Search Results - "Landman, I.S."

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  1. 1

    Melt damage simulation of W-macrobrush and divertor gaps after multiple transient events in ITER by Bazylev, B.N., Janeschitz, G., Landman, I.S., Loarte, A., Pestchanyi, S.E.

    Published in Journal of nuclear materials (15-06-2007)
    “…Tungsten in the form of macrobrush structure is foreseen as one of two candidate materials for the ITER divertor and dome. In ITER, even for moderate and weak…”
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    Journal Article Conference Proceeding
  2. 2

    Erosion of macrobrush tungsten armor after multiple intense transient events in ITER by Bazylev, B.N., Janeschitz, G., Landman, I.S., Pestchanyi, S.E.

    Published in Fusion engineering and design (01-11-2005)
    “…The tungsten macrobrushes are foreseen as a perspective ITER divertor armour. Macroscopic erosion by melt motion is the dominating damage mechanism for…”
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    Journal Article Conference Proceeding
  3. 3

    Development of an advanced magnetic equilibrium model for fusion reactor system codes by Franza, F., Landman, I.S., Pestchanyi, S.

    Published in Fusion engineering and design (01-11-2018)
    “…Fusion system codes are vital computational tools for the assessment of the key design parameters of a fusion power plant. The main goal is to capture the key…”
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    Journal Article
  4. 4

    Modelling of massive gas injection for ITER disruption mitigation by Landman, I.S., Pestchanyi, S.E., Igitkhanov, Y., Pitts, R.

    Published in Journal of nuclear materials (01-07-2013)
    “…In ITER the plasma impact on the wall after disruptions can be mitigated by a preventive massive gas injection (MGI) of a noble gas into the confined plasma…”
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    Journal Article
  5. 5

    Modelling of radiation impact on ITER Beryllium wall by Landman, I.S., Janeschitz, G.

    Published in Journal of nuclear materials (30-04-2009)
    “…In the ITER H-Mode confinement regime, edge localized instabilities (ELMs) will perturb the discharge. Plasma lost after each ELM moves along magnetic field…”
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    Journal Article Conference Proceeding
  6. 6

    Two-dimensional modeling of disruption mitigation by gas injection by Landman, I.S., Pestchanyi, S.E., Igitkhanov, Y., Pitts, R.

    Published in Fusion engineering and design (01-10-2011)
    “…In ITER, wall damage after the disruptions can be mitigated using preventive massive gas injection (MGI) of noble gases into confined plasma. In the plasma the…”
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    Journal Article Conference Proceeding
  7. 7

    Modelling of SOL transport and radiation losses for ITER with the integrated tokamak code TOKES by Landman, I.S., Janeschitz, G.

    Published in Journal of nuclear materials (15-06-2009)
    “…For integrated simulations of tokamak plasma equilibrium and surface processes the code TOKES was recently designed. The new radiation database and SOL model…”
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    Journal Article Conference Proceeding
  8. 8

    Numerical simulations of plasma wall interactions for ITER by Landman, I.S., Janeschitz, G.

    Published in Journal of nuclear materials (15-06-2007)
    “…At the ELMy H-mode of ITER repetitive transient processes may cause wall material vaporization and subsequent contamination of the confinement region. The…”
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    Journal Article Conference Proceeding
  9. 9

    Evaporation and vapor shielding of CFC targets exposed to plasma heat fluxes relevant to ITER ELMs by Safronov, V.M., Arkhipov, N.I., Landman, I.S., Pestchanyi, S.E., Toporkov, D.A., Zhitlukhin, A.M.

    Published in Journal of nuclear materials (30-04-2009)
    “…Carbon fibre composite NB31 was tested at plasma gun facility MK-200UG by plasma heat fluxes relevant to Edge Localised Modes in ITER. The paper reports the…”
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    Journal Article
  10. 10

    Modelling of wall and SOL processes and contamination of ITER plasma after impurity injection with the tokamak code TOKES by Landman, I.S., Pestchanyi, S.E., Igitkhanov, Y., Pitts, R.

    Published in Fusion engineering and design (01-12-2010)
    “…In the future tokamak ITER the damage to the wall after the disruptions can be mitigated using preventive massive gas injection (MGI) of noble gases into…”
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    Journal Article Conference Proceeding
  11. 11

    Contamination of ITER core by impurities of tungsten and carbon by Landman, I.S., Janeschitz, G.

    Published in Fusion engineering and design (01-12-2008)
    “…The ITER operation including ELMy H-mode is simulated with the code TOKES that considers processes among D-, T-, He-, C- and W-species and aims at fully…”
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    Journal Article Conference Proceeding
  12. 12

    Tungsten melt layer erosion due to J×B force under conditions relevant to ITER ELMs by Garkusha, I.E., Bazylev, B.N., Bandura, A.N., Byrka, O.V., Chebotarev, V.V., Landman, I.S., Kulik, N.V., Makhlaj, V.A., Petrov, Yu.V., Solyakov, D.G., Tereshin, V.I.

    Published in Journal of nuclear materials (15-06-2007)
    “…The behavior of tungsten under repetitive hydrogen plasma impacts causing surface melting in conditions of an applied J×B force of up to 20MN/m3 is studied…”
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    Journal Article Conference Proceeding
  13. 13

    Erosion of tungsten armor after multiple intense transient events in ITER by Bazylev, B.N., Janeschitz, G., Landman, I.S., Pestchanyi, S.E.

    Published in Journal of nuclear materials (01-03-2005)
    “…Macroscopic erosion by melt motion is the dominating damage mechanism for tungsten armour under high-heat loads with energy deposition W>1MJ/m2 and τ>0.1ms…”
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    Journal Article
  14. 14

    Simulation of tokamak armour erosion and plasma contamination at intense transient heat fluxes in ITER by Landman, I.S., Bazylev, B.N., Garkusha, I.E., Loarte, A., Pestchanyi, S.E., Safronov, V.M.

    Published in Journal of nuclear materials (01-03-2005)
    “…For ITER, the potential material damage of plasma facing tungsten-, CFC-, or beryllium components during transient processes such as ELMs or mitigated…”
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    Journal Article
  15. 15

    Simulation of dust production in ITER transient events by Pestchanyi, S.E., Landman, I.S.

    Published in Fusion engineering and design (01-12-2008)
    “…Dust production from the divertor armour during edge-localised modes (ELMs) has been investigated. Analysis of available experimental data on the dust particle…”
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    Journal Article Conference Proceeding
  16. 16

    Molecular dynamics simulations of the effect of deuterium on tungsten erosion by oxygen by Landman, I.S., Wuerz, H.

    Published in Journal of nuclear materials (01-03-2003)
    “…Chemical erosion of tungsten is one of the critical issues for its use as tokamak armor material. Oxygen impurities in the SOL plasma may deteriorate the good…”
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    Journal Article
  17. 17

    Simulation of multi-atomic interactions in H–O–W system with the MD code CADAC by Landman, I.S.

    Published in Fusion engineering and design (01-11-2005)
    “…For future tokamak reactors, chemical erosion of tungsten armour surfaces under impact of hot deuterium–tritium plasma that contains impurities, for instance…”
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    Journal Article Conference Proceeding
  18. 18

    Tungsten erosion under plasma heat loads typical for ITER type I ELMs and disruptions by Garkusha, I.E., Bandura, A.N., Byrka, O.V., Chebotarev, V.V., Landman, I.S., Makhlaj, V.A., Marchenko, A.K., Solyakov, D.G., Tereshin, V.I., Trubchaninov, S.A., Tsarenko, A.V.

    Published in Journal of nuclear materials (01-03-2005)
    “…The behavior of pure sintered tungsten under repetitive plasma heat loads of ∼1MJ/m2 (which is relevant to ITER ELMs) and 25MJ/m2 (ITER disruptions) is studied…”
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    Journal Article
  19. 19

    Lateral deflection of the SOL plasma during a giant ELM by Landman, I.S., Wuerz, H.

    Published in Journal of nuclear materials (01-03-2001)
    “…In recent H-mode experiments at JET with giant ELMs a lateral deflection of hot tokamak plasma striking the divertor plate has been observed. This deflection…”
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    Journal Article
  20. 20

    Effect of hydrogen retention on tungsten erosion by oxygen by Landman, I.S., Würz, H.

    Published in Fusion engineering and design (01-09-2003)
    “…One important problem for future tokamak reactors with a tungsten divertor armor is chemical erosion. Impurities such as oxygen contained in the scrape-off…”
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    Journal Article Conference Proceeding