Search Results - "Topilski, L."

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  1. 1

    Prevention of hydrogen and dust explosion in ITER by Chuyanov, V., Topilski, L.

    Published in Fusion engineering and design (01-02-2006)
    “…It is to be expected that, over time, an interaction of plasma with walls and the divertor will create in ITER hundreds of kilograms of beryllium, carbon or…”
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    Journal Article Conference Proceeding
  2. 2

    Fusion safety codes: international modeling with MELCOR and ATHENA–INTRA by Marshall, T, Porfiri, M.T, Topilski, L, Merrill, B

    Published in Fusion engineering and design (01-12-2002)
    “…For a number of years, the world fusion safety community has been involved in benchmarking their safety analyses codes against experiment data to support…”
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    Journal Article Conference Proceeding
  3. 3

    Validation and benchmarking in support of ITER-FEAT safety analysis by Topilski, L.N., Masson, X., Porfiri, M.T., Pinna, T., Sponton, L.-L., Andersen, J., Takase, K., Kurihara, R., Sardain, P., Girard, C.

    Published in Fusion engineering and design (01-04-2001)
    “…This paper briefly describes the codes used for International Thermonuclear Experimental Reactor (ITER) safety analysis, including some information on their…”
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    Journal Article Conference Proceeding
  4. 4

    Modelling of two-phase flow under accidental conditions fusion codes benchmark by Sardain, P, Girard, C, Andersson, J, Porfiri, M.T, Kurihara, R, Masson, X, Mignot, G, Pinna, T, Topilski, L

    Published in Fusion engineering and design (01-04-2001)
    “…The scope of this benchmark is to assess the capabilities of the best estimate thermal hydraulic codes to simulate the main physical phenomena occurring during…”
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    Journal Article Conference Proceeding
  5. 5

    Results of two-phase flow experiments with an integrated Ingress-of-Coolant Event (ICE) test facility for ITER safety by Takase, Kazuyuki, Akimoto, Hajime, Topilski, Leonid N.

    Published in Fusion engineering and design (01-04-2001)
    “…An integrated ICE (Ingress-of-Coolant Event) test facility was constructed in order to demonstrate the adequacy of the ITER (International Thermonuclear…”
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    Journal Article Conference Proceeding
  6. 6

    Lessons learned from the ITER safety approach for future fusion facilities by Gordon, C., Bartels, H.-W., Honda, T., Iseli, M., Raeder, J., Topilski, L., Moshonas, K., Taylor, N.

    Published in Fusion engineering and design (01-04-2001)
    “…Safety has been an integral part of the design process for the ITER project since the conceptual design activities of the project. The safety approach…”
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    Journal Article Conference Proceeding
  7. 7

    ITER inherent/passive ultimate safety margins by Piet, Steven J., Topilski, Leonid N., Bartels, Hans-Werner, Poucet, Andre E., Petti, David A.

    Published in Fusion Engineering and Design (03-09-1998)
    “…The self-limiting nature of the fusion reaction, modest mobilizable radioactive inventories, multiple confinement layers, and passive decay heat removal,…”
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    Journal Article Conference Proceeding
  8. 8

    ITER reference accidents by Bartels, H.-W., Poucet, A., Cambi, G., Gordon, C., Gaeta, M., Gulden, W., Honda, T., Iseli, M., Jahn, H., Koonce, J., Kveton, O., Merrill, B., Mitchell, N., Moore, R.L., Petti, D., Polkinghorne, S., Porfiri, M.T., Raeder, J., Saji, G., Stubbe, E., Piet, S.J., Topilski, L., Uckan, N., VanHove, W.

    Published in Fusion Engineering and Design (03-09-1998)
    “…Reference accidents are selected to envelope possible accident sequences to confirm the adequacy of ITER's safety design. Analyses of ITER reference accidents…”
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    Journal Article Conference Proceeding
  9. 9

    Source term and mobilization assessment in NSSR-1 of ITER by PIET, S. J, DI PACE, L, FEDERICI, G, HOLLAND, D. F, MCCARTHY, K. A, NISAN, S, ODA, Y, SEKI, Y, TOPILSKI, L. N

    Published in Journal of fusion energy (01-06-1997)
    “…We describe the radioactive sources in the International Thermonuclear Experimental Reactor (ITER). The most important sources are co-deposited tritium,…”
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    Conference Proceeding Journal Article
  10. 10

    Fusion specific features in ITER accident analysis by BARTELS, H.-W, GORDON, C. W, PIET, S. J, POUCET, A. E, SAJI, G, TOPILSKI, L. N

    Published in Journal of fusion energy (01-06-1997)
    “…Fusion specific features like inherent plasma shutdown, low decay heat densities, cryogenic temperatures, and limited source terms were considered during the…”
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    Conference Proceeding Journal Article
  11. 11

    Safety and Environmental Activities for ITER by Saji, G, Aymar, R, Bartels, H.-W, Gordon, C. W, Gulden, W, Holl, D. H, Iida, H, Inabe, T, Iseli, M, Kashirski, A. V, Kolbasov, B. N, Krivosheev, M, McCarthy, K. A, Marbach, G, Morozov, S. I, Natalizio, A, Petti, D. A, Piet, S. J, Poucet, A. E, Raeder, J, Seki, Y, Topilski, L. N

    Published in Journal of fusion energy (01-09-1997)
    “…This paper will summarize highlights of the safety approach and discuss the ITER EDA safety activities. The ITER safety approach is driven by three major…”
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    Journal Article
  12. 12

    Approaches to safety, environment and regulatory approval for ITER by Saji, G, Bartels, H.W, Chuyanov, V, Holland, D, Kashirski, A.V, Morozov, S.I, Piet, S.J, Poucet, A, Raeder, J, Rebut, P.H, Topilski, L.N

    Published in Fusion engineering and design (01-03-1995)
    “…International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities (EDA) in safety and environment are approaching the point where…”
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    Journal Article
  13. 13

    Safety related R&D for the ITER baseline design by Reyes, S., Taylor, N., Cortes, P., Ciattaglia, S., Rosanvallon, S., Perevezentsev, A., Iseli, M., Baker, D., Elbez-Uzan, J., Topilski, L., Gulden, W., Sharpe, P., Hayashi, T.

    “…This paper presents an overview of the safety related operating feedback taken into account in the ITER baseline design, and of the previously completed and…”
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    Conference Proceeding
  14. 14

    MELCOR ex-vessel LOCA simulations for ITER by Gaeta, M.J., Merrill, B.J., Bartels, H.-W., Topilski, L.

    “…Ex-vessel loss-of-coolant-accident (LOCA) simulations for the International Thermonuclear Experimental Reactor (ITER) were performed using the MELCOR code. The…”
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    Conference Proceeding
  15. 15