N. Bekris

ORCID: 0000-0003-3621-9082
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Magnetic confinement fusion research
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Superconducting Materials and Applications
  • Muon and positron interactions and applications
  • Nuclear Physics and Applications
  • Ion-surface interactions and analysis
  • Nuclear materials and radiation effects
  • Diamond and Carbon-based Materials Research
  • Particle accelerators and beam dynamics
  • Laser-Plasma Interactions and Diagnostics
  • Plasma Diagnostics and Applications
  • Magneto-Optical Properties and Applications
  • Radioactive contamination and transfer
  • Semiconductor materials and devices
  • Nuclear and radioactivity studies
  • Seismic Waves and Analysis
  • Radiation Effects in Electronics
  • Graphite, nuclear technology, radiation studies
  • Hydrogen Storage and Materials
  • Radiation Detection and Scintillator Technologies
  • Neural Networks and Reservoir Computing
  • Thin-Film Transistor Technologies
  • Chemical Synthesis and Characterization

Culham Science Centre
2013-2024

Karlsruhe Institute of Technology
2012-2024

Culham Centre for Fusion Energy
2014-2024

Royal Military Academy
2020

FZI Research Center for Information Technology
2000-2009

University of Toronto
2008

KTH Royal Institute of Technology
2007

Abstract The JET 2019–2020 scientific and technological programme exploited the results of years concerted engineering work, including ITER-like wall (ILW: Be W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power 2019–2020, tested technical procedural preparation for safe operation with tritium. Research along three complementary axes yielded wealth new results. Firstly, plasma delivered scenarios...

10.1088/1741-4326/ac47b4 article EN cc-by Nuclear Fusion 2022-01-04

Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...

10.1088/1741-4326/ad3e16 article EN cc-by Nuclear Fusion 2024-04-12

The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...

10.1088/1741-4326/aa5e28 article EN cc-by Nuclear Fusion 2017-06-15

Management of tritium inventory remains one the grand challenges in development fusion energy, and choice plasma-facing materials is a key factor for in-vessel retention. The Atomic Molecular Data Unit International Energy Agency organized Coordinated Research Project (CRP) on overall topic reactors during period 2001-2006. This dealt with hydrogenic retention ITER's – Be, C, W compounds (mixed materials) these elements as well removal techniques. results CRP are summarized this paper...

10.13182/fst54-891 article EN Fusion Science & Technology 2008-11-01

Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...

10.1088/1741-4326/ab2276 article EN cc-by Nuclear Fusion 2019-05-17

The objective of thermonuclear fusion consists producing electricity from the coalescence light nuclei in high temperature plasmas. most promising route to envisages confinement such plasmas with magnetic fields, whose studied configuration is tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one main potential showstoppers on a commercial reactor. In this work we report how, deploying innovative analysis methods thousands JET experiments covering isotopic...

10.1038/s41467-024-46242-7 article EN cc-by Nature Communications 2024-03-18

Among the various getter materials interalloy ZrCo has been selected by ITER team as reference material for storage of hydrogen isotopes at tritium plant because its excellent properties, which are comparable to those uranium. Only certain conditions, such presence high partial pressure H2 relatively low temperatures (350°C 400°C), or during repeated absorption-desorption heat cycles, have a matter concern, under these conditions can lose gettering properties. Indeed, repetitive...

10.13182/fst12-a14111 article EN Fusion Science & Technology 2012-08-01

The first divertor was installed in the JET machine between 1992 and 1994 operated with carbon tiles then beryllium 1994–5. Post-mortem studies after these experiments demonstrated that most of impurities deposited originate main chamber, asymmetric deposition patterns generally favouring inner region result from drift scrape-off layer. A new monolithic structure 1996 which produced heavy at shadowed areas corner, is where majority tritium trapped by co-deposition during deuterium-tritium...

10.1016/j.fusengdes.2018.10.002 article EN cc-by-nc-nd Fusion Engineering and Design 2018-11-18
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