Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

Jari Likonen; N. Bekris; J.P. Coad; C. Ayres; N. Gotts; I. Jepu; Y. Zayachuk; A. Widdowson; I. Wilson; N. Catarino; E. De alves

doi:10.1016/j.nme.2022.101312

Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

Jari Likonen^*
, N. Bekris
, J.P. Coad
, C. Ayres
, N. Gotts
, I. Jepu
, Y. Zayachuk
, A. Widdowson
, I. Wilson
, N. Catarino
, E. De alves

^*Corresponding author for this work

BA4511 Fusion energy

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

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Abstract

In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at ∼590 and 820 °C. A few samples were reannealed at 850 °C using the same heating procedure and it turned out that a further ∼40–50 % of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of ∼4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of ∼3 with these results.

Original language	English
Article number	101312
Journal	Nuclear Materials and Energy
Volume	33
DOIs	https://doi.org/10.1016/j.nme.2022.101312
Publication status	Published - Oct 2022
MoE publication type	A1 Journal article-refereed

Funding

This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion)), from the EPSRC [grant number EP/W006839/1] and within the framework of the Contract for the Operation of the JET Facilities and has received funding from the European Union's Horizon 2020 research and innovation programme. The research used UKAEA's Materials Research Facility, which has been funded by and is part of the UK's National Nuclear User Facility and Henry Royce Institute for Advanced Materials.

UN SDGs

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

SDG 7 Affordable and Clean Energy

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title = "Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997",

abstract = "In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at ∼590 and 820 °C. A few samples were reannealed at 850 °C using the same heating procedure and it turned out that a further ∼40–50 \% of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of ∼4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of ∼3 with these results.",

author = "Jari Likonen and N. Bekris and J.P. Coad and C. Ayres and N. Gotts and I. Jepu and Y. Zayachuk and A. Widdowson and I. Wilson and N. Catarino and \{De alves\}, E.",

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doi = "10.1016/j.nme.2022.101312",

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T1 - Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

AU - Likonen, Jari

AU - Bekris, N.

AU - Coad, J.P.

AU - Ayres, C.

AU - Gotts, N.

AU - Jepu, I.

AU - Zayachuk, Y.

AU - Widdowson, A.

AU - Wilson, I.

AU - Catarino, N.

AU - De alves, E.

PY - 2022/10

Y1 - 2022/10

N2 - In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at ∼590 and 820 °C. A few samples were reannealed at 850 °C using the same heating procedure and it turned out that a further ∼40–50 % of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of ∼4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of ∼3 with these results.

AB - In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at ∼590 and 820 °C. A few samples were reannealed at 850 °C using the same heating procedure and it turned out that a further ∼40–50 % of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of ∼4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of ∼3 with these results.

UR - https://www.scopus.com/pages/publications/85142678486

U2 - 10.1016/j.nme.2022.101312

DO - 10.1016/j.nme.2022.101312

M3 - Article

SN - 2352-1791

VL - 33

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 101312

ER -

Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

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UN SDGs

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