Degradation of plasma facing materials due to severe thermal shocks

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

doi:10.1109/fusion.1997.687761

Cited by 3 publications

(7 citation statements)

References 2 publications

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“…In disruption-like thermal shock tests, the first candidate S65C (Brush Wellman, US) showed less crater depth, cracking depth and thickness of the recrystallization thickness, up to 1 GW/m 2 (5.2 MJ/m 2 ) for 5 ms compared to other grades (DShG200, DShG56 and TR-30). 112) Erosion of Be increased significantly after irradiation (0.35 dpa at 350 C and 700 C). It was partially due to bubble formation in melted layer caused by gas (He, T) production during neutron irradiation.…”

Section: Transient Heat Load Testing: Thermal Shock Testsmentioning

confidence: 99%

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ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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Section: Transient Heat Load Testing: Thermal Shock Testsmentioning

confidence: 99%

“…In the unirradiated stage both types of mock-ups showed very high failure limits. [69][70][71][72][73][74] The flat tile mock-up survived 1000 cycles at 20 MW/m 2 . The monoblock was loaded for 1000 cycles at 19 MW/m 2 .…”

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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Section: Validations and Benchmarkingmentioning

confidence: 99%

“…Several experiments from various sources [20][21][22][23] were used to benchmark our numerical simulation to validate the developed model implemented in HEIGHTS before applying it to ITERlike simulation. The first benchmark is an experiment performed in the electron beam facility JUDITH [20]. In this experiment a divertor module FT38/2 with Be armour on CuCrZr structure was exposed in conditions equivalent to VDE with deposited surface energy of 60 MJ m −2 within 1.5 s. The processes of energy deposition, heat conduction in Be, melting and vaporization of Be were modelled and compared with the above experiment.…”

Section: Validations and Benchmarkingmentioning

confidence: 99%

“…In this experiment a divertor module FT38/2 with Be armour on CuCrZr structure was exposed in conditions equivalent to VDE with deposited surface energy of 60 MJ m −2 within 1.5 s. The processes of energy deposition, heat conduction in Be, melting and vaporization of Be were modelled and compared with the above experiment. Figure 2(a) shows a cross-section of the exposed Be target after the energy deposition [20]. Figure 2(b) shows the HEIGHTS simulation results for the same conditions.…”

Section: Validations and Benchmarkingmentioning

confidence: 99%

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Comprehensive simulation of vertical plasma instability events and their serious damage to ITER plasma facing components

Hassanein

Sizyuk²

2008

Nucl. Fusion

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Safe and reliable operation is still one of the major challenges in the development of the new generation of ITERlike fusion reactors. The deposited plasma energy during major disruptions, edge-localized modes (ELMs) and vertical displacement events (VDEs) causes significant surface erosion, possible structural failure and frequent plasma contamination. While plasma disruptions and ELM will have no significant thermal effects on the structural materials or coolant channels because of their short deposition time, VDEs having longer-duration time could have a destructive impact on these components. Therefore, modelling the response of structural materials to VDE has to integrate detailed energy deposition processes, surface vaporization, phase change and melting, heat conduction to coolant channels and critical heat flux criteria at the coolant channels. The HEIGHTS 3D upgraded computer package considers all the above processes to specifically study VDE in detail. Results of benchmarking with several known laboratory experiments prove the validity of HEIGHTS implemented models. Beryllium and tungsten are both considered surface coating materials along with copper structure and coolant channels using both smooth tubes with swirl tape insert. The design requirements and implications of plasma facing components are discussed along with recommendations to mitigate and reduce the effects of plasma instabilities on reactor components.

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