Search Results - "Leenaers, A."

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  1. 1

    Pore pressure estimation in irradiated UMo by Salvato, D., Leenaers, A., Van den Berghe, S., Detavernier, C.

    Published in Journal of nuclear materials (01-11-2018)
    “…Image analysis was performed on SEM micrographs of recently irradiated UMo dispersion fuel plates. Detailed information on the fission gas inter-granular…”
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  2. 2

    High burn-up structure of U(Mo) dispersion fuel by Leenaers, A., Van Renterghem, W., Van den Berghe, S.

    Published in Journal of nuclear materials (01-08-2016)
    “…The evolution of the high burn-up structure (HBS) in U(Mo) fuel irradiated up to a burn-up of ∼70% 235U or ∼5 × 1021 f/cm3 or ∼120 GWd/tHM is described and…”
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  3. 3

    Transmission electron microscopy investigation of irradiated U–7 wt%Mo dispersion fuel by Van den Berghe, S., Van Renterghem, W., Leenaers, A.

    Published in Journal of nuclear materials (30-04-2008)
    “…The microstructural evolution of atomised U–7 wt%Mo alloy fuel under irradiation was investigated by transmission electron microscopy on material from the…”
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  4. 4
  5. 5

    Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2 by Leenaers, A., Van den Berghe, S., Koonen, E., Kuzminov, V., Detavernier, C.

    Published in Journal of nuclear materials (01-03-2015)
    “…In the framework of the SELENIUM project two full size flat fuel plates were produced with respectively Si and ZrN coated U(Mo) particles and irradiated in the…”
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  6. 6

    The initial formation stages of a nanobubble lattice in neutron irradiated U(Mo) by Salvato, D., Leenaers, A., Van Renterghem, W., Van den Berghe, S., Detavernier, C., Evans, J.H.

    Published in Journal of nuclear materials (01-02-2020)
    “…Low burnup samples of U7wt%Mo with 10%, 15%, 20% and 25% 235U burnup were analysed by transmission electron microscopy in order to study the formation…”
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  7. 7

    Surface engineering of low enriched uranium–molybdenum by Leenaers, A., Van den Berghe, S., Detavernier, C.

    Published in Journal of nuclear materials (01-09-2013)
    “…Recent attempts to qualify the LEU(Mo) dispersion plate fuel with Si addition to the Al matrix up to high power and burn-up have not yet been successful due to…”
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  8. 8

    Aluminum cladding oxide growth prediction for high flux research reactors by Kim, Yeon Soo, Chae, H.T., Van den Berghe, S., Leenaers, A., Kuzminov, V., Yacout, A.M.

    Published in Journal of nuclear materials (01-02-2020)
    “…Aluminum cladding oxidation of research-reactor fuel elements at high power conditions has a disadvantageous effect on fuel performance due to the lower…”
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  9. 9

    U(Mo) grain refinement induced by irradiation with high energy iodine by Salvato, D., Shi, J., Breitkreutz, H., Van Renterghem, W., Baumeister, B., Schwarz, C., Leenaers, A., Van den Berghe, S., Detavernier, C., Petry, W.

    Published in Journal of nuclear materials (01-05-2021)
    “…Grain refinement in U(Mo) has been achieved out-of-pile by irradiating an U(Mo) foil with 80 MeV high-flux 127I ions at 140°C up to a high dose of ~ 2.1 × 1018…”
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  10. 10

    Microstructure and calorimetric analysis of the UMn binary system by Cea, A.K., Leenaers, A., Van den Berghe, S., Pardoen, T.

    Published in Journal of nuclear materials (01-02-2019)
    “…The microstructure, growth kinetics, and the high temperature phase equilibria of the UMn binary system are investigated using differential scanning…”
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  11. 11

    A modelling study of the inter-diffusion layer formation in U-Mo/Al dispersion fuel plates at high power by Ye, B., Hofman, G.L., Leenaers, A., Bergeron, A., Kuzminov, V., Van den Berghe, S., Kim, Y.S., Wallin, H.

    Published in Journal of nuclear materials (01-02-2018)
    “…Post irradiation examinations of full-size U-Mo/Al dispersion fuel plates fabricated with ZrN- or Si- coated U-Mo particles revealed that the reaction rate of…”
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  12. 12

    STEM-EDS/EELS and APT characterization of ZrN coatings on UMo fuel kernels by He, L., Bachhav, M., Keiser, D.D., Madden, J.W., Perez, E., Miller, B.D., Gan, J., Van Renterghem, W., Leenaers, A., Van den Berghe, S.

    Published in Journal of nuclear materials (01-12-2018)
    “…In the framework of the SELENIUM project, ZrN coated U-Mo fuel kernels were irradiated in the Belgium Reactor 2 of SCK•CEN to a plate average burnup of 48%…”
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  13. 13

    Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth by Iltis, X., Zacharie-Aubrun, I., Ryu, H.J., Park, J.M., Leenaers, A., Yacout, A.M., Keiser, D.D., Vanni, F., Stepnik, B., Blay, T., Tarisien, N., Tanguy, C., Palancher, H.

    Published in Journal of nuclear materials (01-11-2017)
    “…Significant progresses in the performances under in-pile irradiation of particular U-Mo based fuels have been observed over the last fifteen years. One of the…”
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  14. 14

    Microstructural evolution of U(Mo)–Al(Si) dispersion fuel under irradiation – Destructive analyses of the LEONIDAS E-FUTURE plates by Leenaers, A., Van den Berghe, S., Van Eyken, J., Koonen, E., Charollais, F., Lemoine, P., Calzavara, Y., Guyon, H., Jarousse, C., Geslin, D., Wachs, D., Keiser, D., Robinson, A., Hofman, G., Kim, Y.S.

    Published in Journal of nuclear materials (01-10-2013)
    “…Several irradiation experiments have confirmed the positive effect of adding Si to the matrix of an U(Mo) dispersion fuel plate on its in-pile irradiation…”
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  15. 15

    Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates by Van den Berghe, S., Parthoens, Y., Cornelis, G., Leenaers, A., Koonen, E., Kuzminov, V., Detavernier, C.

    Published in Journal of nuclear materials (01-11-2013)
    “…Extensive fuel-matrix interactions leading to plate pillowing have caused a severe impediment on the development of a suitable high density low-enriched…”
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  16. 16

    Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation by Ye, B., Miao, Y., Shi, J., Salvato, D., Mo, K., Jamison, L., Bergeron, A., Hofman, G.L., Leenaers, A., Oaks, A., Yacout, A.M., Van den Berghe, S., Petry, W., Kim, Y.S.

    Published in Journal of nuclear materials (01-02-2021)
    “…A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence of interdiffusion in bilayer Al-UMo samples under…”
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  17. 17

    Transmission electron microscopy investigation of neutron irradiated Si and ZrN coated UMo particles prepared using FIB by Van Renterghem, W., Miller, B.D., Leenaers, A., Van den Berghe, S., Gan, J., Madden, J.W., Keiser, D.D.

    Published in Journal of nuclear materials (01-01-2018)
    “…Two fuel plates, containing Si and ZrN coated U-Mo fuel particles dispersed in an Al matrix, were irradiated in the BR2 reactor of SCK•CEN to a burn-up of ∼70%…”
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  18. 18

    Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates by Van den Berghe, S., Parthoens, Y., Charollais, F., Kim, Y.S., Leenaers, A., Koonen, E., Kuzminov, V., Lemoine, P., Jarousse, C., Guyon, H., Wachs, D., Keiser Jr, D., Robinson, A., Stevens, J., Hofman, G.

    Published in Journal of nuclear materials (01-11-2012)
    “…In the framework of the elimination of High-Enriched Uranium (HEU) from the civil circuit, the search for an appropriate fuel to replace the high-enriched…”
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  19. 19

    3D reconstructions of irradiated U Mo fuel to understand breaching effects in ZrN diffusion barriers by Miller, B.D., Keiser, D.D., Abir, M., Aitkaliyeva, A., Leenaers, A., Hernandez, B.J., Van Renterghem, W., Winston, A.

    Published in Journal of nuclear materials (01-11-2018)
    “…To understand interaction layer behavior in U-Mo fuel kernels coated with physical vapor deposition (PVD) ZrN barriers, two cubes of irradiated fuel were…”
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  20. 20

    Heavy ion irradiation of UMo/Al samples PVD coated with Si and ZrN layers by Jungwirth, R., Zweifel, T., Chiang, H.-Y., Petry, W., Van den Berghe, S., Leenaers, A.

    Published in Journal of nuclear materials (01-03-2013)
    “…Excessive U-Al interdiffusion hampers the development of UMo/Al based disperse fuel since several years. As a remedy, addition of diffusion limiting elements…”
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