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Konys, Jürgen [Author]

Untersuchungen zur Korrosion des Vanadiums und der Legierung V 3Ti 1Si in strömendem Lithium

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Karlsruhe: Kernforschungszentrum, 1985
Konys, Jürgen [Author]

Untersuchungen zur Korrosion des Vanadiums und der Legierung V 3Ti 1Si in strömendem Lithium - [Als Ms. vervielfältigt]

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Karlsruhe: Kernforschungszentrum Karlsruhe, 1985 ; Online-Ausgabe, Karlsruhe: KIT-Bibliothek, 2007

Published in: Kernforschungszentrum Karlsruhe: Kernforschungszentrum Karlsruhe ; 4006
Schroer, Carsten [Author]; Konys, Jürgen [Author]

Physical chemistry of corrosion and oxygen control in liquid lead and lead-bismuth eutectic

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Karlsruhe: Forschungszentrum Karlsruhe, 2007

Published in: Forschungszentrum Karlsruhe: Wissenschaftliche Berichte des Forschungszentrums Karlsruhe ; 7364
Konys, Jürgen [Author]; Leistikow, Siegfried [Author]; Ehrlich, Karl [Author] ; Institut für Materialforschung Karlsruhe

Available metallurgical and process parameters/treatments for reduction of general corrosion/stress corrosion cracking for in- and ex-vessel application = Metallkundliche und prozessspezifische Maßnahmen bzw. Vorbehandlungen zur Reduzierung der allgemeinen sowie der Spannungsrisskorrosion von in-vessel und ex-vessel Anwendungen - [Als Manuskript gedruckt]

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Karlsruhe: Forschungszentrum Karlsruhe, Mai 2004

Published in: Forschungszentrum Karlsruhe: Wissenschaftliche Berichte des Forschungszentrums Karlsruhe ; 6973
Lorenz, Julia [Author]; Nold, Claudia [Author]; Konys, Jürgen [Author]

Systematische Untersuchungen zu den mechanischen Eigenschaften und dem Gefüge von Nickel-Dispersionsschichten mit eingelagerten AIN-Nanopartikeln

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Karlsruhe: Forschungszentrum Karlsruhe, 2008

Published in: Forschungszentrum Karlsruhe: Wissenschaftliche Berichte des Forschungszentrums Karlsruhe ; 741400
Stein-Fechner, Kathleen [Author]; Glasbrenner, Heike [Author]; Konys, Jürgen [Author]; Wedemeyer, Olaf [Author]

Development of a tritium permeation barrier on MANET II steel by hot dip aluminising and subsequent heat treatment

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Karlsruhe: KIT-Bibliothek, [2016]

Published in: Forschungszentrum Karlsruhe: Wissenschaftliche Berichte des Forschungszentrums Karlsruhe ; 5926
Glasbrenner, Heike [Author]; Stein-Fechner, Kathleen [Author]; Konys, Jürgen [Author]; Voß, Z. [Author]; Wedemeyer, Olaf [Author]

Development of a tritium permeation barrier on F82H-mod. sheets and on MANET tubes by hot dip aluminising and subsequent heat treatment

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Karlsruhe: KIT-Bibliothek, [2016]

Published in: Forschungszentrum Karlsruhe: Wissenschaftliche Berichte des Forschungszentrums Karlsruhe ; 6079
Borgstedt, Hans U.; Konys, Jürgen

The Influence of the Concentration of Nonmetals in Lithium on Reactions with the Alloy V-1 Si-3 Ti

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Informa UK Limited, 1998

Published in: Fusion Technology, 33 (1998) 1, Seite 68-73
Wulf, Sven-Erik; Krauss, Wolfgang; Konys, Jürgen

Long-term corrosion behavior of Al-based coatings in flowing Pb–15.7Li, produced by electrochemical ECX process

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Elsevier BV, 2018

Published in: Nuclear Materials and Energy, 16 (2018), Seite 158-162
Wulf, Sven-Erik; Krauss, Wolfgang; Konys, Jürgen

Corrosion resistance of Al-based coatings in flowing Pb–15.7Li produced by aluminum electrodeposition from ionic liquids

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Elsevier BV, 2016

Published in: Nuclear Materials and Energy, 9 (2016), Seite 519-523
Krauss, Wolfgang; Konys, Jürgen; Wulf, Sven-Erik

Corrosion barriers processed by Al electroplating and their resistance against flowing Pb–15.7Li

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Elsevier BV, 2014

Published in: Journal of Nuclear Materials, 455 (2014) 1-3, Seite 522-526
Tsisar, Valentyn; Yeliseyeva, Olga; Konys, Jürgen

Oxidation/dissolution of ferritic ODS steels in static lead with various oxygen content at 650 °C

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Elsevier BV, 2014

Published in: Nuclear Engineering and Design, 280 (2014), Seite 673-679
Holstein, Nils; Krauss, Wolfgang; Konys, Jürgen; Saverio Nitti, Francesco

New developments of hydrogen impurity online-monitoring in liquid lithium of IFMIF-DONES

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Elsevier BV, 2024

Published in: Nuclear Materials and Energy, 40 (2024), Seite 101697
Tsisar, Valentyn; Schroer, Carsten; Wedemeyer, Olaf; Skrypnik, Aleksandr; Konys, Jürgen

Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10−7 Mass % Dissolved Oxygen

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ASME International, 2019

Published in: Journal of Nuclear Engineering and Radiation Science, 5 (2019) 3
Tsisar, Valentyn; Schroer, Carsten; Wedemeyer, Olaf; Skrypnik, Aleksandr; Konys, Jürgen

Effect of Structural State and Surface Finishing on Corrosion Behavior of 1.4970 Austenitic Steel at 400 and 500 °C in Flowing Pb-Bi Eutectic With Dissolved Oxygen

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ASME International, 2018

Published in: Journal of Nuclear Engineering and Radiation Science, 4 (2018) 4
Tsisar, Valentyn; Schroer, Carsten; Wedemeyer, Olaf; Skrypnik, Aleksandr; Konys, Jürgen

Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550 °C with 10−7mass% dissolved oxygen

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Elsevier BV, 2014

Published in: Journal of Nuclear Materials, 454 (2014) 1-3, Seite 332-342
Yurechko, Mariya; Schroer, Carsten; Wedemeyer, Olaf; Skrypnik, Aleksandr; Konys, Jürgen

Creep-rupture tests on chromium-containing conventional and ODS steels in oxygen-controlled Pb and air at 650 °C

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Elsevier BV, 2014

Published in: Nuclear Engineering and Design, 280 (2014), Seite 686-696
Yurechko, Mariya; Schroer, Carsten; Skrypnik, Aleksandr; Wedemeyer, Olaf; Konys, Jürgen

Creep-to-rupture of 12Cr- and 14Cr-ODS steels in oxygen-controlled lead and air at 650°C

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Elsevier BV, 2014

Published in: Journal of Nuclear Materials, 450 (2014) 1-3, Seite 88-98
Schroer, Carsten; Wedemeyer, Olaf; Novotny, Josef; Skrypnik, Aleksandr; Konys, Jürgen

Performance of 9% Cr steels in flowing lead-bismuth eutectic at 450 and 550 °C, and 10−6mass% dissolved oxygen

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Elsevier BV, 2014

Published in: Nuclear Engineering and Design, 280 (2014), Seite 661-672
Yurechko, Mariya; Schroer, Carsten; Skrypnik, Aleksandr; Wedemeyer, Olaf; Konys, Jürgen

Creep-to-rupture of the steel P92 at 650°C in oxygen-controlled stagnant lead in comparison to air

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Elsevier BV, 2013

Published in: Journal of Nuclear Materials, 432 (2013) 1-3, Seite 78-86

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