Search Results - "Beneš, Ondřej"

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  1. 1

    Predicting material release during a nuclear reactor accident by Konings, Rudy J. M., Wiss, Thierry, Beneš, Ondřej

    Published in Nature materials (01-03-2015)
    “…In the aftermath of a nuclear reactor accident, understanding the release of fission products from the fuel is key…”
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    Journal Article
  2. 2

    The molten salt reactor (MSR) in generation IV: Overview and perspectives by Serp, Jérôme, Allibert, Michel, Beneš, Ondřej, Delpech, Sylvie, Feynberg, Olga, Ghetta, Véronique, Heuer, Daniel, Holcomb, David, Ignatiev, Victor, Kloosterman, Jan Leen, Luzzi, Lelio, Merle-Lucotte, Elsa, Uhlíř, Jan, Yoshioka, Ritsuo, Zhimin, Dai

    Published in Progress in nuclear energy (New series) (01-11-2014)
    “…Molten Salt Reactors (MSR) with the fuel dissolved in the liquid salt and fluoride-salt-cooled High-temperature Reactors (FHR) have many research themes in…”
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    Journal Article
  3. 3

    Isobaric Heat Capacity of Solid and Liquid Thorium Tetrafluoride by Tosolin, Alberto, Capelli, Elisa, Konings, Rudy, Luzzi, Lelio, Beneš, Ondřej

    Published in Journal of chemical and engineering data (12-09-2019)
    “…The isobaric heat capacity of solid and liquid thorium tetrafluoride was determined by two calorimetry methods: drop calorimetry to obtain the enthalpy…”
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    Journal Article
  4. 4

    Thermophysical Properties of FUNaK (NaF-KF-UF 4 ) Eutectics by Fache, Maxime, Voigt, Laura, Colle, Jean-Yves, Hald, John, Beneš, Ondřej

    Published in Materials (06-06-2024)
    “…General interest in the deployment of molten salt reactors (MSRs) is growing, while the available data on uranium-containing fuel salt candidates remains…”
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    Journal Article
  5. 5

    Prague Water Net Zero Strategy 2025: methodology and roadmap by Srb, Martin, Grešíková, Markéta, Salová, Nikola, Sýkora, Petr, Štrupl, Jiří, Xia, Roman, Huml, Ondřej, Prokop, Pavel, Hájková, Martina, Harasymchuk, Ivanna, Kočí, Vladimír, Beneš, Ondřej

    Published in Water science & technology. Water supply (01-05-2023)
    “…Abstract In 2019, Prague set out its Prague 2030 Climate Plan and Pražské vodovody a kanalizace, a.s., as the operator of drinking water supply and drainage…”
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    Journal Article
  6. 6

    On the fluorination of plutonium dioxide by ammonium hydrogen fluoride by Claux, Benoit, Beneš, Ondřej, Capelli, Elisa, Souček, Pavel, Meier, Roland

    Published in Journal of fluorine chemistry (01-03-2016)
    “…A method for synthesis of PuF3 from PuO2 by fluorination using NH4HF2 was investigated. PuO2 powder was added over a 4 times excess of NH4HF2 into a Ni…”
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    Journal Article
  7. 7

    Physico-chemical properties of the system (LiF-NaF)eut-LaF3 – Phase equilibria, density and volume properties, electrical conductivity and surface tension by Kubíková, Blanka, Mlynáriková, Jarmila, Beneš, Ondřej, Mikšíková, Eva, Priščák, Jozef, Tosolin, Alberto, Boča, Miroslav

    Published in Journal of molecular liquids (15-10-2018)
    “…A detailed physico-chemical investigation of molten system (LiF-NaF)eut-LaF3 up to 15 mol% of LaF3 has been done. The phase equilibria were measured by two…”
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    Journal Article
  8. 8

    Thermal Properties and Behaviour of Am-Bearing Fuel in European Space Radioisotope Power Systems by Watkinson, Emily Jane, Mesalam, Ramy, Vigier, Jean-François, Beneš, Ondřej, Griveau, Jean-Christophe, Colineau, Eric, Sierig, Mark, Freis, Daniel, Ambrosi, Richard M., Staicu, Dragos, Konings, Rudy J. M.

    Published in Thermo (01-12-2021)
    “…The European Space Agency is funding the research and development of 241Am-bearing oxide-fuelled radioisotope power systems (RPSs) including radioisotope…”
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    Journal Article
  9. 9

    High temperature heat capacity of PuPO4 monazite-analogue by BENES, Ondřej, POPA, Karin, REUSCHER, Vivien, ZAPPIA, Alessandro, STAICU, Dragos, KONINGS, Rudy J. M

    Published in Journal of nuclear materials (01-11-2011)
    “…The enthalpy increments of PuPO4 have been measured using drop calorimetry in the temperature range from 530 K to 1386 K. The heat capacity was derived from…”
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    Journal Article
  10. 10

    Experimental and Computational Exploration of the NaF–ThF4 Fuel System: Structure and Thermochemistry by Schreuder, Maarten B. J. W, Ocádiz Flores, Jaén A, Gheribi, Aimen E, Beneš, Ondrej, Griveau, Jean-Christophe, Colineau, Eric, Konings, Rudy J. M, Smith, Anna Louise

    Published in The journal of physical chemistry. B (05-08-2021)
    “…The structural, thermochemical, and thermophysical properties of the NaF–ThF4 fuel system were studied with experimental methods and molecular dynamics (MD)…”
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    Journal Article
  11. 11

    Synthesis of UF4 and ThF4 by HF gas fluorination and re-determination of the UF4 melting point by Souček, Pavel, Beneš, Ondřej, Claux, Benoit, Capelli, Elisa, Ougier, Michel, Tyrpekl, Václav, Vigier, Jean-Francois, Konings, Rudy J.M.

    Published in Journal of fluorine chemistry (01-08-2017)
    “…Pure UF4 and ThF4 were synthesised using HF gas fluorination of the respective oxides and characterised by X-ray diffraction and differential scanning…”
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    Journal Article
  12. 12

    Thermodynamic Assessment of the NaF-KF-UF4 System by Schacherl, Bianca, Eloirdi, Rachel, Konings, Rudy J. M., Beneš, Ondrej

    Published in Thermo (01-09-2021)
    “…In the Molten Salt Reactor (MSR) concept, metal fluorides are key components of possible fuel and coolant salts. The fast reactor option opens the possibility…”
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    Journal Article
  13. 13

    An original approach for Raman spectroscopy analysis of radioactive materials and its application to americium-containing samples by Naji, Mohamed, Colle, Jean-Yves, Beneš, Ondrej, Sierig, Mark, Rautio, Jouni, Lajarge, Patrick, Manara, Dario

    Published in Journal of Raman spectroscopy (01-09-2015)
    “…An approach for Raman measurements of highly radioactive samples is presented here. The innovative part of this approach lies in the fact that no single part…”
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    Journal Article
  14. 14
  15. 15

    Heat capacity of Bi2UO6 by Popa, Karin, Beneš, Ondrej, Raison, Philippe E., Griveau, Jean-Christophe, Pöml, Philipp, Colineau, Eric, Konings, Rudy J.M., Somers, Joseph

    Published in Journal of nuclear materials (01-10-2015)
    “…In the frame of the safety of lead–bismuth eutectic cooled fast reactors, the thermal behaviour of bismuth(III) uranate(VI) was studied as a possible…”
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    Journal Article
  16. 16

    Heat capacity, thermal expansion, and thermal diffusivity of NaUO2BO3 by Popa, Karin, Beneš, Ondrej, Staicu, Dragoş, Griveau, Jean-Christophe, Colineau, Eric, Seibert, Alice, Colle, Jean-Yves, Stohr, Sarah, Raison, Philippe E., Somers, Joseph, Konings, Rudy J. M.

    “…In the present studies, the thermal behaviour of NaUO 2 BO 3 has been investigated. This compound is a potential product of interaction between the coolant…”
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    Journal Article
  17. 17

    A mass spectrometric investigation of the vaporisation behaviour in the (U+Pu+O) system by Gotcu-Freis, Petronela, Colle, Jean-Yves, Hiernaut, Jean-Pol, Beneš, Ondrej, Guéneau, Christine, Konings, Rudy J.M.

    Published in The Journal of chemical thermodynamics (01-04-2014)
    “…•Vapour pressure measurements performed at high temperatures on (U,Pu) oxide samples.•Experimental facility consisted of a Knudsen cell coupled with a mass…”
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    Journal Article
  18. 18

    Thermodynamic data to model the interaction between coolant and fuel in gen IV sodium cooled fast reactors by Dinsdale, Alan, Gisby, John, Davies, Hugh, Konings, Rudy, Benes, Ondrej

    “…Understanding the behaviour of nuclear fuels in various environments is vital to the design and safe operation of nuclear reactors. While this is true if the…”
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    Conference Proceeding
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  20. 20

    Nuclear Reactor Fuels: Materials with Highly Complex Behaviour by Konings, Rudy J. M., Manara, Dario, Beneš, Ondrej, Guéneau, Christine

    Published in EPJ Web of conferences (01-01-2013)
    “…This lecture will principally focus on the high temperature characterisation of nuclear fuel materials, which is a challenging task. Nuclear fuels are highly…”
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    Journal Article