Development of laser-based diagnostics for surface characterisation of wall components in fusion devices

Huber, A.; Schweer, B.; Philipps, V.; Gierse, N.; Zlobinski, M.; Brezinsek, S.; Biel, W.; Kotov, V.; Leyte-Gonzales, R; Mertens, Ph.; Samm, U.

doi:10.1016/j.fusengdes.2011.01.090

Cited by 66 publications

(27 citation statements)

References 6 publications

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“…Laser-based diagnostics for determining the composition of the material of the wall and the tritium retention are being examined for the ITER [56]. The method is simply to heat by laser irradiation the surface and evaporate the material.…”

Section: Radiation Measurements (Bolometers and Spectroscopy)mentioning

confidence: 99%

Diagnostics and control for the steady state and pulsed tokamak DEMO

Orsitto¹,

Villari²,

Moro³

et al. 2016

Nucl. Fusion

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The present paper is devoted to a first assessment of the DEMO diagnostics systems and controls in the context of pulsed and steady state reactor design under study in Europe. In particular, the main arguments treated are: (i) The quantities to be measured in DEMO and the requirements for the measurements; (ii) the present capability of the diagnostic and control technology, determining the most urgent gaps, and (iii) the program and strategy of the research and development (R&D) needed to fill the gaps. Burn control, magnetohydrodynamic stability, and basic machine protection require improvements to the ITER technology, and moderated efforts in R&D can be dedicated to infrared diagnostics (reflectometry, electron cyclotron emission, polarimetry) and neutron diagnostics. Metallic Hall sensors appear to be a promising candidate for magnetic measurements in the high neutron fluence and long/steady state discharges of DEMO.

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Section: Radiation Measurements (Bolometers and Spectroscopy)mentioning

confidence: 99%

Diagnostics and control for the steady state and pulsed tokamak DEMO

Orsitto¹,

Villari²,

Moro³

et al. 2016

Nucl. Fusion

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“…[8] [9]) to determine fuel content and material composition. Both the plasma device and the analysis chamber shall be located inside a Hot Cell.…”

Section: Jule-psi and Judithmentioning

confidence: 99%

“…For that purpose, two Nd:YAG lasers are available at FZJ (LID-QMS: pulse energy > 100 J, pulse duration 1 − 3 ms, detection of the desorbed fuel gas by Quadrupol Mass Spectrometry (QMS), LIA-QMS, LIBS: pulse energy > 5 J, pulse duration <15 ns, detection via line-of-sight QMS for LIA, optical spectroscopy for LIBS, cf. [9] for details).…”

Section: Jule-psi and Judithmentioning

confidence: 99%

New linear plasma devices in the trilateral euregio cluster for an integrated approach to plasma surface interactions in fusion reactors

Unterberg¹,

Jaspers

Koch³

et al. 2011

Fusion Engineering and Design

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a b s t r a c tNew linear plasma devices are currently being constructed or planned in the Trilateral Euregio Cluster (TEC) to meet the challenges with respect to plasma surface interactions in DEMO and ITER: i) MAGNUM-PSI (FOM), a high particle and power flux device with super-conducting magnetic field coils which will reach ITER-like divertor conditions at high magnetic field, ii) the newly proposed linear plasma device JULE-PSI (FZJ), which will allow to expose toxic and neutron activated target samples to ITER-like fluences and ion energies including in vacuo analysis of neutron activated samples, and iii) the plasmatron VISION I, a compact plasma device which will be operated inside the tritium lab at SCK-CEN Mol, capable to investigate tritium plasmas and moderately activated wall materials. This contribution shows the capabilities of the new devices and their forerunner experiments (Pilot-PSI at FOM and PSI-2 Jülich at FZJ) in view of the main objectives of the new TEC program on plasma surface interactions.

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“…Short and ultra-short laser pulses are used in a wide spectrum of fields like material processing [1,2], nano-particle production [3,4] or in diagnostic applications [5]. Our purpose is to establish a reliable quantitative laser-induced breakdown spectroscopy (LIBS) diagnostic for deuterium retention analysis on inner walls of future fusion reactors as proposed by Huber et al [6]. The goal is to provide a method that can be applied not only to present-day fusion facilities like EAST Tokamak in Hefei, China or W7-X Stellarator in Greifswald, Germany [7,8], but also to future fusion devices like ITER [9].…”

Section: Introductionmentioning

confidence: 99%

Laser-induced ablation of tantalum in a wide range of pulse durations

et al. 2020

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We present data and analysis of the laser-induced ablation of pure tantalum (Ta, $$Z=73$$ Z = 73 ). We have identified different physical regimes using a wide range of laser pulse durations. A comparison of the influence of strongly varying laser pulse parameters on high-Z materials is presented. The crater depth caused by three different laser systems of pulse duration $${\varDelta }\tau _1=5\,\mathrm {ns}$$ Δ τ 1 = 5 ns and wavelength $$\lambda _1=1064\,\mathrm {nm}$$ λ 1 = 1064 nm , $${\varDelta }\tau _2=35\,\mathrm {ps}$$ Δ τ 2 = 35 ps , $$\lambda _2=355\,\mathrm {nm}$$ λ 2 = 355 nm and $${\varDelta }\tau _3=8.5\,\mathrm {fs}$$ Δ τ 3 = 8.5 fs , $$\lambda _3=790\,\mathrm {nm}$$ λ 3 = 790 nm are analyzed via confocal microscopy as a function of laser fluence and intensity. The minimum laser fluence needed for ablation, called threshold fluence, decreases with shorter pulse duration from $$1.10\,\mathrm {J/cm}^2$$ 1.10 J / cm 2 for the nanosecond laser to $$0.17\,\mathrm {J/cm}^2$$ 0.17 J / cm 2 for the femtosecond laser.

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Development of laser-based diagnostics for surface characterisation of wall components in fusion devices

Cited by 66 publications

References 6 publications

Diagnostics and control for the steady state and pulsed tokamak DEMO

Diagnostics and control for the steady state and pulsed tokamak DEMO

New linear plasma devices in the trilateral euregio cluster for an integrated approach to plasma surface interactions in fusion reactors

Laser-induced ablation of tantalum in a wide range of pulse durations

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