Material damage to beryllium, carbon, and tungsten under severe thermal shocks

Linke, J.; Duwe, R.; Gervash, A.; Qian, R.H.; Rödig, M.; Schuster, Andreas

doi:10.1016/s0022-3115(98)00245-1

Cited by 22 publications

(3 citation statements)

References 5 publications

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“…59 pulse; on the other hand charged particles originating from the heated surface and/or from the ablation vapour have strong impact on the measured current I abs . When the beam power is increased this current drop occurs earlier; however, it does not affect the energy transfer to the test sample, since the energy of the emitted charged particles is negligible compared to the one of the incident electrons (120 keV) [15][16][17][18]. The high temperatures in the electron beam-exposed surface region result in melting of SiC and TiC, and molten silicon and titanium carbides segregate to the sample surface.…”

Section: Resultsmentioning

confidence: 99%

High Heat Flux Testing of TiC-Doped Isotropic Graphite for Plasma Facing Components

Lopez‐Galilea

Pintsuk

Garcı́a-Rosales

et al. 2008

AMR

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The technical design solution for the future thermonuclear fusion reactor, ITER, must guarantee a reasonable lifetime from a safety and economical point of view. Carbon fibre reinforced carbon (CFC) is envisaged as a corrective material solution for the strike point area of ITER divertor due to its high thermal shock resistance necessary to withstand excessive heat loads during transient thermal loads; in particular plasma disruptions that can deposit energy densities of several ten MJm-2 with a typical timescale in the order of milliseconds. In this work, as potential alternative to CFCs new finely dispersed TiC-doped isotropic graphites with high thermal conductivity and mechanical strength, manufactured using synthetic mesophase pitch “AR” as raw material, have been evaluated under typical disruption conditions using an energetic electron beam at the JUDITH facility.

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Section: Resultsmentioning

confidence: 99%

High Heat Flux Testing of TiC-Doped Isotropic Graphite for Plasma Facing Components

Lopez‐Galilea

Pintsuk

Garcı́a-Rosales

et al. 2008

AMR

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“…Material tests under pure heat loads typically use pulses which simulate the impact of a single or several disruption-, VDE-or ELM-like heat loads. Since disruption and VDElike heat loads lead to melting [76][77][78], ELM-like heat loads will be considered here. These tests use pulse duration and energy densities as outlined above for ELMs.…”

Section: 21mentioning

confidence: 99%

Baseline high heat flux and plasma facing materials for fusion

et al. 2017

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In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing materials (PFMs) and coolant tube materials, respectively, mainly due to high thermal conductivity and, in the case of tungsten, its high melting point. In this paper, recent understandings and future issues on responses of tungsten and Cu alloys to fusion environments (high particle flux (including T and He), high heat flux, and high neutron doses) are reviewed. This review paper includes; Tritium retention in tungsten (K. Schmid and M. Balden), Impact of stationary and transient heat loads on tungsten (J.W. Coenen and Th. Loewenhoff), Helium effects on surface morphology of tungsten (Y. Ueda and A. Ito), Neutron radiation effects in tungsten (A. Hasegawa), and Copper and copper alloys development for high heat flux components (C. Hardie, M. Porton, and M. Gilbert).

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“…The thermal shock response of beryllium has previously been studied within the fusion energy community, where it is the plasma facing material of choice for the International Thermonuclear Experimental Reactor fusion test reactor [5]. Linke et al [6] and Spilker et al [7] have used electron beams to mimic the high energy density deposition and induced thermal shock expected on the inner walls of a fusion tokamak. Microstructural studies were then performed to evaluate material degradation and resistance to thermal shock from varying loading cycles.…”

Section: Introductionmentioning

confidence: 99%

Thermal shock experiment of beryllium exposed to intense high energy proton beam pulses

Ammigan

Bidhar

Hurh

et al. 2019

Phys. Rev. Accel. Beams

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Beryllium is a material extensively used in various particle accelerator beam lines and target facilities, as beam windows and, to a lesser extent, as secondary particle production targets. With increasing beam intensities of future multimegawatt accelerator facilities, these components will have to withstand even greater thermal and mechanical loads during operation. As a result, it is critical to understand the beaminduced thermal shock limit of beryllium to help reliably operate these components without having to compromise particle production efficiency by limiting beam parameters. As part of the RaDIATE (radiation damage in accelerator target environments) Collaboration, an exploratory experiment to probe and investigate the thermomechanical response of several candidate beryllium grades was carried out at CERN's HiRadMat facility, a user facility capable of delivering very-high-intensity proton beams to test accelerator components. Multiple arrays of thin beryllium disks of varying thicknesses and grades, as well as thicker cylinders, were exposed to increasing beam intensities to help identify any thermal shock failure threshold. Real-time experimental measurements and postirradiation examination studies provided data to compare the response of the various beryllium grades, as well as benchmark a recently developed beryllium Johnson-Cook strength model.

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Material damage to beryllium, carbon, and tungsten under severe thermal shocks

Cited by 22 publications

References 5 publications

High Heat Flux Testing of TiC-Doped Isotropic Graphite for Plasma Facing Components

High Heat Flux Testing of TiC-Doped Isotropic Graphite for Plasma Facing Components

Baseline high heat flux and plasma facing materials for fusion

Thermal shock experiment of beryllium exposed to intense high energy proton beam pulses

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