Search Results - "Tromm, W"

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  1. 1

    Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention by Khabensky, V.B., Granovsky, V.S., Almjashev, V.I., Vitol, S.A., Krushinov, E.V., Kotova, S.Ju, Sulatsky, A.A., Gusarov, V.V., Bechta, S.V., Barrachin, M., Bottomley, D., Fischer, M., Hellmann, S., Piluso, P., Miassoedov, A., Tromm, W.

    Published in Nuclear engineering and design (01-02-2018)
    “…•Simple equations for temperature gradients in liquid-solid systems are given.•The models are compared with data from METCOR, METCOR-P, MASCA projects.•A model…”
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    Journal Article
  2. 2

    Ranking of severe accident research priorities by Schwinges, B., Journeau, C., Haste, T., Meyer, L., Tromm, W., Trambauer, K.

    “…The objectives of the SARNET network are to define common research programmes in the field of severe accidents and to develop common computer tools and…”
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    Journal Article Conference Proceeding
  3. 3

    Oxidation kinetics of corium pool by Sulatsky, A.A., Smirnov, S.A., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Vitol, S.A., Kotova, S.Yu, Fischer, M., Hellmann, S., Tromm, W., Miassoedov, A., Bottomley, D., Piluso, P., Barrachin, M.

    Published in Nuclear engineering and design (01-09-2013)
    “…•The analysis of experimental data on molten corium oxidation was been carried out.•The analysis has revealed the main factors influencing the oxidation…”
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    Journal Article
  4. 4

    Phase diagram of the UO2–FeO1+x system by Bechta, S V, Krushinov, E V, Almjashev, V I, Vitol, S A, Mezentseva, L P, Petrov, Yu B, Lopukh, D B, Khabensky, V B, Barrachin, M, Hellmann, S, Froment, K, Fisher, M, Tromm, W, Bottomley, D, Defoort, F, Gusarov, V V

    Published in Journal of nuclear materials (15-05-2007)
    “…Phase-relation studies of the UO2-FeO1+x system in an inert atmosphere are presented. The eutectic point has been determined, which corresponds to a…”
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    Journal Article
  5. 5

    Phase diagram of the ZrO2–FeO system by Bechta, S.V., Krushinov, E.V., Almjashev, V.I., Vitol, S.A., Mezentseva, L.P., Petrov, Yu.B., Lopukh, D.B., Khabensky, V.B., Barrachin, M., Hellmann, S., Froment, K., Fischer, M., Tromm, W., Bottomley, D., Defoort, F., Gusarov, V.V.

    Published in Journal of nuclear materials (01-01-2006)
    “…The results on the ZrO2-FeO system studies in a neutral atmosphere are presented. The refined eutectic point has been found to correspond to a ZrO2…”
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    Journal Article
  6. 6

    VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere by Bechta, S.V., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Vitol, S.A., Sulatsky, A.A., Gusarov, V.V., Almiashev, V.I., Lopukh, D.B., Bottomley, D., Fischer, M., Piluso, P., Miassoedov, A., Tromm, W., Altstadt, E., Fichot, F., Kymalainen, O.

    Published in Nuclear engineering and design (01-06-2009)
    “…The long-term in-vessel corium retention (IVR) in the lower head bears a risk of the vessel wall deterioration caused by steel corrosion. The ISTC METCOR…”
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    Journal Article
  7. 7

    Corrosion of vessel steel during its interaction with molten corium by Bechta, S.V., Khabensky, V.B., Vitol, S.A., Krushinov, E.V., Granovsky, V.S., Lopukh, D.B., Gusarov, V.V., Martinov, A.P., Martinov, V.V., Fieg, G., Tromm, W., Bottomley, D., Tuomisto, H.

    Published in Nuclear engineering and design (01-09-2006)
    “…This paper is concerned with corrosion of a cooled vessel steel structure interacting with molten corium in air and neutral (nitrogen) atmospheres during an…”
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    Journal Article
  8. 8

    Corrosion of vessel steel during its interaction with molten corium by Bechta, S.V., Khabensky, V.B., Vitol, S.A., Krushinov, E.V., Granovsky, V.S., Lopukh, D.B., Gusarov, V.V., Martinov, A.P., Martinov, V.V., Fieg, G., Tromm, W., Bottomley, D., Tuomisto, H.

    Published in Nuclear engineering and design (01-07-2006)
    “…An experimental examination of the cooled vessel steel corrosion during the interaction with molten corium is presented. The experiments have been conducted on…”
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    Journal Article
  9. 9

    Corium spreading and coolability: CSC Project by Cognet, G, Alsmeyer, H, Tromm, W, Magallon, D, Wittmaack, R, Sehgal, B.R, Widmann, W, De Cecco, L, Ocelli, R, Azarian, G, Pineau, D, Spindler, B, Fieg, G, Werle, H, Journeau, C, Cranga, M, Laffont, G

    Published in Nuclear engineering and design (01-11-2001)
    “…In the context of severe accidents, large R&D efforts throughout the world are currently directed towards ex-vessel corium behaviour. Among the mitigation…”
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    Journal Article Conference Proceeding
  10. 10

    KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects by Sanchez-Espinoza, V.H., Gabrielli, F., Imke, U., Zhang, K., Mercatali, L., Huaccho, G., Duran, J., Campos, A., Stakhanova, A., Murat, O., Mercan, A.K., Etcheto, J., Steinbrück, M., Stuckert, J., Gabriel, S., Ottenburger, S., Stieglitz, R., Tromm, W.

    Published in Nuclear engineering and design (01-12-2023)
    “…•Unique computational routes for safety assessment and radiological risk estimation.•High-fidelity coupled tools based on Monte Carlo with static and dynamic…”
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    Journal Article
  11. 11

    Experiments for a core catcher concept based on water addition from below by Tromm, W., Alsmeyer, H.

    Published in Nuclear engineering and design (01-08-1995)
    “…A core catcher concept is proposed to be integrated into a new PWR design based on the standard German PWR. The core catcher achieves coolability by spreading…”
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    Journal Article
  12. 12

    Controlling and cooling core melts outside the pressure vessel by Alsmeyer, H, Albrecht, G, Fieg, G, Stegmaier, U, Tromm, W, Werle, H

    Published in Nuclear engineering and design (01-12-2000)
    “…For future reactors, the control and cooling of ex-vessel corium melts is under consideration to increase the passive safety features even for very unlikely…”
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    Journal Article
  13. 13

    Concept of a core cooling system and experiments performed by Alsmeyer, H., Tromm, W.

    Published in Nuclear engineering and design (1995)
    “…One of the problems which must be solved in severe accidents is the melt-concrete interaction which does occur when the core debris penetrates the lower…”
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    Journal Article
  14. 14

    BETA experiments on melt-concrete interaction: the role of zirconium and the potential sump water contact during core melt-down accidents by Alsmeyer, H., Adelhelm, C., Dillmann, H.-G., Foit, J.J., Heinle, M., Ratajczak, W., Schneider, H., Schumacher, G., Skokan, A., Stiefel, S., Tromm, W.

    Published in Nuclear engineering and design (01-02-1995)
    “…In the BETA test facility of Kernforschungszentrum Karlsruhe, prototypical core melts can be simulated in concrete structures sufficient in size to allow a…”
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    Journal Article
  15. 15

    Corrosion of vessel steel during its interaction with molten corium: Part 1. Experimental by Bechta, Sevostian, Khabensky, V.B., Vitol, S.A, Krushinov, E.V., Granovsky, V.S., Lopukh, D.B., Gusarov, V.V., Martinov, A.P., Fieg, G., Tromm, W., Bottomley, D., Tuomisto, H.

    Published in Nuclear engineering and design (01-09-2006)
    “…This paper is concerned with corrosion of a cooled vessel steel structure interacting with molten corium in air and neutral (nitrogen) atmospheresduring an…”
    Get full text
    Journal Article
  16. 16

    Corrosion of vessel steel during its interaction with molten corium: Part 2. Model development by Bechta, Sevostian, Khabensky, V.B., Vitol, S.A, Krushinov, E.V., Granovsky, V.S., Lopukh, D.B., Gusarov, V.V., Martinov, A.P., Fieg, G., Tromm, W., Bottomley, D., Tuomisto, H.

    Published in Nuclear engineering and design (01-07-2006)
    “…An experimental examination of the cooled vessel steel corrosion during the interaction with molten corium is presented. The experiments havebeen conducted on…”
    Get full text
    Journal Article
  17. 17

    Phase diagram of the UO 2–FeO 1+ x system by Bechta, S.V., Krushinov, E.V., Almjashev, V.I., Vitol, S.A., Mezentseva, L.P., Petrov, Yu.B., Lopukh, D.B., Khabensky, V.B., Barrachin, M., Hellmann, S., Froment, K., Fisher, M., Tromm, W., Bottomley, D., Defoort, F., Gusarov, V.V.

    Published in Journal of nuclear materials (2007)
    “…Phase-relation studies of the UO 2–FeO 1+ x system in an inert atmosphere are presented. The eutectic point has been determined, which corresponds to a…”
    Get full text
    Journal Article
  18. 18

    Phase diagram of the ZrO 2–FeO system by Bechta, S.V., Krushinov, E.V., Almjashev, V.I., Vitol, S.A., Mezentseva, L.P., Petrov, Yu.B., Lopukh, D.B., Khabensky, V.B., Barrachin, M., Hellmann, S., Froment, K., Fischer, M., Tromm, W., Bottomley, D., Defoort, F., Gusarov, V.V.

    Published in Journal of nuclear materials (2006)
    “…The results on the ZrO 2–FeO system studies in a neutral atmosphere are presented. The refined eutectic point has been found to correspond to a ZrO 2…”
    Get full text
    Journal Article
  19. 19
  20. 20

    Phase transformation in the binary section of the UO 2 -FeO-Fe system by Bechta, Sevostian, Krushinov, E.V., Almjashev, V.I., Vitol, S.A, Mezentseva, L.P., Petrov, Yu.B., Lopukh, D.B., Lomanova, N.A., Khabensky, V.B., Barrachin, M., Hellmann, S., Froment, K., Fischer, M., Tromm, W., Bottomley, D., Gusarov, V.V.

    Published in Radiochemistry (New York, N.Y.) (2007)
    “…Phase transformations in the oxide binary section of the UO 2 -FeO-Fe ternary system were studied. The melting onset point of the UO 2 -FeO heterogeneous…”
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    Journal Article