Tritium related studies within the JET fusion technology work programme

S. Rosanvallon, N. Bekris, J. Braet, P. Coad, G. Counsell, I. Cristescu, C. Grisolia, F. Le Guern, G. Ionita, Jari Likonen, A. Perevezenstev, G. Piazza, C. Poletiko, M. Rubel, J.M. Weulersse, J. Williams, JET-EFDA Contributors

    Research output: Contribution to journalArticleScientificpeer-review

    2 Citations (Scopus)

    Abstract

    The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fusion Development Agreement, to address issues related to JET and ITER. In particular, there are four topics related to tritium being investigated. Based on the experience gained on the existing tokamaks, first calculations indicate that in-vessel tritium retention could represent a burden for ITER operation. Therefore erosion/deposition studies are being performed in order to better understand the layer co-deposition and tritium retention processes in tokamaks. Moreover, testing of in-situ detritiation processes, in particular laser and flash lamp treatments, should assess detritiation techniques for in-vessel components in the ITER-relevant JET configuration. To reduce the constraints on waste disposal, dedicated procedures are being developed for detritiation of metals, graphite, carbon-fibre composites, process and housekeeping waste. During the operational and decommissioning phases of a fusion reactor, many processes will produce tritiated water. Key components for an ITER relevant water detritiation facility are being studied experimentally with the aim of producing a complete design that could be implemented and tested at JET. This paper describes these topics of the FT-programme, the strategy developed and the results obtained so far.

    Original languageEnglish
    Pages (from-to)268 - 273
    Number of pages6
    JournalFusion Science and Technology
    Volume48
    Issue number1
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Tritium
    tritium
    Fusion reactions
    fusion
    vessels
    Decommissioning (nuclear reactors)
    decommissioning
    waste disposal
    flash lamps
    Graphite
    Water
    fusion reactors
    fiber composites
    Fusion reactors
    carbon fibers
    Electric lamps
    Waste disposal
    water
    Carbon fibers
    luminaires

    Cite this

    Rosanvallon, S., Bekris, N., Braet, J., Coad, P., Counsell, G., Cristescu, I., ... JET-EFDA Contributors (2005). Tritium related studies within the JET fusion technology work programme. Fusion Science and Technology, 48(1), 268 - 273. https://doi.org/10.13182/FST05-A925
    Rosanvallon, S. ; Bekris, N. ; Braet, J. ; Coad, P. ; Counsell, G. ; Cristescu, I. ; Grisolia, C. ; Le Guern, F. ; Ionita, G. ; Likonen, Jari ; Perevezenstev, A. ; Piazza, G. ; Poletiko, C. ; Rubel, M. ; Weulersse, J.M. ; Williams, J. ; JET-EFDA Contributors. / Tritium related studies within the JET fusion technology work programme. In: Fusion Science and Technology. 2005 ; Vol. 48, No. 1. pp. 268 - 273.
    @article{758973552a214efa98b75f88d0d56d19,
    title = "Tritium related studies within the JET fusion technology work programme",
    abstract = "The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fusion Development Agreement, to address issues related to JET and ITER. In particular, there are four topics related to tritium being investigated. Based on the experience gained on the existing tokamaks, first calculations indicate that in-vessel tritium retention could represent a burden for ITER operation. Therefore erosion/deposition studies are being performed in order to better understand the layer co-deposition and tritium retention processes in tokamaks. Moreover, testing of in-situ detritiation processes, in particular laser and flash lamp treatments, should assess detritiation techniques for in-vessel components in the ITER-relevant JET configuration. To reduce the constraints on waste disposal, dedicated procedures are being developed for detritiation of metals, graphite, carbon-fibre composites, process and housekeeping waste. During the operational and decommissioning phases of a fusion reactor, many processes will produce tritiated water. Key components for an ITER relevant water detritiation facility are being studied experimentally with the aim of producing a complete design that could be implemented and tested at JET. This paper describes these topics of the FT-programme, the strategy developed and the results obtained so far.",
    author = "S. Rosanvallon and N. Bekris and J. Braet and P. Coad and G. Counsell and I. Cristescu and C. Grisolia and {Le Guern}, F. and G. Ionita and Jari Likonen and A. Perevezenstev and G. Piazza and C. Poletiko and M. Rubel and J.M. Weulersse and J. Williams and {JET-EFDA Contributors}",
    year = "2005",
    doi = "10.13182/FST05-A925",
    language = "English",
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    pages = "268 -- 273",
    journal = "Fusion Science and Technology",
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    publisher = "American Nuclear Society ANS",
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    Rosanvallon, S, Bekris, N, Braet, J, Coad, P, Counsell, G, Cristescu, I, Grisolia, C, Le Guern, F, Ionita, G, Likonen, J, Perevezenstev, A, Piazza, G, Poletiko, C, Rubel, M, Weulersse, JM, Williams, J & JET-EFDA Contributors 2005, 'Tritium related studies within the JET fusion technology work programme', Fusion Science and Technology, vol. 48, no. 1, pp. 268 - 273. https://doi.org/10.13182/FST05-A925

    Tritium related studies within the JET fusion technology work programme. / Rosanvallon, S.; Bekris, N.; Braet, J.; Coad, P.; Counsell, G.; Cristescu, I.; Grisolia, C.; Le Guern, F.; Ionita, G.; Likonen, Jari; Perevezenstev, A.; Piazza, G.; Poletiko, C.; Rubel, M.; Weulersse, J.M.; Williams, J.; JET-EFDA Contributors.

    In: Fusion Science and Technology, Vol. 48, No. 1, 2005, p. 268 - 273.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Tritium related studies within the JET fusion technology work programme

    AU - Rosanvallon, S.

    AU - Bekris, N.

    AU - Braet, J.

    AU - Coad, P.

    AU - Counsell, G.

    AU - Cristescu, I.

    AU - Grisolia, C.

    AU - Le Guern, F.

    AU - Ionita, G.

    AU - Likonen, Jari

    AU - Perevezenstev, A.

    AU - Piazza, G.

    AU - Poletiko, C.

    AU - Rubel, M.

    AU - Weulersse, J.M.

    AU - Williams, J.

    AU - JET-EFDA Contributors,

    PY - 2005

    Y1 - 2005

    N2 - The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fusion Development Agreement, to address issues related to JET and ITER. In particular, there are four topics related to tritium being investigated. Based on the experience gained on the existing tokamaks, first calculations indicate that in-vessel tritium retention could represent a burden for ITER operation. Therefore erosion/deposition studies are being performed in order to better understand the layer co-deposition and tritium retention processes in tokamaks. Moreover, testing of in-situ detritiation processes, in particular laser and flash lamp treatments, should assess detritiation techniques for in-vessel components in the ITER-relevant JET configuration. To reduce the constraints on waste disposal, dedicated procedures are being developed for detritiation of metals, graphite, carbon-fibre composites, process and housekeeping waste. During the operational and decommissioning phases of a fusion reactor, many processes will produce tritiated water. Key components for an ITER relevant water detritiation facility are being studied experimentally with the aim of producing a complete design that could be implemented and tested at JET. This paper describes these topics of the FT-programme, the strategy developed and the results obtained so far.

    AB - The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fusion Development Agreement, to address issues related to JET and ITER. In particular, there are four topics related to tritium being investigated. Based on the experience gained on the existing tokamaks, first calculations indicate that in-vessel tritium retention could represent a burden for ITER operation. Therefore erosion/deposition studies are being performed in order to better understand the layer co-deposition and tritium retention processes in tokamaks. Moreover, testing of in-situ detritiation processes, in particular laser and flash lamp treatments, should assess detritiation techniques for in-vessel components in the ITER-relevant JET configuration. To reduce the constraints on waste disposal, dedicated procedures are being developed for detritiation of metals, graphite, carbon-fibre composites, process and housekeeping waste. During the operational and decommissioning phases of a fusion reactor, many processes will produce tritiated water. Key components for an ITER relevant water detritiation facility are being studied experimentally with the aim of producing a complete design that could be implemented and tested at JET. This paper describes these topics of the FT-programme, the strategy developed and the results obtained so far.

    U2 - 10.13182/FST05-A925

    DO - 10.13182/FST05-A925

    M3 - Article

    VL - 48

    SP - 268

    EP - 273

    JO - Fusion Science and Technology

    JF - Fusion Science and Technology

    SN - 1536-1055

    IS - 1

    ER -

    Rosanvallon S, Bekris N, Braet J, Coad P, Counsell G, Cristescu I et al. Tritium related studies within the JET fusion technology work programme. Fusion Science and Technology. 2005;48(1):268 - 273. https://doi.org/10.13182/FST05-A925