Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities

G. M. Wright; A. W. Kleyn; E. Alves; L. C. Alves; N. P. Barradas; G. J. van Rooij; A. J. van Lange; A. E. Shumack; J. Westerhout; R. S. Al; W. A.J. Vijvers; B. de Groot; M. J. van de Pol; H. J. van der Meiden; J. Rapp; N. J. Lopes Cardozo

doi:10.1016/j.jnucmat.2009.01.173

Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities

G. M. Wright, A. W. Kleyn, E. Alves, L. C. Alves, N. P. Barradas, G. J. van Rooij, A. J. van Lange, A. E. Shumack, J. Westerhout, R. S. Al, W. A.J. Vijvers, B. de Groot, M. J. van de Pol, H. J. van der Meiden, J. Rapp, N. J. Lopes Cardozo

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Abstract

Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (∼10²⁴ D/m²s, T_e ∼ 2 eV). The surface temperature of the target is ∼1600 K at the center and decreased radially to ∼1000 K at the edges. A 2-D spatial scan of the W target using nuclear reaction analysis (NRA) shows an asymmetric D retention profile with the lowest retention values at the center of the target and the highest 6 mm off-center. Even in the regions of larger retention, the D concentrations were ≤5 × 10¹⁵ D/cm² as measured by NRA. Thermal desorption spectroscopy (TDS) is used to measure the global D retention. Very low retention with retained fractions ranging from 10^-7 to 10^-5 D_retained/D_incident were measured with TDS. Both NRA and TDS results show no clear dependence of retention on incident fluence possibly indicating the absence of plasma-driven trap production in W under these conditions.

Original language	English
Pages (from-to)	610-613
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	390-391
Issue number	1
DOIs	https://doi.org/10.1016/j.jnucmat.2009.01.173
State	Published - Jun 15 2009
Externally published	Yes

Funding

This work, supported by the European Communities under the contract of the Association EURATOM/FOM, was carried out within the framework of the European Fusion Programme with financial support from NWO. The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Funders	Funder number
Nederlandse Organisatie voor Wetenschappelijk Onderzoek

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.jnucmat.2009.01.173

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Wright, G. M., Kleyn, A. W., Alves, E., Alves, L. C., Barradas, N. P., van Rooij, G. J., van Lange, A. J., Shumack, A. E., Westerhout, J., Al, R. S., Vijvers, W. A. J., de Groot, B., van de Pol, M. J., van der Meiden, H. J., Rapp, J., & Lopes Cardozo, N. J. (2009). Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities. Journal of Nuclear Materials, 390-391(1), 610-613. https://doi.org/10.1016/j.jnucmat.2009.01.173

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title = "Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities",

abstract = "Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (∼1024 D/m2s, Te ∼ 2 eV). The surface temperature of the target is ∼1600 K at the center and decreased radially to ∼1000 K at the edges. A 2-D spatial scan of the W target using nuclear reaction analysis (NRA) shows an asymmetric D retention profile with the lowest retention values at the center of the target and the highest 6 mm off-center. Even in the regions of larger retention, the D concentrations were ≤5 × 1015 D/cm2 as measured by NRA. Thermal desorption spectroscopy (TDS) is used to measure the global D retention. Very low retention with retained fractions ranging from 10-7 to 10-5 Dretained/Dincident were measured with TDS. Both NRA and TDS results show no clear dependence of retention on incident fluence possibly indicating the absence of plasma-driven trap production in W under these conditions.",

author = "Wright, {G. M.} and Kleyn, {A. W.} and E. Alves and Alves, {L. C.} and Barradas, {N. P.} and {van Rooij}, {G. J.} and {van Lange}, {A. J.} and Shumack, {A. E.} and J. Westerhout and Al, {R. S.} and Vijvers, {W. A.J.} and {de Groot}, B. and {van de Pol}, {M. J.} and {van der Meiden}, {H. J.} and J. Rapp and {Lopes Cardozo}, {N. J.}",

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doi = "10.1016/j.jnucmat.2009.01.173",

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Wright, GM, Kleyn, AW, Alves, E, Alves, LC, Barradas, NP, van Rooij, GJ, van Lange, AJ, Shumack, AE, Westerhout, J, Al, RS, Vijvers, WAJ, de Groot, B, van de Pol, MJ, van der Meiden, HJ, Rapp, J & Lopes Cardozo, NJ 2009, 'Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities', Journal of Nuclear Materials, vol. 390-391, no. 1, pp. 610-613. https://doi.org/10.1016/j.jnucmat.2009.01.173

TY - JOUR

T1 - Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities

AU - Wright, G. M.

AU - Kleyn, A. W.

AU - Alves, E.

AU - Alves, L. C.

AU - Barradas, N. P.

AU - van Rooij, G. J.

AU - van Lange, A. J.

AU - Shumack, A. E.

AU - Westerhout, J.

AU - Al, R. S.

AU - Vijvers, W. A.J.

AU - de Groot, B.

AU - van de Pol, M. J.

AU - van der Meiden, H. J.

AU - Rapp, J.

AU - Lopes Cardozo, N. J.

PY - 2009/6/15

Y1 - 2009/6/15

N2 - Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (∼1024 D/m2s, Te ∼ 2 eV). The surface temperature of the target is ∼1600 K at the center and decreased radially to ∼1000 K at the edges. A 2-D spatial scan of the W target using nuclear reaction analysis (NRA) shows an asymmetric D retention profile with the lowest retention values at the center of the target and the highest 6 mm off-center. Even in the regions of larger retention, the D concentrations were ≤5 × 1015 D/cm2 as measured by NRA. Thermal desorption spectroscopy (TDS) is used to measure the global D retention. Very low retention with retained fractions ranging from 10-7 to 10-5 Dretained/Dincident were measured with TDS. Both NRA and TDS results show no clear dependence of retention on incident fluence possibly indicating the absence of plasma-driven trap production in W under these conditions.

AB - Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (∼1024 D/m2s, Te ∼ 2 eV). The surface temperature of the target is ∼1600 K at the center and decreased radially to ∼1000 K at the edges. A 2-D spatial scan of the W target using nuclear reaction analysis (NRA) shows an asymmetric D retention profile with the lowest retention values at the center of the target and the highest 6 mm off-center. Even in the regions of larger retention, the D concentrations were ≤5 × 1015 D/cm2 as measured by NRA. Thermal desorption spectroscopy (TDS) is used to measure the global D retention. Very low retention with retained fractions ranging from 10-7 to 10-5 Dretained/Dincident were measured with TDS. Both NRA and TDS results show no clear dependence of retention on incident fluence possibly indicating the absence of plasma-driven trap production in W under these conditions.

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VL - 390-391

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EP - 613

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1

ER -

Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities

Abstract

Funding

UN SDGs

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