First-principles investigation of Wsingle bondV and Wsingle bondMo alloys as potential plasma facing materials (PFMs) for nuclear application

https://doi.org/10.1016/j.ijrmhm.2020.105448Get rights and content

Highlights

  • First-principles calculations of the BCC Wsingle bondV and Wsingle bondMo systems were investigated.

  • Both systems are thermodynamically favourable and mechanically stable at 0 K.

  • The Hv of BCC W1-xMox and W1-xVx was predicted using an ab initio technique.

  • Mo reduced the hardness while up to 15 at.% V composition sustained high hardness of solid solutions.

  • The VCA tool is reliable for design and product development of advanced W-based alloys.

Abstract

Density-functional theory (DFT) based first-principles calculations were used to investigate the crystal structure, binding energy, phase stability and elastic properties of body-centered cubic (BCC) W-based binary solid solutions. The effect of alloying up to 50 atomic percent (at.%) concentration range is determined from the virtual-crystal approximation (VCA) approach. Resulting BCC solid solutions are assessed in comparison to the ideal Vegard's law. Solubility of the alloying elements is characterized by the negative enthalpy of mixing. The values of elastic constants computed for the ground state structures are used to assess the effect of alloying on the ductility and hardness. Based on current results, it seems key to strike a tricky balance between moderate Pugh's modulus ratio (B/G) between bulk and shear moduli (B,G) and elastic anisotropy (A) such that high hardness is not completely compromised at the expense of ductility. The predicted property trends are in agreement with existing theoretical and experimental data, which is indicative that the VCA approach is reliable in development of such alloys.

Introduction

Despite its key concerns such as environmental impact, safety and raw materials supply limitations, nuclear fusion still has a potential to become a source of safe and clean power generation, thus rendering nuclear power as a solution for future energy generation. However, with better selection of materials closer to the fusion reaction prone to becoming radioactive, such that they have short half-life, then the issue of disposing radioactive waste can be minimized or eliminated [1]. Plasma-facing materials (PFM) and plasma facing components (PFC) are exposed to the harsh nuclear fusion power plants environments as they act as the interface between the plasma and the material part [1,2]. Hence the operational conditions in such extreme environment require materials that can withstand high heat flux and surface neutron irradiation. Such a combination of demand poses a stiff challenge in terms of material performance. Consequently, great effort has been dedicated to search (theoretical and experimental) for suitable materials with high thermal conductivity, low sputtering yield and sufficient mechanical properties even under neutron irradiation. Due to their supreme high temperature properties such as high melting temperature, good thermal conductivity, high creep resistance, high temperature strength and good erosion resistance, tungsten (W) and tungsten based materials are found to be amongst the frontrunners as potential candidates for various fusion applications [[2], [3], [4]]. However, prior to application of such materials certain properties still need to be enhanced to improve their performance. The key properties that need to be improved are the low temperature ductility and fracture toughness as well as the ductile-to-brittle transition temperature (DBTT) while maintaining high temperature properties. One of the methods to improve the ductility and DBTT is through solid solution alloying. In many studies, the first-principles calculations have demonstrated the capability to investigate solid solution alloying in various systems [[5], [6], [7], [8]] and was successful in predicting data that supported the existing experimental data.

Over the past decades, density functional theory (DFT) based methods have become a useful and viable tool to investigate behaviour of crystalline materials. These methods aid in facilitating the development of advanced materials by providing guidelines for design of new materials and give physical mechanistic insight into the origins of experimentally-derived trends. This is attributed to massive development efforts complemented by exponential increase in computational power. Consequently, the DFT-based first-principles calculations have demonstrated the capability to generate results with high level of accuracy and comparable to experimental data [[5], [6], [7], [8]]. The obtained materials data do not only provide insights about materials behaviour at electronic or atomic scale but can also be fed into a range of length and time scales modelling and simulation techniques capable of predicting materials performance at engineering scale. At this scale, the predictions of the macroscopic mechanical properties, such as flow stress, work hardening, and fatigue behaviour, in metals or other materials undergoing dislocation mediated plastic flow, is key [9].

In this study, a first-principles based virtual-crystal approximation (VCA) solid-solution unit-cell approach is used investigate the effect of alloying on various properties of W. It is well-known from metallurgy that solid-solution may have softening or hardening (strengthening) effect while in other systems induces phase transformation [5]. The Wsingle bondV and Wsingle bondMo binary solid solution systems were chosen since they present 100% solubility [10,11], although in the current work the focus is limited to 50 at.% solute. A random solid solution (SS) with BCC crystal structure is represented by a model shown in Fig. 1. Ideally using this model, W-X (X = V, Mo) binary solid solution may be formed when an atom of W or X occupy randomly any position in the crystal, thus only changing the composition. In this manner, correct symmetry and crystal structure are maintained as they are both critical to predicting structural and elastic properties, with the latter linked to mechanical properties reported in experimental data. The composition can be varied by representing atoms as a fractional composition, A1-xBx. The details of the calculation for the elastic constants are presented in previous studies [5]. Unit cell approach allows for small composition variation Wsingle bondV and Wsingle bondMo BCC SS. For further clarification, the full details of this method are described elsewhere [5]. Current approach differs slightly from earlier ab initio calculations studies conducted on similar materials in that supercell and ordered crystal structures were used [12].

Section snippets

Methodology

The ab initio modelling work was carried out using the CASTEP module within the Materials Studio software package [13]. The CASTEP code, a first principles quantum mechanical based programme for performing electronic structure calculations within the Hohenberg-Kohn-Sham density functional theory (DFT) [14,15], was used within the generalized gradient approximation (GGA) formalism [16] to describe the electronic exchange-correlation interactions. We used the recent Perdew-Burke-Ernzerhof (PBE) [

Phase stability

As shown in Fig. 2(a), the lattice parameter decreases with increase in V composition as expected since the metallic atomic radius of V is smaller than that of W. However, this decrease in lattice parameter is linear but deviates negatively from the Vegard's rule shown by the dotted line. Nonetheless, the predicted trend as well as the negative deviation from Vegard's law are both in agreement with experimental observations [10]. In addition, the predicted lattice parameter of 3.181 Å for

Conclusion

Both systems considered in this study are thermodynamically favourable and mechanical stable at 0 K as characterized by negative mixing enthalpy and C′ > 0. The Vickers hardness of BCC W1-xMox and W1-xVx solid solutions predicted for the first time using an ab initio technique are presented. Introduction of Mo significantly reduces the hardness of W while the introduction of up to 15 at.% V composition seems to sustain high hardness complimented by slight increase in ductility but A is reduced.

Declaration of Competing Interest

No conflict of interest exists.

Acknowledgements

The authors are grateful to the support of Department of Science and Innovation (DSI) through Center for High Performance Computing for their computational resources.

References (31)

  • D.M. Duffy

    Fusion power: a challenge for materials science

    Phil. Trans. R. Soc. A

    (2010)
  • Rieth M. Linsmeier Ch et al.

    Development of advanced high heat flux and plasma-facing materials

    Nucl. Fusion

    (2017)
  • D. Nguyen-Manh et al.

    Self-interstitial atom defects in bcc transition metals: group-specific trends

    Phys. Rev. B

    (2006)
  • M.A. Kebede et al.

    Solution-combustion synthesized aluminium-doped spinel (LiAlxMn2-xO4) as a high-performance lithium-ion battery cathode material

    Appl. Phys. A Mater. Sci. Process.

    (2015)
  • S.V. Nagender-Naidu et al.

    The Mo−W (molybdenum-tungsten) system

    Bull. Alloy Phase Diagr.

    (1984)
  • Cited by (8)

    • First-principles study phonon and thermodynamic properties of binary W-Mo alloys

      2022, Materials Today Communications
      Citation Excerpt :

      Nikoulis et al. [9] used the machine-learning interatomic potential to investigate the effect of W-Mo binary systems on the threshold displacement energies and the atomic interatomic potential function of W-Mo alloys had a significant dependence on the local chemical environment and elements of the main recoil atoms. By first-principles calculation method, Phasha et al. [19] reported the crystal structure, phase stability, binding energy and elastic constants of the W-Mo alloys. Chen et al. [20] studied the formation energies, binding energies and point defect of binary W-Mo alloys by using the developed interatomic potentials.

    • Does the pathway for development of next generation nuclear materials straightly go through high-entropy materials?

      2021, International Journal of Refractory Metals and Hard Materials
      Citation Excerpt :

      The structural components of the breeder blanket in fusion reactors are expected to operate well above 400 °C, exceeding the working limit of current Zr alloys [14]. Tungsten is the leading candidate for plasma-facing parts owing to its high melting temperature, low erosion rates, high thermal conductivity and small tritium retention [18,19]. Unfortunately, these advantages are coupled with a very low fracture toughness and pronounced embrittlement upon irradiation with neutrons at temperatures below ~800 °C, which significantly restrict the useful operating temperature window and create some difficulties in fabrication [4].

    View all citing articles on Scopus
    View full text