Detritiation of JET tiles by laser cleaning

A. Widdowson; J. P. Coad; D. Farcage; D. Hole; Jari Likonen; Tommi Renvall; A. Semerok; P.-Y. Thro; JET-EFDA Contributors

doi:10.13182/FST08-A1763

Detritiation of JET tiles by laser cleaning

A. Widdowson, J. P. Coad, D. Farcage, D. Hole, Jari Likonen, Tommi Renvall, A. Semerok, P.-Y. Thro, JET-EFDA Contributors

Research output: Contribution to journal › Article › Scientific › peer-review

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Abstract

The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern to the fusion community as the scale of tritium retention by this mechanism could be a limiting factor for the operation of fusion reactors, such as ITER. Hence there is a need to investigate ways of mitigating T retention and also for detritiating surfaces by either desorption of T or removal of tritiated deposits. The results of the removal of codeposits from CFC tiles by pulsed laser ablation are reported here. The results show that it is possible to completely remove a 300μm thick hydrogen isotope rich carbon film at a rate of 12x10
^-3m²/hr by this method and that with optimisation of the laser parameters there is scope to improve the treatment rates to provide a useful tool for managing T inventory in tokamaks.

Original language	English
Pages (from-to)	51-54
Number of pages	4
Journal	Fusion Science and Technology
Volume	54
Issue number	1
DOIs	https://doi.org/10.13182/FST08-A1763
Publication status	Published - 2008
MoE publication type	A1 Journal article-refereed

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title = "Detritiation of JET tiles by laser cleaning",

abstract = "The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern to the fusion community as the scale of tritium retention by this mechanism could be a limiting factor for the operation of fusion reactors, such as ITER. Hence there is a need to investigate ways of mitigating T retention and also for detritiating surfaces by either desorption of T or removal of tritiated deposits. The results of the removal of codeposits from CFC tiles by pulsed laser ablation are reported here. The results show that it is possible to completely remove a 300μm thick hydrogen isotope rich carbon film at a rate of 12x10-3m2/hr by this method and that with optimisation of the laser parameters there is scope to improve the treatment rates to provide a useful tool for managing T inventory in tokamaks.",

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T1 - Detritiation of JET tiles by laser cleaning

AU - Widdowson, A.

AU - Coad, J. P.

AU - Farcage, D.

AU - Hole, D.

AU - Likonen, Jari

AU - Renvall, Tommi

AU - Semerok, A.

AU - Thro, P.-Y.

AU - JET-EFDA Contributors,

PY - 2008

Y1 - 2008

N2 - The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern to the fusion community as the scale of tritium retention by this mechanism could be a limiting factor for the operation of fusion reactors, such as ITER. Hence there is a need to investigate ways of mitigating T retention and also for detritiating surfaces by either desorption of T or removal of tritiated deposits. The results of the removal of codeposits from CFC tiles by pulsed laser ablation are reported here. The results show that it is possible to completely remove a 300μm thick hydrogen isotope rich carbon film at a rate of 12x10-3m2/hr by this method and that with optimisation of the laser parameters there is scope to improve the treatment rates to provide a useful tool for managing T inventory in tokamaks.

AB - The retention of tritium (T) by carbon based deposits on tokamak surfaces is of increasing concern to the fusion community as the scale of tritium retention by this mechanism could be a limiting factor for the operation of fusion reactors, such as ITER. Hence there is a need to investigate ways of mitigating T retention and also for detritiating surfaces by either desorption of T or removal of tritiated deposits. The results of the removal of codeposits from CFC tiles by pulsed laser ablation are reported here. The results show that it is possible to completely remove a 300μm thick hydrogen isotope rich carbon film at a rate of 12x10-3m2/hr by this method and that with optimisation of the laser parameters there is scope to improve the treatment rates to provide a useful tool for managing T inventory in tokamaks.

U2 - 10.13182/FST08-A1763

DO - 10.13182/FST08-A1763

M3 - Article

SN - 1536-1055

VL - 54

SP - 51

EP - 54

JO - Fusion Science and Technology

JF - Fusion Science and Technology

IS - 1

ER -

Detritiation of JET tiles by laser cleaning

Abstract

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