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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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Surface Morphological Features of Molybdenum Irradiated by a Single Laser Pulse

TL;DR: In this paper, an erosion crater formed in correspondence with the laser spot due to the vaporization and melting of the metal, while all around a network of cracks induced by thermal stresses is observed.
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Structure evolution of Y2O3 and consequent effects on mechanical properties of W–Y2O3 alloy prepared by ball milling and SPS

TL;DR: In this article, the structure evolution of Y2O3 during the preparation process was characterized in detail using X-ray diffraction (XRD), scanning electron microscope (SEM) and transmission electron microscopy (TEM).
Journal ArticleDOI

3D Simulation of a Loss of Vacuum Accident (LOVA) in ITER (International Thermonuclear Experimental Reactor): Evaluation of Static Pressure, Mach Number, and Friction Velocity

TL;DR: In this paper, the first seconds of a LOVA in ITER have been simulated by means of a CFD simulation of the beginning of the pressurization transient inside the whole Tokamak, and it has been observed that a real-scale reactor is more severe than the one reproduced in reduced-scale facilities, as STARDUST-U, because the speeds are higher and the dust resuspension capacity of the flow is greater.
Journal ArticleDOI

The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data

TL;DR: Key elements and methodology of the strategy to develop the materials database and handbook for the in-vessel materials are outlined, including concepts to accommodate sparse irradiated materials data and links to EU-DEMO engineering design criteria.
Journal ArticleDOI

The effects of ion irradiation on the micromechanical fracture strength and hardness of a self-passivating tungsten alloy

TL;DR: In this paper, an ultra-fine grained self-passivating tungsten alloy (W88-Cr10-Ti2 in wt.%) has been implanted with iodine ions to average doses of 0.7 and 7 dpa, as well as with helium ions to an average concentration of 650 amp.
References
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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.