ends far into the scrape off layer. Similar trends of fuel concentrations are observed in all JET operating periods; (i) low on surfaces exposed to high heat flux and erosion and (ii) higher in deposits. The pattern of fuel retention and deposition correlates with heat flux and distribution of limiter plasmas touching inner and outer limiters. The D/Be ratio in the thickest deposit is ∼0.01. Global fuel retention attributed to limiters is <0.01% of injected fuel. Marker coatings reveal a rapid transition from strong erosion to deposition within 15 mm. This work highlights the need to carefully consider the requirements of marker coatings for long exposure studies in high erosion areas.

KW - Beryllium

KW - Deposition

KW - Erosion

KW - Fuel retention

KW - Jet ITER-like wall

KW - Material migration

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U2 - 10.1088/1402-4896/ab5350

DO - 10.1088/1402-4896/ab5350

M3 - 会议文章

AN - SCOPUS:85084639127

SN - 0031-8949

VL - 2020

JO - Physica Scripta

JF - Physica Scripta

IS - T171

M1 - 014051

T2 - 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019

Y2 - 20 May 2019 through 24 May 2019

ER -

Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods

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Keywords

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