Search Results - "Neuberger, Heiko"
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Technological Processes for Steel Applications in Nuclear Fusion
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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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
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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Additive manufacturing technologies for EUROFER97 components
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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Microstructural features in additively manufactured EUROFER97 components
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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An enhanced, near-term HCPB design as driver blanket for the EU DEMO
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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Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program
Published in Fusion engineering and design (01-08-2020)“…•A consolidated design of the HCPB blanket has been achieved for the pre-Conceptual Design Phase of the EU DEMO.•While a fairly large TBR can be reached, the…”
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Overview of the HCPB Research Activities in EUROfusion
Published in IEEE transactions on plasma science (01-06-2018)“…In the framework of the EUROfusion's Power Plant Physics and Technology, the working package breeding blanket (BB) aims at investigating four different BB…”
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Thermal-hydraulic study on rib and dimple structures for cooling the First Wall of DEMO
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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A revised design approach of the attachment system for the ITER EU-HCPB-TBM based on a central cylindrical connection element
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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Evaluation of conservative and innovative manufacturing routes for gas cooled Test Blanket Module and Breeding Blanket First Walls
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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Advances in Additive Manufacturing of fusion materials
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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Status of the EU DEMO breeding blanket manufacturing R&D activities
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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Fabrication of HCPB breeding blanket components using the additive manufacturing processes of selective laser melting and cold spray
Published in Fusion engineering and design (01-11-2020)“…•This paper summarizes developments in Additive Manufacturing applied for fusion first walls.•Selective Laser Melting is intended to be followed for…”
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The European ITER test blanket modules: Progress in development of fabrication technologies towards standardization
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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Options for a high heat flux enabled helium cooled first wall for DEMO
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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Overview on ITER and DEMO blanket fabrication activities of the KIT INR and related frameworks
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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Experimental investigation on the possible techniques of pebbles packing for the HCPB Test Blanket Module
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
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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Options for a high heat flux enabled helium cooled first wall for DEMO
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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ITER Port Plug Engineering Trainee Program: Design, manufacturing and integration of structural components (analysis of the attachment)
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