Author
L. Giancarli
Bio: L. Giancarli is an academic researcher from ITER. The author has contributed to research in topics: Blanket & Divertor. The author has an hindex of 28, co-authored 99 publications receiving 3068 citations.
Topics: Blanket, Divertor, European union, Coolant, Fusion power
Papers published on a yearly basis
Papers
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TL;DR: In this article, the authors have made advances in understanding radiation damage in SiC at the fundamental level through MD simulations of displacement cascades and showed that SiC composites made with the advanced fibers of Nicalon Type S and the UBE Tyranno SA have excellent thermal conductivity and radiation stability.
198 citations
TL;DR: The main features of the six TBSs that are presently planned for installation and operation in ITER, the main interfaces with other ITER systems and the main aspects of the TBM Program management are described.
198 citations
TL;DR: The SiCf/SiC composite is a promising structural material candidate for fusion power cores and has been considered internationally in several power plant studies as discussed by the authors, but its behavior and performance at high temperatures and under irradiation are still not well known and need to be better characterized.
192 citations
TL;DR: SiCf/SiC composites are among the most promising candidate structural materials for fusion because of their potential application for high performance reactors and superior safety characteristics compared to metallic materials as mentioned in this paper.
184 citations
TL;DR: The ITER plasma-facing components directly face the thermonuclear plasma and include the divertor, the blanket and the test blanket modules with their corresponding frames as discussed by the authors, which provides a physical boundary for the plasma transients and contributes to the thermal and nuclear shielding of the vacuum vessel and external machine components.
149 citations
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TL;DR: In this paper, a sedimentological core and petrographic characterisation of samples from eleven boreholes from the Lower Carboniferous of Bowland Basin (Northwest England) is presented.
Abstract: Deposits of clastic carbonate-dominated (calciclastic) sedimentary slope systems in the rock record have been identified mostly as linearly-consistent carbonate apron deposits, even though most ancient clastic carbonate slope deposits fit the submarine fan systems better. Calciclastic submarine fans are consequently rarely described and are poorly understood. Subsequently, very little is known especially in mud-dominated calciclastic submarine fan systems. Presented in this study are a sedimentological core and petrographic characterisation of samples from eleven boreholes from the Lower Carboniferous of Bowland Basin (Northwest England) that reveals a >250 m thick calciturbidite complex deposited in a calciclastic submarine fan setting. Seven facies are recognised from core and thin section characterisation and are grouped into three carbonate turbidite sequences. They include: 1) Calciturbidites, comprising mostly of highto low-density, wavy-laminated bioclast-rich facies; 2) low-density densite mudstones which are characterised by planar laminated and unlaminated muddominated facies; and 3) Calcidebrites which are muddy or hyper-concentrated debrisflow deposits occurring as poorly-sorted, chaotic, mud-supported floatstones. These
9,929 citations
TL;DR: SiC-based ceramic matrix composites, consisting of carbon or SiC fibers embedded in a SiC-matrix, are tough ceramics when the fiber/matrix bonding is properly optimized through the use of a thin interphase.
1,358 citations
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: In this article, a strategy for designing high-performance radiation-resistant materials is based on the introduction of a high, uniform density of nanoscale particles that simultaneously provide good high temperature strength and neutron radiation damage resistance.
844 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