Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4

Roedig, M.; Kuehnlein, Walter L.; Linke, J.; Pitzer, D.; Merola, M.; Rigal, Emmanuel; Schedler, B.; Visca, E.

doi:10.1016/j.jnucmat.2004.04.176

Cited by 44 publications

(33 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…71) The thermal fatigue tests of the monoblock mock-up (0.2 dpa at 200 C) were carried out at 12 MW/m 2 for 1000 cycles without failure. 74) However, the failure limits are reduced to about 10 MW/m 2 after 0.15 and 0.6 dpa at 200 C. The failure was caused by detachment of the W rods at the joining between W alloy and OFHC-Cu which is ascribed to radiation induced embrittlement of the OFHC-Cu layer. 74) On the other hand, W monoblock showed rather benign performance before and after irradiation at 18 MW/m 2 for 1000 cycles.…”

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 96%

“…74) However, the failure limits are reduced to about 10 MW/m 2 after 0.15 and 0.6 dpa at 200 C. The failure was caused by detachment of the W rods at the joining between W alloy and OFHC-Cu which is ascribed to radiation induced embrittlement of the OFHC-Cu layer. 74) On the other hand, W monoblock showed rather benign performance before and after irradiation at 18 MW/m 2 for 1000 cycles. 74) W-coated mock-up, VPS-W (5 mm thickness) on CuCrZr with Ni-Al-Si interlayer, was tested as an alternative solution of W components.…”

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 96%

“…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%

“…74) After neutron irradiation (0.2, 0.35, 1 dpa at $200 C, 350 C and 700 C in HFR, Petten, the Nederland), both types of CFC mock-ups showed a dramatic increase of surface temperature due to the reduction of thermal conductivity of CFC. 74) In case of CFC flat tiles, detachment of a tile started after 200 cycles at 19.5 MW/m 2 after 0.2 dpa at 200 C, and tests were limited to 15 MW/m 2 after 1 dpa at 200 C because of strong erosion (sublimation). Monoblock design is considered more robust because it will not detach due to the geometry, however, monoblock mock-up showed even more severe temperature increase after irradiation.…”

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

See 3 more Smart Citations

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

View full text Add to dashboard Cite

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.

show abstract

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 96%

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 96%

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

See 2 more Smart Citations

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

View full text Add to dashboard Cite

show abstract

“…3) at the Research Center Juelich will enable also the simulation of very short events (ELMs) with high repetition rate. Since qualified neutron sources for the irradiation with energetic (14 MeV) neutrons are not available, the degradation of plasma facing materials and components under ITER specific conditions has been investigated in material test reactors [8] …”

Section: Simulation Of Iter Relevant Heat Loadsmentioning

confidence: 99%

EU Development of High Heat Flux Components

Linke

Lorenzetto²,

Majerus

et al. 2005

Fusion Science and Technology

Self Cite

View full text Add to dashboard Cite

Plasma-facing materials for thermo-nuclear fusion devices

Singheiser

Hirai

Linke

et al. 2009

Trans Indian Inst Met

View full text Add to dashboard Cite

The plasma facing materials and components in existing and future fusion devices are strongly affected by plasma wall interaction processes. These components, in particular the first wall (FW), the limiters and the divertor are subject to intense quasi-stationary thermal loads during plasma operation. While the resulting thermal loads to the first wall will remain below 1 MW·m -2 , special attention has to be paid to high heat flux components like limiters and the divertor. Here the expected power densities will be at least one order of magnitude above the ones at the FW, with expected peak heat fluxes of up to 20 MW·m -2 for future magnetic confinement devices. Beside quasi-stationary heat loads, short transient thermal pulses with deposited energy densities up to several tens of MJ·m -2 are another serious concern for next step tokamak devices, in particular for ITER. The most serious events are plasma disruptions, vertical displacement events, and Edge Localized Modes (socalled ELMs). These requirements make high demands on the selection of qualified materials and reliable fabrication processes for actively cooled plasma facing components. High heat flux test facilities based on intense electron and ion beams have been utilized successfully to assess the efficiency and the fatigue life time of different material solutions and design concepts. Modeling and experiments with both normal operation scenarios and transient events, are being performed to evaluate and to quantify the resulting material erosion or damage and thus to assess the life time of the components. Additional research activities are focused on the degradation of materials and joints due to energetic neutrons. In order to investigate irradiation induced property changes, materials samples and actively cooled plasma facing components have been irradiated in fission reactors and tested in thermal load tests. The technical solutions which are considered today are mainly based on beryllium, carbon materials or tungsten as armor materials and copper alloys or stainless steel for the heat sink. Furthermore, the needs for extensive quality control methods and non-destructive analyses during the procurement phase will be highlighted.

show abstract

Post irradiation testing of samples from the irradiation experiments PARIDE 3 and PARIDE 4

Cited by 44 publications

References 3 publications

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

EU Development of High Heat Flux Components

Plasma-facing materials for thermo-nuclear fusion devices

Contact Info

Product

Resources

About