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Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Michael Rieth, +70 more
- 01 Jan 2013 - 
- Vol. 432, Iss: 1, pp 482-500
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TLDR
In this article, the progress of work within the EFDA long-term fusion materials program in the area of tungsten alloys is reviewed, with a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.
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This article is published in Journal of Nuclear Materials.The article was published on 2013-01-01 and is currently open access. It has received 599 citations till now.

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Journal ArticleDOI

A better nanochannel tungsten film in releasing helium atoms

TL;DR: In this article, three tungsten columns whose top surfaces are {100, {110} and {111} -oriented were studied by molecular dynamics simulations and density functional theory calculations.
Journal ArticleDOI

The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation

TL;DR: In this article, a Hall-Petch-like relationship based on the mean boundary spacing along the crack front and a modified version also reflecting the high aspect ratios of the grains are well-suited to describe the evolution in transition temperature and its anisotropic nature.
Journal ArticleDOI

Effect of Ti and TiC Alloyants on the Mechanical Properties of W-Based Armour Materials

TL;DR: In this article, two W/Ti based products are presented: (1) a W-Ti alloy with a Ti solid solution and (2) an UFG microstructure product with TiC dispersed particles; both with the aim of obtaining a suitable fusion armour material with enhanced properties, especially at very high temperatures when pure tungsten suffers strong thermal degradation.
References
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Journal ArticleDOI

Separable dual-space Gaussian pseudopotentials

TL;DR: The pseudopotential is of an analytic form that gives optimal efficiency in numerical calculations using plane waves as a basis set and is separable and has optimal decay properties in both real and Fourier space.
Journal ArticleDOI

Relativistic separable dual-space Gaussian pseudopotentials from H to Rn

TL;DR: The relativistic dual-space Gaussian pseudopotential was introduced in this paper for the whole Periodic Table and a complete table of pseudopoetic parameters for all the elements from H to Rn.
Journal ArticleDOI

Overview No. 1: The nucleation of cavities by plastic deformation

S.H. Goods, +1 more
- 01 Jan 1979 - 
TL;DR: A review of the literature concerning cavity nucleation as a result of plastic deformation indicates that at low temperatures there is a critical plastic strain required to nucleate a cavity.
Journal Article

Nuclear fusion

TL;DR: The advantages of nuclear fusion as an energy source and research progress in this area are summarized in this article, where the current state of the art is described, including the Compact Ignition Tokamak (CIT), International Thermonuclear Experimental Reactor (ITER), and a US design called TIBER II.
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Q1. What contributions have the authors mentioned in the paper "Recent progress in research on tungsten materials for nuclear fusion applications in europe" ?

In this paper, the authors present a detailed review of the use and properties of tungsten materials for the first wall of a fusion tokamak. 

The main requirements of tungsten materials for structural divertor applications compriseproperties like high thermal conductivity, high temperature strength and stability, high recrystallization temperature, and enough ductility for an operation period of about two years under enormous neutron load. 

It was demonstrated that diffusion bonding at only 700 °C can be successfully performed with a minimal alteration of the microstructure of the base materials and strongly reduced formation of vanadium-carbide. 

The linear oxidation rate of tungsten at 1000 °C is about 1.410-2 mg cm-2 s-1 [43], which in the approximately 1000 m2 DEMO first wall would correspond to a release of half a ton of tungsten oxides per hour. 

Powder injection moulding (PIM) was investigated as a mass fabrication option for the tungstenarmour tiles which had to be joined to the thimbles. 

After the implantation has stopped (region III), the D retention drops and a remnant D flux to the W surface takes place for about 10 min. 

The use of tungsten as first wall (FW) armour of a fusion power reactor represents an importantsafety concern in the event of a loss of coolant accident with simultaneous air ingress into the reactor vessel. 

But even neglecting the irradiation effects (due to the large gaps in the knowledge of properties of these materials), there are still unsolved problems related to the use and properties of tungsten materials. 

Due to the fabrication route, missing mechanical working and/or an increased impurity level could also be an additional explanation for this severe brittleness. 

In helium cooled divertor designs tungsten materials are also considered for structural use (e.g. as pressurized pipes or thimbles). 

The formation of intermetallic compounds in tungsten alloys is just one of the factors responsible for their increased hardening, the other being the conventional solute hardening that gives rise to the embrittlement of the alloys that occurs even in the limit where the concentration of the alloying elements is small. 

It shows that the vacancy formation energy in W-Ta alloys depends sensitively on the lattice site at which a vacancy is formed, whereas in W-V alloys it is almost independent of the location of the vacancy site. 

In the first case, pure metallic powders were mechanically mixed, compacted, and molten to allow for brazing filler materials with homogeneous compositions. 

In a recent development, precursor powders are fabricated under certain solution conditions where the particle growth could be controlled to produce uniformly yttrium doped nano-sized tungsten oxides. 

In W, the production of impurities, such as Re, Ta, and Os, is fairly significant, being of the order of a few thousand to tens of thousands of atomic parts per million (appm) over a typical DEMO-like first-wall 5-year neutron exposure. 

Preliminary results of mechanical characterization of these W-W joints using Ti-Fe fillers gave rise to an average shear strength of 140 ± 8 MPa. 

So far, only rhenium is known to improve the ductility of tungsten by solid solution but its usefor fusion energy applications has been ruled out for various reasons (cost, irradiation embrittlement). 

The oxidation behaviour of the WCr12Ti2.5 alloy is similar to that of the WCr10Si10 material; in this case the oxidation rate is similar to that of thin films of same composition at 600 °C but higher at 800 and 1000 °C [48]. 

Only grain growing and physical sputtering were identified as the surface modification processes of the pure hydrogen loaded materials (Fig. 17). 

The results show the possibility of designing alloys where vacancies form within a desired range of temperature, suggesting the possibility of developing alloys with improved stability under irradiation. 

the fracture resistance may increase with crack propagation, which implies that it is not always possible to characterize the material‘s toughness with one single value such as plane strain fracture toughness KIC or critical energy release rate GIC. 

In what follows, the results, conclusions, and outlooks are summarized for each of theW&WALLOYS programme‘s main subtopics, which are (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. 

Further investigations into the effect of grain boundary crystallography and chemistry are currently on-going, but it appears that tantalum has no beneficial effects, and may even have detrimental effects, on the fracture properties of tungsten.