Search Results - "Neuberger, Heiko"

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  1. 1

    Technological Processes for Steel Applications in Nuclear Fusion by Rieth, Michael, Dürrschnabel, Michael, Bonk, Simon, Jäntsch, Ute, Bergfeldt, Thomas, Hoffmann, Jan, Antusch, Steffen, Simondon, Esther, Klimenkov, Michael, Bonnekoh, Carsten, Ghidersa, Bradut-Eugen, Neuberger, Heiko, Rey, Jörg, Zeile, Christian, Pintsuk, Gerald, Aiello, Giacomo

    Published in Applied sciences (01-12-2021)
    “…Plasma facing components for energy conversion in future nuclear fusion reactors require a broad variety of different fabrication processes. We present, along…”
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    Journal Article
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    Cold Spray metal powder deposition with 9 %Cr-steel applied for the HCPB First Wall fabrication: Proof of concept and options for ODS steel processing by Neuberger, Heiko, Hernandez, Francisco, Rieth, Michael, Bonnekoh, Carsten, Stratil, Ludek, Dlouhy, Ivo, Dymacek, Petr, Müller, Oliver, Adler, Lucas, Kunert, Ulrich

    Published in Nuclear materials and energy (01-06-2023)
    “…•Proof of concept for manufacturing process combining AM with Cold Spray metal powder deposition and diffusion welding.•Suitable for manufacturing of complex…”
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    Journal Article
  3. 3

    Additive manufacturing technologies for EUROFER97 components by Bonk, Simon, Neuberger, Heiko, Beckers, Daniel, Koch, Jonas, Antusch, Steffen, Rieth, Michael

    Published in Journal of nuclear materials (01-05-2021)
    “…By uncoupling the manufacturability from the design process, additive manufacturing of the baseline material EUROFER97 can open significant design freedom for…”
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    Journal Article
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    Microstructural features in additively manufactured EUROFER97 components by Bonk, Simon, Dürrschnabel, Michael, Neuberger, Heiko, Simondon, Esther, Rieth, Michael

    Published in Fusion engineering and design (01-12-2021)
    “…By uncoupling the manufacturability from the design process, additive manufacturing of RAFM steels like EUROFER97 can open significant design freedom for…”
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    Journal Article
  5. 5

    An enhanced, near-term HCPB design as driver blanket for the EU DEMO by Hernández, Francisco A., Pereslavtsev, Pavel, Zhou, Guangming, Neuberger, Heiko, Rey, Jorg, Kang, Qinlan, Boccaccini, Lorenzo V., Bubelis, Evaldas, Moscato, Ivo, Dongiovanni, Danilo

    Published in Fusion engineering and design (01-09-2019)
    “…The Helium Cooled Pebble Bed (HCPB) breeding blanket is a candidate as driver blanket for the EU DEMO. The reference design of the HCPB is based on a cooling…”
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    Journal Article
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    Thermal-hydraulic study on rib and dimple structures for cooling the First Wall of DEMO by Ruck, Sebastian, Arbeiter, Frederik, Brenneis, Björn, Hernandez, Francisco, Neuberger, Heiko, Schwab, Florian

    Published in Fusion engineering and design (01-09-2019)
    “…•Rib-structuring causes high heat transfer coefficients required for the helium cooled FW.•Semi-detaching the ribs increases the heat transfer and the cooling…”
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    Journal Article
  9. 9

    A revised design approach of the attachment system for the ITER EU-HCPB-TBM based on a central cylindrical connection element by Zeile, Christian, Neuberger, Heiko

    Published in Fusion engineering and design (01-08-2012)
    “…► Design of an attachment system based on a cylinder to connect TBM and shield. ► Attachment system has to cope with high EM loads and different thermal…”
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    Journal Article
  10. 10

    Evaluation of conservative and innovative manufacturing routes for gas cooled Test Blanket Module and Breeding Blanket First Walls by Neuberger, Heiko, Rey, Joerg, Arbeiter, Frederik, Hernandez, Francisco, Ruck, Sebastian, Koehly, Christina, Stratil, Ludek, Niewöhner, Reinhard, Felde, Alexander

    Published in Fusion engineering and design (01-09-2019)
    “…•Using Electrical Discharge Machining in combination with forming is an option to manufacture a U-shaped First Wall without welding.•Additive Manufacturing…”
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    Journal Article
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    Advances in Additive Manufacturing of fusion materials by Neuberger, Heiko, Hernandez, Francisco, Ruck, Sebastian, Arbeiter, Frederik, Bonk, Simon, Rieth, Michael, Stratil, Ludek, Müller, Oliver, Volker, Kai-Uwe

    Published in Fusion engineering and design (01-06-2021)
    “…Recent analysis result in significant impact on the design of the Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB). Especially the main demanding…”
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    Journal Article
  12. 12

    Status of the EU DEMO breeding blanket manufacturing R&D activities by Forest, Laurent, Aktaa, Jarir, Boccaccini, Lorenzo Virgilio, Emmerich, Thomas, Eugen-ghidersa, Bradut, Fondant, Gilles, Froio, Antonio, Puma, Antonella Li, Namburi, Hygreeva, Neuberger, Heiko, Rey, Jörg, Savoldi, Laura, Sornin, Denis, Vala, Ladislav

    Published in Fusion engineering and design (01-03-2020)
    “…The realization of a DEMOnstration Fusion Power Reactor (DEMO) to follow ITER, with the capability of generating several hundred MW of net electricity and…”
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    Journal Article
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    The European ITER test blanket modules: Progress in development of fabrication technologies towards standardization by Zmitko, Milan, Thomas, Noël, LiPuma, Antonella, Forest, Laurent, Cogneau, Laurence, Rey, Jörg, Neuberger, Heiko, Poitevin, Yves

    Published in Fusion engineering and design (01-11-2016)
    “…•Significant progress on the development of welding procedures for European TBM achieved.•Fabrication processes feasibility based on diffusion and fusion…”
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    Journal Article
  15. 15

    Options for a high heat flux enabled helium cooled first wall for DEMO by Arbeiter, Frederik, Chen, Yuming, Ghidersa, Bradut-Eugen, Klein, Christine, Neuberger, Heiko, Ruck, Sebastian, Schlindwein, Georg, Schwab, Florian, von der Weth, Axel

    Published in Fusion engineering and design (01-06-2017)
    “…•Design challenges for helium cooled first wall reviewed and otimization approaches explored.•Application of enhanced heat transfer surfaces to the First Wall…”
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    Journal Article
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    Overview on ITER and DEMO blanket fabrication activities of the KIT INR and related frameworks by Neuberger, Heiko, Rey, Joerg, von der Weth, Axel, Hernandez, Francisco, Martin, Tatiana, Zmitko, Milan, Felde, Alexander, Niewöhner, Reinhard, Krüger, Friedhelm

    Published in Fusion engineering and design (01-10-2015)
    “…•Recent achievements in fabricaition within different frameworks.•First Wall mockup with erosion technology.•Manufacturing of a HCPB TBM Cooling Plate Mockup…”
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    Journal Article
  17. 17

    Experimental investigation on the possible techniques of pebbles packing for the HCPB Test Blanket Module by Abou-Sena, Ali, Neuberger, Heiko, Ihli, Thomas

    Published in Fusion engineering and design (01-06-2009)
    “…The Helium Cooled Pebble Bed Test Blanket Module (TBM) features a structural box that consists of the first wall, two caps and a stiffening grid. Inside the…”
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    Journal Article Conference Proceeding
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    The European ITER Test Blanket Modules: Current status of fabrication technologies development and a way forward by Zmitko, Milan, Galabert, Jose, Thomas, Noël, Forest, Laurent, Bucci, Philippe, Cogneau, Laurence, Rey, Jörg, Neuberger, Heiko, Poitevin, Yves

    Published in Fusion engineering and design (01-10-2015)
    “…•Significant progress on development of welding procedures for European TBM achieved.•Fabrication processes feasibility based on diffusion and fusion welding…”
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    Journal Article
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    Options for a high heat flux enabled helium cooled first wall for DEMO by Arbeiter, Frederik, Chen, Yuming, Ghidersa, Bradut-Eugen, Klein, Christine, Neuberger, Heiko, Ruck, Sebastian, Schlindwein, Georg, Schwab, Florian, von der Weth, Axel

    Published in Fusion engineering and design (01-06-2017)
    “…Helium is considered as coolant in the plasma facing first wall of several blanket concepts for DEMO fusion reactors, due to the favorable properties of…”
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    Journal Article
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    ITER Port Plug Engineering Trainee Program: Design, manufacturing and integration of structural components (analysis of the attachment) by Zeile, Christian, Neuberger, Heiko, Dolensky, Bernhard

    Published in Fusion engineering and design (01-10-2011)
    “…The structural connection of helium cooled plasma facing components in ITER to the water cooled structural port plug shield requires an attachment system,…”
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    Journal Article Conference Proceeding