Predicting the performance of tungsten in a fusion environment: a literature review

Abstract

Tungsten has been proposed for use in the divertor of future fusion devices. In this environment, it will be exposed to high heat fluxes, neutron damage and hydrogen and helium implantation. This review covers previous experimental and modelling work to establish our ability to predict the performance of tungsten in a fusion environment. Surrogates for high-energy neutrons have been used to predict the change in mechanical properties of tungsten, including fission neutron and self-ion exposure. These studies are critically analysed, with a focus on the difference in results from neutron and ion studies. Further studies to improve our ability to predict the performance of tungsten are proposed as a critical part of the path towards a working fusion reactor.

Radiation-induced segregation in W-Re: from kinetic Monte Carlo simulations to atom probe tomography experiments

“…at once. At high temperatures (stage IV Recovery [3]) vacancies become much more mobile and play a more significant role in microstructural evolution. Monte Carlo (MC) simulations using a CE Hamiltonian have predicted the precipitation of Re in W alloys through the formation of small voids, decorated with Re atoms [23].…”

“…3 Computational results 3.1 SGMC Figure 3 shows the equilibriated Re content as a function of the change in chemical potential, ∆µ. There is a jump in the concentration at 100 K indicating the presence of a miscibility gap, implying a phase transformation is predicted by this parameterisation.…”

“…The realisation of fusion energy is dependant on the development of high performance plasma facing materials that can withstand the extreme operational conditions they will be subjected to. Estimates suggest that the plasma facing components (PFCs) in a prototype fusion power station (DEMO) will experience a thermal loading of 10 MW m −2 [1], requiring an operating temperature of around 1300 K. W is currently the leading candidate material for these components due to its high melting temperature (3695 K), good thermal conductivity, resistance to sputtering and low activation under neutron irradiation [2,3]. The PFCs also receive an intense flux of 14 MeV neutrons and high energy He/H ions which introduce radiation damage and a significant amount of transmutation.…”

Advanced approach to the local structure reconstruction and theory validation on the example of the W L3-edge extended x-ray absorption fine structure of tungsten

“…Tungsten and its alloys are important materials for plasma-facing components in fusion reactors, which are expected to withstand sever damage of their microstructure when exposed to high-energy irradiation [1,2,3]. Therefore, an understanding of material properties on atomistic level, in particular the mechanisms of embrittlement, is a challenging task which can be achieved by combined use of proper theoretical and experimental methods.…”

High-Temperature Nano-Indentation Creep of Reduced Activity High Entropy Alloys Based on 4-5-6 Elemental Palette

“…The effect of temperature on the creep behavior of the R-HEAs was also investigated systematically. Stress exponent, activation volume, and activation energy of alloys at different combinations of temperature and loads were compared with pure tungsten (W), a reference metal used in nuclear reactors [33].…”