Search Results - "WISS, T"

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  1. 1

    Synthesis of Reactive Telechelic Polymers Based on Pentafluorophenyl Esters by Roth, Peter J, Wiss, Kerstin T, Zentel, Rudolf, Theato, Patrick

    Published in Macromolecules (25-11-2008)
    “…A diazo initiator and a chain transfer agent (CTA), both containing a pentafluorophenyl (PFP) activated ester, were synthesized. In a RAFT polymerization using…”
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  2. 2

    Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy by Marchetti, M., Laux, D., Fongaro, L., Wiss, T., Van Uffelen, P., Despaux, G., Rondinella, V.V.

    Published in Journal of nuclear materials (01-10-2017)
    “…Scanning acoustic microscopy is a non-destructive technique that allows determining the local material elastic properties by measuring the velocity of acoustic…”
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  3. 3

    Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour by Panetier, C., Pipon, Y., Gaillard, C., Moncoffre, N., Wiss, T., Mangin, D., Dieste, O., Marchand, B., Ducher, R., Dubourg, R., Epicier, T., Raimbault, L.

    Published in Journal of nuclear materials (01-01-2021)
    “…•SIMS and TEM techniques were combined to compare the thermal behaviour of Cs and Xe in UO2.•Both elements form bubbles with different growth kinetics.•At…”
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  4. 4

    Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant by Cognini, L., Pizzocri, D., Barani, T., Van Uffelen, P., Schubert, A., Wiss, T., Luzzi, L.

    Published in Nuclear engineering and design (15-12-2018)
    “…•Review of all the available experimental results for Henry’s constant of helium in oxide nuclear fuel.•Clustering of data based on microstructure of measured…”
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  5. 5

    Effect of molybdenum on the behaviour of caesium in uranium dioxide at high temperature by Panetier, C., Sarrasin, L., Gaillard, C., Pipon, Y., Wiss, T., Benedetti, A., Dieste, O., Mangin, D., Ducher, R., Dubourg, R., Moncoffre, N.

    Published in Journal of nuclear materials (01-03-2021)
    “…•The effect of a metallic fission product on Cs behaviour and its release in UO2 was investigated as a relevant aspect of fuel safety•Mo and Cs were…”
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  6. 6

    Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations by Luzzi, L., Cognini, L., Pizzocri, D., Barani, T., Pastore, G., Schubert, A., Wiss, T., Van Uffelen, P.

    Published in Nuclear engineering and design (15-04-2018)
    “…•Review of all the available experimental data of helium diffusivity in oxide nuclear fuel.•Clustering of the data based on the experimental technique used to…”
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  7. 7

    Melting behaviour of uranium-americium mixed oxides under different atmospheres by Epifano, E., Prieur, D., Martin, P.M., Guéneau, C., Dardenne, K., Rothe, J., Vitova, T., Dieste, O., Wiss, T., Konings, R.J.M., Manara, D.

    Published in The Journal of chemical thermodynamics (01-01-2020)
    “…•The very high melting temperatures of (U,Am)-oxides (T > 2500 K) were measured.•The effect of the oxidation on the melting behaviour was studied.•Extensive…”
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  8. 8

    Elastic properties of severely degraded fuels by Marchetti, M., Laux, D., Seibert, A., Bottomley, P.D., Wiss, T., Rondinella, V.V., Despaux, G.

    Published in Journal of nuclear materials (01-02-2020)
    “…The decommissioning of nuclear power plants subjected to a nuclear accident is a crucial activity for post-accident recovery and remediation of the affected…”
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  9. 9

    TEM analysis of irradiation-induced interaction layers in coated UMo/X/Al trilayer systems (X= Ti, Nb, Zr, and Mo) by Chiang, H.-Y., Wiss, T., Park, S.-H., Dieste-Blanco, O., Petry, W.

    Published in Journal of nuclear materials (01-02-2018)
    “…Uranium-molybdenum (UMo) alloy powder embedded in an Al matrix is considered as a promising candidate for fuel conversion of research reactors. A modified…”
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  10. 10

    High Frequency Acoustic Microscopy for the Determination of Porosity and Young's Modulus in High Burnup Uranium Dioxide Nuclear Fuel by Marchetti, Mara, Laux, Didier, Cappia, Fabiola, Laurie, M., Van Uffelen, P., Rondinella, V. V., Wiss, T., Despaux, G.

    Published in IEEE transactions on nuclear science (01-06-2016)
    “…During irradiation UO 2 nuclear fuel experiences the development of a non-uniform distribution of porosity which contributes to establish varying mechanical…”
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  11. 11

    Ring-Opening Polymerization and Copolymerization of Propylene Oxide Catalyzed by N-Heterocyclic Carbenes by Lindner, Ronald, Lejkowski, Michael L., Lavy, Séverine, Deglmann, Peter, Wiss, Kerstin T., Zarbakhsh, Sirus, Meyer, Lars, Limbach, Michael

    Published in ChemCatChem (01-02-2014)
    “…Herein, we demonstrate the application of adducts of various N‐heterocyclic carbenes (NHCs) with CO2 (i.e., NHC–CO2) as precatalysts in the ring‐opening…”
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  12. 12

    Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen by Hiernaut, J.-P., Wiss, T., Colle, J.-Y., Thiele, H., Walker, C.T., Goll, W., Konings, R.J.M.

    Published in Journal of nuclear materials (01-07-2008)
    “…A commercial PWR fuel sample with a local burn-up of about 240MWd/kgHM was annealed in a Knudsen cell mass spectrometer system with a heating rate of 10K/min…”
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  13. 13

    Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions by González-Robles, E., Metz, V., Wegen, D.H., Herm, M., Papaioannou, D., Bohnert, E., Gretter, R., Müller, N., Nasyrow, R., de Weerd, W., Wiss, T., Kienzler, B.

    Published in Journal of nuclear materials (01-10-2016)
    “…During reactor operation the fission gases Kr and Xe are formed within the UO2 matrix of nuclear fuel. Their quantification is important to evaluate their…”
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  14. 14

    Thermal diffusion of helium in 238Pu-doped UO2 by Talip, Z., Wiss, T., Di Marcello, V., Janssen, A., Colle, J.-Y., Van Uffelen, P., Raison, P., Konings, R.J.M.

    Published in Journal of nuclear materials (01-02-2014)
    “…UO2 samples doped with 0.1wt.% plutonium oxide have been investigated with the aim to study alpha-damage effects and the behaviour of radiogenic helium in…”
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  15. 15

    Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy by Wiss, T., Thiele, H., Janssen, A., Papaioannou, D., Rondinella, V. V., Konings, R. J. M.

    Published in JOM (1989) (01-12-2012)
    “…Recent electron microscopy investigations are presented with an emphasis on properties related to the safe extended operation of nuclear fuel. In particular,…”
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  16. 16

    TEM-EELS analyses of protactinium by O Dieste, T Wiss, J-C Griveau, R J M Konings, G van der Laan, R Caciuffo

    Published in Materials research express (01-02-2019)
    “…A fragment of metallic protactinium (Pa) has been studied using a transmission electron microscope (TEM) equipped with an electron energy loss spectroscopy…”
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  17. 17

    Impact of auto-irradiation on the thermophysical properties of oxide nuclear reactor fuels by Staicu, D., Wiss, T., Rondinella, V.V., Hiernaut, J.P., Konings, R.J.M., Ronchi, C.

    Published in Journal of nuclear materials (01-02-2010)
    “…The effect of α-damage on the thermophysical properties of UO 2 was investigated using samples doped with 238Pu. Characterisations were performed after…”
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  18. 18

    The mechanism of the hydrothermal alteration of cerium- and plutonium-doped zirconolite by Pöml, P., Geisler, T., Cobos-Sabaté, J., Wiss, T., Raison, P.E., Schmid-Beurmann, P., Deschanels, X., Jégou, C., Heimink, J., Putnis, A.

    Published in Journal of nuclear materials (01-03-2011)
    “…A comprehensive study on the aqueous stability of Ce- and Pu-doped zirconolite has been performed. Four series of hydrothermal experiments were carried out…”
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  19. 19

    Fission product release and microstructure changes of irradiated MOX fuel at high temperatures by Colle, J.-Y., Hiernaut, J.-P., Wiss, T., Beneš, O., Thiele, H., Papaioannou, D., Rondinella, V.V., Sasahara, A., Sonoda, T., Konings, R.J.M.

    Published in Journal of nuclear materials (01-11-2013)
    “…Samples of irradiated MOX fuel of 44.5GWd/tHM mean burn-up were prepared by core drilling at three different radial positions of a fuel pellet. They were…”
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  20. 20

    Uranium secondary phase formation during anoxic hydrothermal leaching processes of UO2 nuclear fuel by Amme, M., Wiss, T., Thiele, H., Boulet, P., Lang, H.

    Published in Journal of nuclear materials (15-05-2005)
    “…Mobilisation of uranium in geologic environments from UO2 solid phases usually takes place by oxidative dissolution involving a change of U oxidation state…”
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