The deuterium inventory in ASDEX Upgrade

M. Mayer (Corresponding Author), V. Rohde, G. Ramos, Elizaveta Vainonen-Ahlgren, Jari Likonen, A. Herrmann, R. Neu, ASDEX Upgrade Team

    Research output: Contribution to journalArticleScientificpeer-review

    22 Citations (Scopus)

    Abstract

    The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam analysis techniques and SIMS for different discharge campaigns between the years 2002 and 2005. ASDEX Upgrade was a carbon dominated machine during this phase. Full poloidal sections of the lower and upper divertor tile surfaces, limiter tiles, gaps between divertor tiles, gaps between inner heat shield tiles and samples from remote areas below the roof baffle and in pump ducts were analysed, thus offering an exhaustive survey of all relevant areas in ASDEX Upgrade. Deuterium is mainly trapped on plasma-exposed surfaces of inner divertor tiles, where about 70% of the retained deuterium inventory is found. About 20% of the inventory is retained at or below the divertor roof baffle, and about 10% is observed in other areas, such as the outer divertor and in gaps between tiles. The long term deuterium retention is 3–4% of the total deuterium input. The obtained results are compared with gas balance measurements, and conclusions about tritium retention in ITER are made.
    Original languageEnglish
    Pages (from-to)1607-1617
    JournalNuclear Fusion
    Volume47
    Issue number11
    DOIs
    Publication statusPublished - 2007
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    tiles
    deuterium
    baffles
    roofs
    tritium
    ducts
    secondary ion mass spectrometry
    ion beams
    pumps
    heat
    carbon
    gases

    Keywords

    • ASDEX upgrade
    • deuterium
    • deuterium inventory
    • ITER
    • fusion energy
    • fusion reactors
    • plasma

    Cite this

    Mayer, M., Rohde, V., Ramos, G., Vainonen-Ahlgren, E., Likonen, J., Herrmann, A., ... Team, ASDEX. U. (2007). The deuterium inventory in ASDEX Upgrade. Nuclear Fusion, 47(11), 1607-1617. https://doi.org/10.1088/0029-5515/47/11/024
    Mayer, M. ; Rohde, V. ; Ramos, G. ; Vainonen-Ahlgren, Elizaveta ; Likonen, Jari ; Herrmann, A. ; Neu, R. ; Team, ASDEX Upgrade. / The deuterium inventory in ASDEX Upgrade. In: Nuclear Fusion. 2007 ; Vol. 47, No. 11. pp. 1607-1617.
    @article{43c049eeb21a4c8f9d610e0f1ed7b690,
    title = "The deuterium inventory in ASDEX Upgrade",
    abstract = "The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam analysis techniques and SIMS for different discharge campaigns between the years 2002 and 2005. ASDEX Upgrade was a carbon dominated machine during this phase. Full poloidal sections of the lower and upper divertor tile surfaces, limiter tiles, gaps between divertor tiles, gaps between inner heat shield tiles and samples from remote areas below the roof baffle and in pump ducts were analysed, thus offering an exhaustive survey of all relevant areas in ASDEX Upgrade. Deuterium is mainly trapped on plasma-exposed surfaces of inner divertor tiles, where about 70{\%} of the retained deuterium inventory is found. About 20{\%} of the inventory is retained at or below the divertor roof baffle, and about 10{\%} is observed in other areas, such as the outer divertor and in gaps between tiles. The long term deuterium retention is 3–4{\%} of the total deuterium input. The obtained results are compared with gas balance measurements, and conclusions about tritium retention in ITER are made.",
    keywords = "ASDEX upgrade, deuterium, deuterium inventory, ITER, fusion energy, fusion reactors, plasma",
    author = "M. Mayer and V. Rohde and G. Ramos and Elizaveta Vainonen-Ahlgren and Jari Likonen and A. Herrmann and R. Neu and Team, {ASDEX Upgrade}",
    year = "2007",
    doi = "10.1088/0029-5515/47/11/024",
    language = "English",
    volume = "47",
    pages = "1607--1617",
    journal = "Nuclear Fusion",
    issn = "0029-5515",
    publisher = "Institute of Physics IOP",
    number = "11",

    }

    Mayer, M, Rohde, V, Ramos, G, Vainonen-Ahlgren, E, Likonen, J, Herrmann, A, Neu, R & Team, ASDEXU 2007, 'The deuterium inventory in ASDEX Upgrade', Nuclear Fusion, vol. 47, no. 11, pp. 1607-1617. https://doi.org/10.1088/0029-5515/47/11/024

    The deuterium inventory in ASDEX Upgrade. / Mayer, M. (Corresponding Author); Rohde, V.; Ramos, G.; Vainonen-Ahlgren, Elizaveta; Likonen, Jari; Herrmann, A.; Neu, R.; Team, ASDEX Upgrade.

    In: Nuclear Fusion, Vol. 47, No. 11, 2007, p. 1607-1617.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - The deuterium inventory in ASDEX Upgrade

    AU - Mayer, M.

    AU - Rohde, V.

    AU - Ramos, G.

    AU - Vainonen-Ahlgren, Elizaveta

    AU - Likonen, Jari

    AU - Herrmann, A.

    AU - Neu, R.

    AU - Team, ASDEX Upgrade

    PY - 2007

    Y1 - 2007

    N2 - The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam analysis techniques and SIMS for different discharge campaigns between the years 2002 and 2005. ASDEX Upgrade was a carbon dominated machine during this phase. Full poloidal sections of the lower and upper divertor tile surfaces, limiter tiles, gaps between divertor tiles, gaps between inner heat shield tiles and samples from remote areas below the roof baffle and in pump ducts were analysed, thus offering an exhaustive survey of all relevant areas in ASDEX Upgrade. Deuterium is mainly trapped on plasma-exposed surfaces of inner divertor tiles, where about 70% of the retained deuterium inventory is found. About 20% of the inventory is retained at or below the divertor roof baffle, and about 10% is observed in other areas, such as the outer divertor and in gaps between tiles. The long term deuterium retention is 3–4% of the total deuterium input. The obtained results are compared with gas balance measurements, and conclusions about tritium retention in ITER are made.

    AB - The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam analysis techniques and SIMS for different discharge campaigns between the years 2002 and 2005. ASDEX Upgrade was a carbon dominated machine during this phase. Full poloidal sections of the lower and upper divertor tile surfaces, limiter tiles, gaps between divertor tiles, gaps between inner heat shield tiles and samples from remote areas below the roof baffle and in pump ducts were analysed, thus offering an exhaustive survey of all relevant areas in ASDEX Upgrade. Deuterium is mainly trapped on plasma-exposed surfaces of inner divertor tiles, where about 70% of the retained deuterium inventory is found. About 20% of the inventory is retained at or below the divertor roof baffle, and about 10% is observed in other areas, such as the outer divertor and in gaps between tiles. The long term deuterium retention is 3–4% of the total deuterium input. The obtained results are compared with gas balance measurements, and conclusions about tritium retention in ITER are made.

    KW - ASDEX upgrade

    KW - deuterium

    KW - deuterium inventory

    KW - ITER

    KW - fusion energy

    KW - fusion reactors

    KW - plasma

    U2 - 10.1088/0029-5515/47/11/024

    DO - 10.1088/0029-5515/47/11/024

    M3 - Article

    VL - 47

    SP - 1607

    EP - 1617

    JO - Nuclear Fusion

    JF - Nuclear Fusion

    SN - 0029-5515

    IS - 11

    ER -

    Mayer M, Rohde V, Ramos G, Vainonen-Ahlgren E, Likonen J, Herrmann A et al. The deuterium inventory in ASDEX Upgrade. Nuclear Fusion. 2007;47(11):1607-1617. https://doi.org/10.1088/0029-5515/47/11/024