Author
Siegfried Malang
Other affiliations: University of California, Los Angeles
Bio: Siegfried Malang is an academic researcher from University of California, San Diego. The author has contributed to research in topics: Blanket & Divertor. The author has an hindex of 36, co-authored 122 publications receiving 3701 citations. Previous affiliations of Siegfried Malang include University of California, Los Angeles.
Topics: Blanket, Divertor, Coolant, Power station, Fusion power
Papers published on a yearly basis
Papers
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TL;DR: In this paper, the authors summarized the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identified the key R&D needs in non-fusion and fusion facilities on the path to DEMO.
234 citations
TL;DR: ARIES-RS as discussed by the authors is a conceptual design study which has examined the potential of an advanced tokamak-based power plant to compete with future energy sources and play a significant role in the future energy market.
143 citations
TL;DR: The ARIES-RS tokamak is a conceptual, D-T-burning 1000 MWe power plant as mentioned in this paper, which employs a reversed-shear plasma and employs a moderate aspect ratio (A40).
140 citations
TL;DR: The paper proposes a strategic conclusion derived from the review of blanket designs for advanced fusion reactors, which includes advanced ceramic breeder concepts, dual coolant blankets as well as self-cooled liquid metal and Flibe blankets.
140 citations
TL;DR: A modular He-cooled divertor concept with integrated pin array (HEMP) is being developed at the Forschungszentrum Karlsruhe to achieve a high heat flux of at least about 10–15 MW/m 2, proposed for a near-term reactor model like DEMO.
126 citations
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TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.
Abstract: The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.
1,187 citations
TL;DR: The progress in the ITER Physics Basis (PIPB) document as discussed by the authors is an update of the IPB, which was published in 1999 [1], and provides methodologies for projecting the performance of burning plasmas, developed largely through coordinated experimental, modelling and theoretical activities carried out on today's large tokamaks (ITER Physics R&D).
Abstract: The 'Progress in the ITER Physics Basis' (PIPB) document is an update of the 'ITER Physics Basis' (IPB), which was published in 1999 [1]. The IPB provided methodologies for projecting the performance of burning plasmas, developed largely through coordinated experimental, modelling and theoretical activities carried out on today's large tokamaks (ITER Physics R&D). In the IPB, projections for ITER (1998 Design) were also presented. The IPB also pointed out some outstanding issues. These issues have been addressed by the Participant Teams of ITER (the European Union, Japan, Russia and the USA), for which International Tokamak Physics Activities (ITPA) provided a forum of scientists, focusing on open issues pointed out in the IPB. The new methodologies of projection and control are applied to ITER, which was redesigned under revised technical objectives. These analyses suggest that the achievement of Q > 10 in the inductive operation is feasible. Further, improved confinement and beta observed with low shear (= high βp = 'hybrid') operation scenarios, if achieved in ITER, could provide attractive scenarios with high Q (> 10), long pulse (>1000 s) operation with beta
706 citations
Karlsruhe Institute of Technology1, University of Helsinki2, University of Oxford3, Max Planck Society4, École Polytechnique Fédérale de Lausanne5, University of Orléans6, Nuclear Research and Consultancy Group7, Academy of Sciences of the Czech Republic8, Warsaw University of Technology9, Technical University of Lisbon10, University of Navarra11, Plansee SE12, Royal Institute of Technology13, Charles III University of Madrid14, Energy Research Centre of the Netherlands15, Technical University of Madrid16, University of Leoben17, King Juan Carlos University18
TL;DR: In this article, the progress of work within the EFDA long-term fusion materials program in the area of tungsten alloys is reviewed, with a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.
599 citations
TL;DR: In this article, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination.
Abstract: Proposed fusion and advanced (Generation IV) fission energy systems require high-performance materials capable of satisfactory operation up to neutron damage levels approaching 200 atomic displacements per atom with large amounts of transmutant hydrogen and helium isotopes. After a brief overview of fusion reactor concepts and radiation effects phenomena in structural and functional (nonstructural) materials, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination. Environmental and safety considerations impose several additional restrictions on potential materials systems, but reduced-activation ferritic/martensitic steels (including thermomechanically treated and oxide dispersion–strengthened options) and silicon carbide ceramic composites emerge as robust structural...
505 citations
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.
494 citations