Modelling the erosion of beryllium carbide surfaces

M. Mehine (Corresponding Author), C. Björkas, K. Vörtler, K. Nordlund, Markus Airila

    Research output: Contribution to journalArticleScientificpeer-review

    7 Citations (Scopus)

    Abstract

    Redeposition of beryllium eroded from main chamber plasma facing components of ITER onto the divertor material carbon creates a mixed material, beryllium carbide Be2C, whose interaction with the plasma is not well known. In this study, we have investigated the erosion of Be2C by deuterium using molecular dynamics simulations and ERO impurity modelling. We found that beryllium sputters preferentially over carbon and identified the sputtering mechanism in the ion energy range 10–100 eV to be both physical and swift chemical sputtering. In addition to single atoms, different types of small molecules/clusters were sputtered, the most frequently occurring molecules being BeD, Be2D, and CD. The sputtering threshold was found to lie between 10 and 15 eV. The MD sputtering yields were used in plasma impurity simulations, serving as a replacement for input data obtained with TRIM. This changes the accumulation rate of impurity Be in the divertor region compared to previous estimates.
    Original languageEnglish
    Pages (from-to)1-7
    Number of pages7
    JournalJournal of Nuclear Materials
    Volume414
    Issue number1
    DOIs
    Publication statusPublished - 2011
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Beryllium
    beryllium
    carbides
    erosion
    Sputtering
    Carbides
    Erosion
    sputtering
    Impurities
    Plasmas
    impurities
    Carbon
    Molecules
    Deuterium
    carbon
    Beam plasma interactions
    Molecular dynamics
    molecules
    deuterium
    simulation

    Cite this

    Mehine, M. ; Björkas, C. ; Vörtler, K. ; Nordlund, K. ; Airila, Markus. / Modelling the erosion of beryllium carbide surfaces. In: Journal of Nuclear Materials. 2011 ; Vol. 414, No. 1. pp. 1-7.
    @article{439f083ed9ac4e2f8ee53c9145169d5b,
    title = "Modelling the erosion of beryllium carbide surfaces",
    abstract = "Redeposition of beryllium eroded from main chamber plasma facing components of ITER onto the divertor material carbon creates a mixed material, beryllium carbide Be2C, whose interaction with the plasma is not well known. In this study, we have investigated the erosion of Be2C by deuterium using molecular dynamics simulations and ERO impurity modelling. We found that beryllium sputters preferentially over carbon and identified the sputtering mechanism in the ion energy range 10–100 eV to be both physical and swift chemical sputtering. In addition to single atoms, different types of small molecules/clusters were sputtered, the most frequently occurring molecules being BeD, Be2D, and CD. The sputtering threshold was found to lie between 10 and 15 eV. The MD sputtering yields were used in plasma impurity simulations, serving as a replacement for input data obtained with TRIM. This changes the accumulation rate of impurity Be in the divertor region compared to previous estimates.",
    author = "M. Mehine and C. Bj{\"o}rkas and K. V{\"o}rtler and K. Nordlund and Markus Airila",
    year = "2011",
    doi = "10.1016/j.jnucmat.2011.03.022",
    language = "English",
    volume = "414",
    pages = "1--7",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
    publisher = "Elsevier",
    number = "1",

    }

    Modelling the erosion of beryllium carbide surfaces. / Mehine, M. (Corresponding Author); Björkas, C.; Vörtler, K.; Nordlund, K.; Airila, Markus.

    In: Journal of Nuclear Materials, Vol. 414, No. 1, 2011, p. 1-7.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Modelling the erosion of beryllium carbide surfaces

    AU - Mehine, M.

    AU - Björkas, C.

    AU - Vörtler, K.

    AU - Nordlund, K.

    AU - Airila, Markus

    PY - 2011

    Y1 - 2011

    N2 - Redeposition of beryllium eroded from main chamber plasma facing components of ITER onto the divertor material carbon creates a mixed material, beryllium carbide Be2C, whose interaction with the plasma is not well known. In this study, we have investigated the erosion of Be2C by deuterium using molecular dynamics simulations and ERO impurity modelling. We found that beryllium sputters preferentially over carbon and identified the sputtering mechanism in the ion energy range 10–100 eV to be both physical and swift chemical sputtering. In addition to single atoms, different types of small molecules/clusters were sputtered, the most frequently occurring molecules being BeD, Be2D, and CD. The sputtering threshold was found to lie between 10 and 15 eV. The MD sputtering yields were used in plasma impurity simulations, serving as a replacement for input data obtained with TRIM. This changes the accumulation rate of impurity Be in the divertor region compared to previous estimates.

    AB - Redeposition of beryllium eroded from main chamber plasma facing components of ITER onto the divertor material carbon creates a mixed material, beryllium carbide Be2C, whose interaction with the plasma is not well known. In this study, we have investigated the erosion of Be2C by deuterium using molecular dynamics simulations and ERO impurity modelling. We found that beryllium sputters preferentially over carbon and identified the sputtering mechanism in the ion energy range 10–100 eV to be both physical and swift chemical sputtering. In addition to single atoms, different types of small molecules/clusters were sputtered, the most frequently occurring molecules being BeD, Be2D, and CD. The sputtering threshold was found to lie between 10 and 15 eV. The MD sputtering yields were used in plasma impurity simulations, serving as a replacement for input data obtained with TRIM. This changes the accumulation rate of impurity Be in the divertor region compared to previous estimates.

    U2 - 10.1016/j.jnucmat.2011.03.022

    DO - 10.1016/j.jnucmat.2011.03.022

    M3 - Article

    VL - 414

    SP - 1

    EP - 7

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 1

    ER -