Radiation Damage in Metallic Systems for Fusion Energy Applications

A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Metal Failure Analysis".

Deadline for manuscript submissions: closed (15 April 2025) | Viewed by 3116

Special Issue Editor


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Guest Editor
National Centre for Scientific Research "Demokritos", Agia Paraskevi, 15341 Athens, Greece
Interests: radiation damage; fusion materials; plasma–wall interaction; aerospace materials; alloys

Special Issue Information

Dear Colleagues,

Nuclear fusion offers a near-limitless, safe and clean energy source. Major challenge for the realization of fusion energy production is the development of suitable materials to endure the harsh fusion environment of intense thermomechanical stresses, and energetic particles of high fluxes. The most significant parts of experimental fusion reactors and energy producing future ones, such as the first wall, divertor, limiters and breeding blanket, are metals and metallic systems. Radiation damage in metallic systems deteriorates their properties and considerably reduces their lifetime.

In order to improve radiation resistance of metallic systems, both the understanding of the radiation damage based on experiments and multiscale materials modelling and the engineering properties of the materials after irradiations exposure are required.  

Thus, this Special Issue aims to invite papers addressing the characterization of metallic materials after irradiation under different conditions and energetic particles, defect production and their interaction, modelling of the radiation damage, and the thermo-mechanical response of metals after irradiation with respect to their perspective fusion application.   

Potential research contributions to this Special Issue can focus on the following:

(i) The understanding of radiation damage at the atomic-to-mesoscale and related modelling;

(ii) Use of characterization techniques, such as transmission electron microscopy, atom probe tomography, positron annihilation spectroscopy, and neutron and synchrotron X-ray scattering, for radiation damage assessment;

(iii) Theoretical and experimental investigations of the influence of radiation conditions on damage production and damage microstructure evolution;

(iv) Development of novel radiation resistant metas and alloys;

(v) Micro/macro-scale testing of irradiated metallic systems;

(vi) Impact of damage on performance and structural integrity.

Dr. Konstantina Mergia
Guest Editor

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Keywords

  • radiation damage
  • ion irradiation
  • neutron irradiation
  • multiscale modelling
  • plasma facing materials
  • structural materials
  • fusion materials

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Published Papers (2 papers)

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Research

28 pages, 5162 KiB  
Article
Post Neutron Irradiation Recovery and Recrystallization of ITER Grade Forged Tungsten Bar
by Dimitrios Papadakis, Efthimios Manios and Konstantina Mergia
Metals 2025, 15(2), 172; https://doi.org/10.3390/met15020172 - 8 Feb 2025
Viewed by 929
Abstract
Defect recovery and recrystallization studies of neutron-irradiated tungsten (W) addressing the microstructural evolution in relation to the mechanical properties, provide valuable insight into defect interactions and annihilation processes. Understanding these mechanisms can aid in the development of effective healing processes, potentially extending the [...] Read more.
Defect recovery and recrystallization studies of neutron-irradiated tungsten (W) addressing the microstructural evolution in relation to the mechanical properties, provide valuable insight into defect interactions and annihilation processes. Understanding these mechanisms can aid in the development of effective healing processes, potentially extending the lifespan of fusion reactor components. Additionally, this research helps to elucidate how neutron exposure alters the behaviour of materials used in fusion reactor components, contributing to improved design and durability. Within this framework, an ITER grade forged W bar was neutron irradiated to a damage of 0.21 displacements per atom at 600 °C and subsequently isochronally annealed from 700 up to 1550 °C in 50 °C steps. Irradiation causes the formation of dislocation loops and vacancy clusters as well as the formation of Re and Os transmutation products, leading to a 35% increase in hardness and a 23% increase in resistivity. The evolution of the microstructure after isochronal annealing is investigated through positron annihilation lifetime spectroscopy, X-ray diffraction, resistivity, and Vickers hardness measurements. The total dislocation line density as well as the number density and size of voids are determined as a function of annealing temperature. Specifically, the critical resolved stresses of dislocations and voids are correlated with their densities and distinct recovery stages are identified. The kinetics of defect annihilation are discussed in relation to the annealing temperature. Nearly complete dislocation annihilation occurs after annealing at 1300 °C, followed by complete void dissolution and recrystallization at 1450 °C. Full article
(This article belongs to the Special Issue Radiation Damage in Metallic Systems for Fusion Energy Applications)
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12 pages, 2629 KiB  
Article
Irradiation Hardening and Microstructure Study of MAX-Phase-Dispersion-Strengthened Vanadium Alloy under Self-Ion Irradiation
by Yinshu Zhao, Pengfei Zheng, Yaxia Wei, Hongtai Luo, Wei Qian, Guihang Zhang, Feng Li, Ming Zhang and Pengbo Zhang
Metals 2024, 14(2), 141; https://doi.org/10.3390/met14020141 - 24 Jan 2024
Cited by 4 | Viewed by 1715
Abstract
V-4Cr-4Ti alloy is one of the candidate structural materials for future fusion reactors due to its desirable characteristics. In our previous research, MAX-phase-dispersion-strengthened vanadium alloy (V-4Cr-4Ti-1.5Y-0.3Ti3SiC2), prepared through mechanical alloying, showed excellent thermal stability and creep resistance and was [...] Read more.
V-4Cr-4Ti alloy is one of the candidate structural materials for future fusion reactors due to its desirable characteristics. In our previous research, MAX-phase-dispersion-strengthened vanadium alloy (V-4Cr-4Ti-1.5Y-0.3Ti3SiC2), prepared through mechanical alloying, showed excellent thermal stability and creep resistance and was expected to have good radiation resistance. This study investigates the effects of 2.5 MeV V2+ ion irradiation on V-4Cr-4Ti-1.5Y-0.3Ti3SiC2 and V-4Cr-4Ti alloys at 500 °C, with peak damage of 0.8, 3.5, and 6.1 dpa. Transmission electron microscopy and nanoindentation were used to examine the changes in microstructure and hardness before and after irradiation. The microscopic analysis reveals that dispersed nanoparticles maintained good stability under irradiation. Defect clusters grow with increasing irradiation doses in both materials. The nanoindentation results show that V-4Cr-4Ti-1.5Y-0.3Ti3SiC2 has higher initial hardness and lower irradiation hardening, indicating better resistance to radiation hardening than V-4Cr-4Ti. This research serves as a valuable reference for the assessment of the irradiation resistance of Ti3SiC2-dispersion-strengthened V-4Cr-4Ti alloy. Full article
(This article belongs to the Special Issue Radiation Damage in Metallic Systems for Fusion Energy Applications)
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