Tritium related studies at the JET facilities

R. Lässer (Corresponding Author), N. Bekris, A.C. Bell, C. Caldwell-Nichols, I. Cristescu, S. Ciattaglia, P. Coad, Ch. Day, M. Glugla, Jari Likonen, D.K. Murdoch, S. Rosanvallon, F. Scaffidi-Argentina

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)

    Abstract

    The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore best suited to study tritium and fusion related issues. JET is now managed under the European Fusion Development Agreement (EFDA) and experiments, enhancements and technology issues are organized as Scientific and Technical (S/T) tasks within various Task Forces (TFs). A large variety of different activities is performed within the fusion technology (FT) TF. A brief summary of FT-studies related to tritium is given presenting topics such as tritium inventory in flakes and tiles, tritium depth profiles in plasma facing components (PFCs), development of a facility for full recovery of the tritium in flakes and tiles, erosion and deposition of plasma exposed materials determined by surface sensitive techniques, development of detritiation techniques for different waste categories, characterization of packing/catalyst combinations for liquid phase catalytic exchange column and design studies of a water detritiation plant using either a solid polymer or KOH electrolyser, test of ITER cryo-panels in the JET Active Gas Handling System, etc.
    Original languageEnglish
    Pages (from-to)75-80
    Number of pages6
    JournalFusion Engineering and Design
    Volume69
    Issue number1-4
    DOIs
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Tritium
    Fusion reactions
    Tile
    Plasmas
    Erosion
    Recovery
    Catalysts
    Liquids
    Polymers
    Gases
    Water
    Experiments

    Keywords

    • tritium
    • JET
    • fusion energy
    • fusion reactors
    • ITER

    Cite this

    Lässer, R., Bekris, N., Bell, A. C., Caldwell-Nichols, C., Cristescu, I., Ciattaglia, S., ... Scaffidi-Argentina, F. (2003). Tritium related studies at the JET facilities. Fusion Engineering and Design, 69(1-4), 75-80. https://doi.org/10.1016/S0920-3796(03)00248-5
    Lässer, R. ; Bekris, N. ; Bell, A.C. ; Caldwell-Nichols, C. ; Cristescu, I. ; Ciattaglia, S. ; Coad, P. ; Day, Ch. ; Glugla, M. ; Likonen, Jari ; Murdoch, D.K. ; Rosanvallon, S. ; Scaffidi-Argentina, F. / Tritium related studies at the JET facilities. In: Fusion Engineering and Design. 2003 ; Vol. 69, No. 1-4. pp. 75-80.
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    abstract = "The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore best suited to study tritium and fusion related issues. JET is now managed under the European Fusion Development Agreement (EFDA) and experiments, enhancements and technology issues are organized as Scientific and Technical (S/T) tasks within various Task Forces (TFs). A large variety of different activities is performed within the fusion technology (FT) TF. A brief summary of FT-studies related to tritium is given presenting topics such as tritium inventory in flakes and tiles, tritium depth profiles in plasma facing components (PFCs), development of a facility for full recovery of the tritium in flakes and tiles, erosion and deposition of plasma exposed materials determined by surface sensitive techniques, development of detritiation techniques for different waste categories, characterization of packing/catalyst combinations for liquid phase catalytic exchange column and design studies of a water detritiation plant using either a solid polymer or KOH electrolyser, test of ITER cryo-panels in the JET Active Gas Handling System, etc.",
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    author = "R. L{\"a}sser and N. Bekris and A.C. Bell and C. Caldwell-Nichols and I. Cristescu and S. Ciattaglia and P. Coad and Ch. Day and M. Glugla and Jari Likonen and D.K. Murdoch and S. Rosanvallon and F. Scaffidi-Argentina",
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    Lässer, R, Bekris, N, Bell, AC, Caldwell-Nichols, C, Cristescu, I, Ciattaglia, S, Coad, P, Day, C, Glugla, M, Likonen, J, Murdoch, DK, Rosanvallon, S & Scaffidi-Argentina, F 2003, 'Tritium related studies at the JET facilities', Fusion Engineering and Design, vol. 69, no. 1-4, pp. 75-80. https://doi.org/10.1016/S0920-3796(03)00248-5

    Tritium related studies at the JET facilities. / Lässer, R. (Corresponding Author); Bekris, N. ; Bell, A.C.; Caldwell-Nichols, C.; Cristescu, I.; Ciattaglia, S.; Coad, P.; Day, Ch.; Glugla, M.; Likonen, Jari; Murdoch, D.K.; Rosanvallon, S.; Scaffidi-Argentina, F.

    In: Fusion Engineering and Design, Vol. 69, No. 1-4, 2003, p. 75-80.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

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    AU - Lässer, R.

    AU - Bekris, N.

    AU - Bell, A.C.

    AU - Caldwell-Nichols, C.

    AU - Cristescu, I.

    AU - Ciattaglia, S.

    AU - Coad, P.

    AU - Day, Ch.

    AU - Glugla, M.

    AU - Likonen, Jari

    AU - Murdoch, D.K.

    AU - Rosanvallon, S.

    AU - Scaffidi-Argentina, F.

    PY - 2003

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    N2 - The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore best suited to study tritium and fusion related issues. JET is now managed under the European Fusion Development Agreement (EFDA) and experiments, enhancements and technology issues are organized as Scientific and Technical (S/T) tasks within various Task Forces (TFs). A large variety of different activities is performed within the fusion technology (FT) TF. A brief summary of FT-studies related to tritium is given presenting topics such as tritium inventory in flakes and tiles, tritium depth profiles in plasma facing components (PFCs), development of a facility for full recovery of the tritium in flakes and tiles, erosion and deposition of plasma exposed materials determined by surface sensitive techniques, development of detritiation techniques for different waste categories, characterization of packing/catalyst combinations for liquid phase catalytic exchange column and design studies of a water detritiation plant using either a solid polymer or KOH electrolyser, test of ITER cryo-panels in the JET Active Gas Handling System, etc.

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    KW - JET

    KW - fusion energy

    KW - fusion reactors

    KW - ITER

    U2 - 10.1016/S0920-3796(03)00248-5

    DO - 10.1016/S0920-3796(03)00248-5

    M3 - Article

    VL - 69

    SP - 75

    EP - 80

    JO - Fusion Engineering and Design

    JF - Fusion Engineering and Design

    SN - 0920-3796

    IS - 1-4

    ER -

    Lässer R, Bekris N, Bell AC, Caldwell-Nichols C, Cristescu I, Ciattaglia S et al. Tritium related studies at the JET facilities. Fusion Engineering and Design. 2003;69(1-4):75-80. https://doi.org/10.1016/S0920-3796(03)00248-5