Wall Forum 2020

Normal vs. Inverse Kinematics Nuclear Reactions

Wall Forum

Deuterium Retention in Tungsten Heavy Alloy

Wall Forum

Deuterium Retention in Tin Depending on Temperature

Wall Forum
In order to asses the useability of liquid Sn as a plasma facing material, it is necessary to gather fundamental data on the behaviour of Sn under hydrogen isotope plasma irradiation. In this talk, results on D retention, surface morphology evolution and erosion of Sn will be presented. This talk was held at the End of Year Meeting 2019 of the EUROfusion work package DTT1-LMD. [mehr]

The influence of helium on transport and deuterium retention in tungsten

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Introduction to the SDTrim.SP PWI code

Tungsten lattice structures for DEMO plasma limiters

Persistent research on thermonuclear magnetic confinement fusion has led to current design activities regarding a demonstration fusion reactor (DEMO). One predominantly challenging issue with respect to the realisation of a DEMO reactor is the design and manufacture of highly loaded plasma-facing components (PFCs) that have to sustain intense particle, heat and neutron fluxes during fusion operation. A particularly critical aspect with respect to PFCs in a DEMO reactor are transient wall loadings that can e.g. arise due to plasma instabilities in a tokamak. Such transient events can lead to very intense heat loadings (several tens of GW/m^2 for time periods of a few ms) on PFCs that in turn can damage the blanket structures of a reactor severely. In order to protect the wall of a fusion reactor against such events specific limiter PFCs are currently being investigated. These components are foreseen to baffle the short and intense heat pulses to the reactor walls in order that blanket structures behind these limiter components are not thermally overloaded or damaged. A possible material solution for such limiter PFCs is the use of tailored porous tungsten (W) materials. With such metamaterials, components can be realised that combine an overall low thermal conductance due to the incorporated porosity with the beneficial plasma-wall interaction properties of W.The talk will give an overview regarding the context in which the development of the abovementioned limiter components is currently being performed in the framework of EUROfusion DEMO activities. Furthermore, it will be presented how IPP is involved in these activities through the fabrication and investigation of tailored anisotropic W lattice structures that are fabricated by means of additive manufacturing. [mehr]

Grain-dependent sputtering - A method to detect the impact angle of the ions

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A method will be introduced to evaluate ten thousand of different single-crystal-grains and correlate the crystal orientation to sputter yields, secondary electron emissions and EDX (energy dispersive X-ray spectroscopy) data. With the method, gallium sputtering is described in "every" crystal orientation of the target tungsten. Also, a comparison will be shown between MD (molecular dynamic) simulations, BCA (binary collision approximation) simulations and the experimental data. Due to the huge amount of data, it is possible to evaluate the impact angle of the ion through Principal Component Analysis (PCA), which could be used as a detector. [mehr]

Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium

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The sputtering behavior of EUROFER is of interest for future fusion reactors, as it is considered a candidate plasma-facing material for recessed areas of the first wall. Of particular interest are the formation of a W-enriched surface layer and the development of a heterogeneous surface morphology. In this work, the impact of these two phenomena on the sputter yield of EUROFER are compared to the measured sputter yield by mass-loss. [mehr]

Additive manufacturing for fusion application

Wall Forum
  • Datum: 08.07.2020
  • Uhrzeit: 15:30 - 18:14
  • Vortragender: Rudolf Neu
  • Ort: Zoom
  • Gastgeber: IPP

Materials for Fusion energy technology – Improvement of thermal stability of cold-rolled tungsten sheets by potassium-doping

Wall Forum
  • Datum: 22.07.2020
  • Uhrzeit: 09:30 - 10:30
  • Vortragende(r): Philipp Lied
  • Karlsruher Institut für Technologie
  • Ort: Zoom
  • Gastgeber: IPP
Tungsten is a promising material for high-temperature applications like in future fusion reactors. To overcome the brittle behaviour of conventional tungsten, significant progress has been made in the last decade to improve the ductility of tungsten by severe cold-rolling. The thereby created fine-grained microstructure, however, is not stable at temperatures above 800 °C, leading to a recrystallized, embrittled material. In this talk, I will present parts of our ongoing study, which utilizes potassium-doping to inhibit recrystallization in cold-rolled tungsten sheets at high temperatures. First, the evolution of rolling texture and mechanical properties with increasing rolling strain is compared to equivalently rolled pure tungsten sheets. The second part shows results from isochronal and isothermal annealing experiments, how restoration phenomena can coarsen the tungsten microstructure and the inhibition potential of potassium-bubbles with increasing dispersion. [mehr]

Spectral solvers for modeling of microstructures

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Spectral solvers are an efficient alternative to the finite-element method for modeling the mechanical behavior of composite microstructures and polycrystals. How they work, their advantages, and potential applications for drawn W fibers and W/Cu composites will be discussed. [mehr]

Microstructure of tungsten irradiated by different ions

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Deuterium retention in mixed Be-W-D codeposited layers

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The use of beryllium and tungsten components in ITER will result in the formation of mixed material codeposited layers. Codeposited layers are expected to govern the tritium inventory in ITER. Although deuterium codeposition with beryllium and tungsten has been extensively studied, little is known about deuterium codeposition with Be-W mixed materials. The results of a systematic study of deuterium retention in Be-W codeposited layers will be presented in this talk. These results were obtained during my one-year stay at the PISCES laboratory (San Diego, USA) within the framework of the US-EU Bilateral Collaboration on ITER Materials. [mehr]

Influence of thin surface oxide films on hydrogen isotope uptake and retention in tungsten

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Deuterium (D) uptake through thin (30-50 nm) surface oxide films into metallic tungsten (W) was studied by using self-damaged W as a getter layer. Depth-resolved concentration profiles of D and oxygen were obtained after D plasma exposure by nuclear reaction analysis and Rutherford backscattering spectrometry. It was found that the oxide film effectively blocks D permeation into the metallic W. Additionally oxygen is slowly removed from the surface-near region of the oxide film during plasma exposure. [mehr]

Transport of Hydrogen across Surfaces and Interfaces in TESSIM-X

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The transport of hydrogen isotopes (His) through the first wall of fusion devices is the driving process for HIs retention but also for permeation to the coolant. Both of these processes have fundamental implications for the safety and the tritium self-sufficiency of a fusion reactor. The first wall of a future fusion reactor will be comprised of the top armor material W and structural materials below like steel or Cu alloys that connect the top plasma-facing surface to the coolant. Therefore, the transport through the whole component from the W armor layer to the coolant needs to be understood. The diffusion trapping code TESSIM-X is capable of handling multi material interfaces and features a fully kinetic surface model that implements the time dependent transport of HIs given an energy landscape. This presentation will describe the physics of HIs transition across solid/solid and solid /gas interfaces. [mehr]

H-retention in tungsten fibre-reinforced tungsten composites

Wall Forum
Deuterium (D) retention in Wf/W manufactured by chemical vapor deposition (CVD) has been investigated using Wf/W single layered model systems consisting of a single plane of unidirectional tungsten fibers embedded in a tungsten matrix produced by CVD. Various parameters with potential influence on the D retention, such as the choice of an erbium oxide interface and potassium doping, have been included in the investigation. The samples have been ground to varying distances between surface and fiber plane - exposing distinct details of the Wf/W microstructures at the surface. After exposure to low temperature D plasma, the D retention of all samples was measured by nuclear reaction analysis (NRA) and thermal desorption spectroscopy (TDS). It was found that the D retention in Wf/W composites is higher than in reference samples made from hot-rolled W by factors between 2 and 5. In addition, a comparison of NRA and TDS data indicated that D penetrates faster into the depth of Wf/W material than into hot-rolled tungsten. [mehr]
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