Search Results - "GLATZ, J. P"

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  1. 1

    Demonstration of a SANEX Process in Centrifugal Contactors using the CyMe4-BTBP Molecule on a Genuine Fuel Solution by Magnusson, D., Christiansen, B., Foreman, M. R. S., Geist, A., Glatz, J.-P., Malmbeck, R., Modolo, G., Serrano-Purroy, D., Sorel, C.

    Published in Solvent extraction and ion exchange (01-03-2009)
    “…Efficient recovery of minor actinides from a genuine spent fuel solution has been successfully demonstrated by the CyMe 4 -BTBP/DMDOHEMA extractant mixture…”
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    Journal Article
  2. 2

    Electrorefining of irradiated experimental metallic fuel at high lanthanides concentration in the LiCl–KCl electrolyte by Souček, P., Uruga, K., Murakami, T., Rodrigues, A., Van Winckel, S., Iizuka, M., Glatz, J.-P.

    Published in Journal of nuclear materials (01-12-2019)
    “…An electrorefining process for homogeneous group-selective recovery of actinides from metallic nuclear fuel in molten LiCl–KCl has been investigated. The…”
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    Journal Article
  3. 3

    On the electrochemical formation of Pu–Al alloys in molten LiCl–KCl by Mendes, E., Malmbeck, R., Nourry, C., Souček, P., Glatz, J.-P.

    Published in Journal of nuclear materials (2012)
    “…► Pu–Al alloys formation in a molten LiCl–KCl eutectic. ► Electrochemical reduction of Pu 3+ on Al and inert W cathodes from 400 °C to 550 °C. ► Pu reduction…”
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    Journal Article
  4. 4

    On the formation of U–Al alloys in the molten LiCl–KCl eutectic by Cassayre, L., Caravaca, C., Jardin, R., Malmbeck, R., Masset, P., Mendes, E., Serp, J., Soucek, P., Glatz, J.-P.

    Published in Journal of nuclear materials (15-08-2008)
    “…U–Al alloy formation has been studied in the temperature range of 400–550 °C by electrochemical techniques in the molten LiCl–KCl eutectic. Cyclic voltammetry…”
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    Journal Article
  5. 5

    Separation of actinides from irradiated An–Zr based fuel by electrorefining on solid aluminium cathodes in molten LiCl–KCl by Souček, P., Murakami, T., Claux, B., Meier, R., Malmbeck, R., Tsukada, T., Glatz, J.-P.

    Published in Journal of nuclear materials (01-04-2015)
    “…•Electrorefining process in molten LiCl-KCl using solid Al electrodes was demonstrated.•High separation factors of actinides over lanthanides were…”
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    Journal Article
  6. 6

    Electrochemistry of uranium in molten LiF–CaF2 by Nourry, C., Souček, P., Massot, L., Malmbeck, R., Chamelot, P., Glatz, J.-P.

    Published in Journal of nuclear materials (01-11-2012)
    “…This article is focused on the electrochemical behaviour of U ions in molten LiF–CaF2 (79–21wt.%) eutectic. On a W electrode, U(III) is reduced in one step to…”
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    Journal Article
  7. 7

    Electrochemical reduction of CerMet fuels for transmutation using surrogate CeO2-Mo pellets by Claux, B., Souček, P., Malmbeck, R., Rodrigues, A., Glatz, J.-P.

    Published in Journal of nuclear materials (01-08-2017)
    “…One of the concepts chosen for the transmutation of minor actinides in Accelerator Driven Systems or fast reactors proposes the use of fuels and targets…”
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    Journal Article
  8. 8

    Actinides recovery from irradiated metallic fuel in LiCl–KCl melts by Murakami, T., Rodrigues, A., Ougier, M., Iizuka, M., Tsukada, T., Glatz, J.-P.

    Published in Journal of nuclear materials (01-11-2015)
    “…Electrorefining of irradiated metallic fuels was successfully demonstrated: Actinides (U, Pu, Np, Am and Cm) in the fuels were dissolved in LiCl–KCl melts with…”
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    Journal Article
  9. 9

    Anodic dissolution of irradiated metallic fuels in LiCl–KCl melt by Murakami, T., Kato, T., Rodrigues, A., Ougier, M., Iizuka, M., Koyama, T., Glatz, J.-P.

    Published in Journal of nuclear materials (01-09-2014)
    “…Electrorefining is the main step in pyro-process of spent nuclear fuels, where actinides are recovered and separated from fission products. In the present…”
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    Journal Article
  10. 10

    Electrochemistry of thorium in LiCl–KCl eutectic melts by Cassayre, L., Serp, J., Soucek, P., Malmbeck, R., Rebizant, J., Glatz, J.-P.

    Published in Electrochimica acta (30-09-2007)
    “…This work presents a study of the electrochemical properties of Th chloride ions dissolved in a molten LiCl–KCl eutectic, in a temperature range of 693–823 K…”
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    Journal Article
  11. 11

    Study of thermodynamic properties of Np–Al alloys in molten LiCl–KCl eutectic by Souček, P., Malmbeck, R., Mendes, E., Nourry, C., Sedmidubský, D., Glatz, J.-P.

    Published in Journal of nuclear materials (01-10-2009)
    “…Pyrochemical methods are investigated worldwide within the framework of Partitioning and Transmutation concepts for spent nuclear fuel reprocessing…”
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    Journal Article
  12. 12

    Electrochemical behaviour of americium ions in LiCl–KCl eutectic melt by Serp, J., Chamelot, P., Fourcaudot, S., Konings, R.J.M., Malmbeck, R., Pernel, C., Poignet, J.C., Rebizant, J., Glatz, J.-P.

    Published in Electrochimica acta (20-05-2006)
    “…This work presents a study on the electrochemical properties of AmCl 3 in a molten LiCl–KCl eutectic, at a temperature range of 733–833 K. Transient…”
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    Journal Article
  13. 13

    Zirconium behaviour during electrorefining of actinide-zirconium alloy in molten LiCl-KCl on aluminium cathodes by Meier, R., Souček, P., Malmbeck, R., Krachler, M., Rodrigues, A., Claux, B., Glatz, J.-P., Fanghänel, Th

    Published in Journal of nuclear materials (15-04-2016)
    “…A pyrochemical electrorefining process for the recovery of actinides from metallic nuclear fuel based on actinide-zirconium alloys (An–Zr) in a molten salt is…”
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    Journal Article
  14. 14

    Investigation of electrorefining of metallic alloy fuel onto solid Al cathodes by Cassayre, L., Malmbeck, R., Masset, P., Rebizant, J., Serp, J., Soucek, P., Glatz, J.-P.

    Published in Journal of nuclear materials (15-01-2007)
    “…This work concerned the electrorefining of UZr and UPuZr alloys on a solid aluminium cathode, in the LiCl–KCl eutectic melt containing U3+, Pu3+, Np3+, Zr2+ or…”
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    Journal Article Conference Proceeding
  15. 15

    Recovery of actinides from actinide–aluminium alloys by chlorination: Part II by Souček, P., Cassayre, L., Eloirdi, R., Malmbeck, R., Meier, R., Nourry, C., Claux, B., Glatz, J.-P.

    Published in Journal of nuclear materials (01-04-2014)
    “…A chlorination route is being investigated for recovery of actinides from actinide–aluminium alloys, which originate from pyrochemical recovery of actinides…”
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    Journal Article
  16. 16

    Recovery of actinides from actinide–aluminium alloys by chlorination: Part I by Cassayre, L., Souček, P., Mendes, E., Malmbeck, R., Nourry, C., Eloirdi, R., Glatz, J.-P.

    Published in Journal of nuclear materials (01-07-2011)
    “…Pyrochemical processes in molten LiCl–KCl are being developed in ITU for recovery of actinides from spent nuclear fuel. The fuel is anodically dissolved to the…”
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    Journal Article
  17. 17

    Exhaustive electrolysis for recovery of actinides from molten LiCl–KCl using solid aluminium cathodes by Souček, P., Malmbeck, R., Mendes, E., Nourry, C., Glatz, J.-P.

    “…An electrorefining process in molten chloride salts using solid aluminium cathodes is being developed in Institute for Transuranium Elements in order to…”
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    Journal Article
  18. 18

    Separation of plutonium from lanthanum by electrolysis in LiCl–KCl onto molten bismuth electrode by Serp, J., Lefebvre, P., Malmbeck, R., Rebizant, J., Vallet, P., Glatz, J.-P.

    Published in Journal of nuclear materials (15-04-2005)
    “…This work presents a study on the electroseparation of plutonium from lanthanum using molten bismuth electrodes in LiCl–KCl eutectic at 733K. The reduction…”
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    Journal Article
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    Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition by Serrano-Purroy, D., Clarens, F., González-Robles, E., Glatz, J.P., Wegen, D.H., de Pablo, J., Casas, I., Giménez, J., Martínez-Esparza, A.

    Published in Journal of nuclear materials (01-08-2012)
    “…Two weak points in Performance Assessment (PA) exercises regarding the alteration of Spent Nuclear Fuel (SNF) are the contribution of the so-called Instant…”
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    Journal Article