Ph. Mertens

ORCID: 0000-0002-5010-5316
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About
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Laser-induced spectroscopy and plasma
  • Atomic and Molecular Physics
  • Nuclear Materials and Properties
  • Plasma Diagnostics and Applications
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Ion-surface interactions and analysis
  • Particle accelerators and beam dynamics
  • Ionosphere and magnetosphere dynamics
  • Metal and Thin Film Mechanics
  • Laser Design and Applications
  • Advanced materials and composites
  • Diamond and Carbon-based Materials Research
  • Mass Spectrometry Techniques and Applications
  • Solid State Laser Technologies
  • High-pressure geophysics and materials
  • Electromagnetic Launch and Propulsion Technology
  • Metallurgical Processes and Thermodynamics
  • Spacecraft and Cryogenic Technologies
  • X-ray Spectroscopy and Fluorescence Analysis
  • Surface Roughness and Optical Measurements

Forschungszentrum Jülich
2013-2022

Culham Science Centre
2006-2014

Max Planck Institute for Plasma Physics
2014

Stadtwerke Jülich (Germany)
2013

Czech Academy of Sciences
2013

United Kingdom Atomic Energy Authority
2010

Culham Centre for Fusion Energy
2010

KTH Royal Institute of Technology
2007-2009

Lawrence Livermore National Laboratory
2007

Imperial College London
2005

Work is in progress to completely replace, 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent ITER design. The ITER-like wall (ILW) will be created combination beryllium (Be), tungsten (W), W-coated and Be-coated inconel tiles, material depending on local anticipated heat flux geometry. It part an integrated package enhancements whose aim develop understanding issues techniques required operate inductive advanced scenarios as close possible...

10.1088/0031-8949/2007/t128/027 article EN Physica Scripta 2007-03-01

The original goals of the JET ITER-like wall included study impact an all W divertor on plasma operation (Coenen et al 2013 Nucl. Fusion 53 073043) and fuel retention (Brezinsek 083023). ITER has recently decided to install a full-tungsten (W) from start operations. One key inputs required in support this decision was possibility melting melt splashing during transients. Damage type can lead modifications surface topology which could higher disruption frequency or compromise subsequent...

10.1088/0029-5515/55/2/023010 article EN Nuclear Fusion 2015-01-21

Cracking thresholds and crack patterns in tungsten targets after repetitive ITER-like edge localized mode (ELM) pulses have been studied recent simulation experiments by laser irradiation. The specimens were tested under selected conditions to quantify the thermal shock response. A Nd:YAG capable of delivering up 32 J energy per pulse with a duration 1 ms at fundamental wavelength λ = 1064 nm has used irradiate ITER-grade samples heat loads. exposures performed for room temperature (RT) as...

10.1088/0031-8949/2014/t159/014005 article EN Physica Scripta 2014-04-01

10.1016/j.fusengdes.2010.04.048 article EN Fusion Engineering and Design 2010-06-03

To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER's plasma facing materials, namely, Be the main wall W in divertor. In addition, protection systems, diagnostics, vertical stability control were upgraded heating capability of neutral beams was increased to over 30 MW. First results confirm expected benefits limitations all metal components (PFCs) but also yield understanding...

10.1063/1.4804411 article EN Physics of Plasmas 2013-05-01

Mirrors will be used as first plasma-viewing elements in optical and laser-based diagnostics ITER. Deterioration of the mirror performance due to e.g. sputtering surface by plasma particles or deposition impurities hamper entire affected diagnostic thus affect ITER operation. The Specialists Working Group on First (FM SWG) Topical Diagnostics International Tokamak Physics Activity (ITPA) plays an important role finding solutions for mirrors.

10.1088/1741-4326/ab1446 article EN Nuclear Fusion 2019-03-28

In the TEXTOR tokamak, experiments were performed to simultaneously determine molecular, atomic and total particle flux of deuterium in front a graphite limiter, temperature which can be controlled independently plasma conditions. With rising limiter temperatures, TTL, but constant conditions an increase Balmer emission decrease Fulcher-band observed. This variation is associated with change type released species: molecules dominate at low temperatures (550 K < TTL 1100 K), whereas ≥ direct...

10.1088/0741-3335/47/4/003 article EN Plasma Physics and Controlled Fusion 2005-03-05

The first results of the Dynamic Ergodic Divertor in TEXTOR, when operating m/n=3/1 mode configuration, are presented. deeply penetrating external magnetic field perturbation this configuration increases toroidal plasma rotation. Staying below excitation threshold for m/n=2/1 tearing mode, rotation is always direction current, even if projection rotating opposite direction. observed consistent with a radial electric field, generated by an enhanced electron transport ergodic layers near...

10.1103/physrevlett.94.015003 article EN Physical Review Letters 2005-01-07

A new endoscope with optimised divertor view has been developed in order to survey and monitor the emission of specific impurities such as tungsten remaining carbon well beryllium JET after implementation ITER-like wall 2011. The is a prototype for testing an ITER relevant design concept based on reflective optics only. It may be subject high neutron fluxes expected ITER. operating wavelength range, from 390 nm 2500 nm, allows measurements all (W I, Be II, C III) optical transmittance (≥30%...

10.1063/1.4731759 article EN Review of Scientific Instruments 2012-07-11

The radiative improved (RI) mode is a tokamak regime offering many attractive reactor features. In the article, RI of TEXTOR-94 shown to follow same scaling as linear ohmic confinement and thus identified one most fundamental operational regimes. current understanding derived from experiments modelling conditions necessary for sustaining reviewed, are mechanisms leading L-RI transition. article discusses compatibility high impurity seeding with low central power density burning reactor, well...

10.1088/0029-5515/39/11y/303 article EN Nuclear Fusion 1999-11-01

The paper provides an overview of processes and underlying physics governing tungsten melt erosion in the fusion plasma environment. Experiments with three different bulk test-limiters were performed TEXTOR: (i) thermally insulated solid plate fixed on a graphite roof-like limiter heated up by to melting point, (ii) macro-brush ITER-relevant castellated structure (iii) lamellae developed for JET divertor. main objectives determine metal surface damage, formation layer its motion magnetic...

10.1088/0031-8949/2007/t128/016 article EN Physica Scripta 2007-03-01

Rate coefficients for the excitation and ionization of neutral as well singly ionized particles and-–predominantly-–their ratios S(D)/XB, which are important conversion photon into particle fluxes in ionizing fusion boundary plasma, have been modelled experimentally determined plasmas fusion-relevant species such He I, Li C B I&II, O Si Mo W H2, CH(D), C2.

10.1088/0953-4075/43/14/144017 article EN Journal of Physics B Atomic Molecular and Optical Physics 2010-07-05

This paper presents an overview of the status and relevant technical issues for ITER-like Wall Project with emphasis on progress since 11th International Workshop Plasma-Facing Materials Components Fusion Applications.

10.1088/0031-8949/2009/t138/014030 article EN Physica Scripta 2009-12-01

An overview of the results obtained so far for radiative I-mode regime on upgraded Torus Experiment Technology Oriented Research (TEXTOR-94) [Proceedings 16th IEEE Symposium Fusion Engineering (Institute Electrical and Electronics Engineers, Piscataway, NJ, 1995), Vol. 1, p. 470] is given. This under quasistationary conditions with edge neon seeding in a pumped limiter tokamak circular cross section. It combines high confinement β (up to normalized beta, βn=2) low q values (down qa=2.8)...

10.1063/1.872343 article EN Physics of Plasmas 1997-05-01

AbstractLimiter lock systems on the top and bottom of TEXTOR vessel are essential elements for experimental investigations plasma-wall interaction in a tokamak. The designed as user facilities that allow insertion wall (limiter) tools diagnostic (electrical probes, gas injection) without breaking vacuum. specially holder central carrier powerful vacuum pump system permit exchange components within ~1 h. Up to ten electrical signals, four thermocouples, supply can be connected at interface....

10.13182/fst05-a695 article EN Fusion Science & Technology 2005-02-01

This paper presents a feasibility study of laser-induced breakdown spectroscopy (LIBS) for the development an in-situ diagnostic characterization deposition layers on plasma-facing components in fusion devices. Preferentially, LIBS would be applied presence toroidal magnetic field and under high vacuum conditions. The impact laser-energy densities plasma parameters correspondingly number emitted photons reproducibility method has been studied laboratory experiments TEXTOR fine-grain graphite...

10.1088/0031-8949/2011/t145/014028 article EN Physica Scripta 2011-12-01
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