Development of the armoring technique for ITER Divertor Dome

Litunovsky, N.V.; Alekseenko, E. N.; Makhankov, A.; Mazul, I.

doi:10.1016/j.fusengdes.2011.02.050

Cited by 29 publications

(9 citation statements)

References 2 publications

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“…Moreover, as the number of armoring tiles in plasma-facing components is rather high, replacement of defective tiles after manufacturing are needed. Brazing is beneficial from this point of view [27] since it allows for a local replacement of a particular damaged component. For this purpose, filler alloys in a form of foils are convenient, but the composition of such alloys should consist of reduced-activation elements only because of the requirement for the DEMO materials.…”

Section: Methodsmentioning

confidence: 99%

Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup

et al. 2021

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Self-passivating, so-called smart alloys are under development for a future fusion power plant. These alloys containing tungsten, chromium and yttrium must possess an acceptable plasma performance during a regular plasma operation of a power plant and demonstrate the suppression of non-desirable oxidation of tungsten in case of an accident. The up-scaling of the bulk smart alloys to the reactor-relevant sizes has begun and the first samples with a diameter of 50 mm and thickness of 5 mm became available. The samples feature high relative density of above 99% and good homogeneity. With production of bulk samples, the research program on joining the smart alloy to the structural material was initiated. In a present study, the novel titanium–zirconium–beryllium braze was applied successfully to join the smart alloy to the Rusfer-reduced-activation steel. The braze has survived at least a hundred of cyclic thermal excursions in the range of 300–600 °C without mechanical destruction.

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Section: Methodsmentioning

confidence: 99%

Self-passivating smart tungsten alloys for DEMO: a progress in joining and upscale for a first wall mockup

et al. 2021

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“…%). The filler was approved for brazing the armor of the ITER Divertor Dome [23] with the following parameters: T = 900 o C, t = 300 s, P ~ 510 -4 Pa. Special fixture and rigs for proper armor fixation and clamping were developed and used.…”

Section: Manufacturing Of W Divertor Target Mock-upsmentioning

confidence: 99%

Globus-M Experiments With Pre-Damaged Tungsten Divertor

Novokhatsky¹,

Gusev²,

Ber³

et al. 2017

PAST-TF

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Divertor targets composed of pre-damaged tungsten (W) tiles were prepared and installed at an outer strike point region of a Globus-M lower divertor. An electron beam was used to irradiate the W tiles close to influence of 1000-2000 disruption events in ITER. Providing adequacy of the e-beam thermal load to the real ITER conditions, the pre-damage treatment was simulated by ANSYS Multiphysics software. The W e-beam treatment results in melting of surface layers, shrinkage and fatigue intergranular cracking of the metal, void formation, grain ordering, and decreasing of microhardness. The first test of the pre-damaged W targets in the Globus-M divertor showed pronounced non-uniform heating caused by plasma disruption events. Temperature field formation may be explained by non-uniform thermal conductivity of the damaged layer or interface between the layer and undamaged bulk structure. One of the most important effects of the pre-damaged W installation is no significant changes in Globus-M discharge behavior.

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“…For joining of W-Cu tiles brazing is performed at ∼970 • C, then brazing assembly is fast cooled in a furnace by gas quenching at cooling rate above 100 • C/s [3]. Thus, necessary strength of CuCrZr may be provided after an additional aging cycle (450 • C, 1 h) in the same furnace.…”

Section: Manufacturing Technologies and Industry Preparationmentioning

confidence: 99%