Recent progress of vanadium-based alloys for fusion application

Jiang, Shaoning; Zhou, Fujie; Zhang, Gaowei; Yi, Xiaoou; Yu, Chang-Wang; Wang, Xiu‐Jie; Rao, Wei-Feng

doi:10.1007/s42864-021-00107-4

Cited by 14 publications

(8 citation statements)

References 84 publications

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“…Table 1. The contrast visibility conditions for the dislocation loops observed in 材料的辐照损伤的观察中已经大量发现 [4,13,30,31] .…”

Section: 钨中位错环类型及其对辐照损伤行为的影响mentioning

confidence: 99%

Analysis of dislocation characteristics and inside-outside contrasts in irradiated and annealed tungsten as a fusion reactor material

Xu¹,

Wan²

2023

Acta Phys. Sin.

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Tungsten is an important candidate plasma-facing material for fusion reactors. Its irradiation response, especially the post-irradiation annealing (PIA) behaviors need to be further investigated. In addition, the practice of the “inside-outside” contrast method for determining the characters of irradiation induced dislocation loops has not been applied frequently, and the current research serve as an example to present some practical considerations. In the current work, a tungsten thin-foil specimen was irradiated at 400℃ with 58 keV D ions to a final fluence of 1×1017cm-2, corresponding to a dose of ~0.1 dpa. The specimen was prepared through the electro-polishing method using a NaOH based electrolyte. The ion irradiation was carried out directly on the electro-polished specimen. The irradiated specimen was followed by isothermal annealing at 900℃ for 1 h. The as-irradiated and post-irradiation annealing modified defects were characterized with a transmission electron microscope (TEM) operated at 200 kV. The irradiation defects were characterized with TEM bright-field imaging for the same imaging field using different g vectors around the three major zone axis: the [001], [111], and [011] zone axis of the body-center cubic lattice of W. For each g vector, a ± g characterization was performed, and the corresponding contrast-extinctions and “inside-outside” contrasts of selected dislocation loops were identified. The indices of the g vectors around different zone axis were assigned consistently with regards to the Kikuchi map. As a result, the D ion irradiation induced a fine distribution of dislocation loops with an average size of 11.10 ±5.41 nm and a bulk density of 2.40×1022 /m3. Voids were not obviously observed. The post-irradiation annealing caused the increase of loop size and decrease of loop density, with numbers of 18.25 ±16.92 nm and 1.19×1022 /m3, respectively. Through the contrast-extinction analysis, the dislocation loops in the irradiated and annealed specimen were identified to be a /2<111> type dislocation loops. The post-irradiation annealing also caused the coalescence of large loops and formed large irregular-shaped dislocation loops. Voids with typical sizes of 1~2 nm were also observed in the annealed specimen. The PIA modified microstructure is consistent with the stage IV or stage V characteristics of classical PIA induced microstructures. Through the “one-step” inside-outside contrast method, the dislocation loops were identified as the interstitial type. The influcing factors for the “one-step” method were discussed and the importance of consistent indexing had been noted.

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“…Table 1. The contrast visibility conditions for the dislocation loops observed in 材料的辐照损伤的观察中已经大量发现 [4,13,30,31] .…”

Section: 钨中位错环类型及其对辐照损伤行为的影响mentioning

confidence: 99%

Analysis of dislocation characteristics and inside-outside contrasts in irradiated and annealed tungsten as a fusion reactor material

Xu¹,

Wan²

2023

Acta Phys. Sin.

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“…This has a very attractive consequence, namely that without Be, the system is freed from the radiological problems arising from its toxicity. Nevertheless, this concept has two main problems: the T recovery of liquid lithium and the MHD pressure drop [ 90 , 93 ].…”

Section: Structural Materialsmentioning

confidence: 99%

“…During the fabrication and processing of these alloys, impurity levels (e.g., C, O and N) must be carefully controlled due to possible degradation of mechanical properties. Based on these considerations, a protective or high-vacuum atmosphere is normally used to prepare the alloy, whose maximum operating temperature is 700 °C [ 58 , 91 , 93 ].…”

Section: Structural Materialsmentioning

confidence: 99%

“…However, their hardening below 400 °C is related to the formation of point defects and clusters. Additionally, it has been found that the dissolution of Ti-rich precipitates may affect the hardness of the welded joint [ 93 ].…”

Section: Structural Materialsmentioning

confidence: 99%

“…Research on coating and corrosion, irradiation damage or H isotope retention has also progressed considerably. However, critical problems related to high temperature operation and low temperature embrittlement of the material remain to be solved [ 90 , 93 ].…”

Section: Structural Materialsmentioning

confidence: 99%

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Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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Kyoto Fusioneering’s Mission to Accelerate Fusion Energy: Technologies, Challenges and Role in Industrialisation

Baus

Barron²,

D’Angiò³

et al. 2023

J Fusion Energ

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Making fusion power viable both technologically and commercially has been a challenge for decades due to the great complexity of the science and engineering challenges. In recent years, changes in both government policies and the emergence of private fusion companies have ushered a newfound push to accelerate fusion energy development. Kyoto Fusioneering (KF) is a privately funded fusion engineering start-up, founded to accelerate the development of high performance, commercially viable technologies that will be required for a fusion power plant, specifically those associated with heating and current drive systems, power generation, and the tritium fuel cycle. The company is focused on supporting the rapid expansion of the budding fusion industry. This paper provides a high-level description of some of the technical and industrial challenges it is tackling in developing a commercial fusion reactor, in particular in relation to: plasma heating with gyrotrons, tritium handling and breeding, energy conversion, and fusion materials. It provides an overview of KF's activities in finding solutions to challenges in each of these areas, including via its new testing facility now under construction, UNITY (Unique Integrated Testing Facility). KF’s core capabilities and areas of R&D focus are discussed, with reference to how they benefit the development of a new fusion industry as a whole and bring the technology closer to industrialisation, including via UNITY and through collaboration with external partners. The importance of industrialisation and subsequently commercialisation is also discussed, through KF’s assessment of the newly emerging fusion ecosystem, and where KF as a company sits within it.

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Recent progress of vanadium-based alloys for fusion application

Cited by 14 publications

References 84 publications

Analysis of dislocation characteristics and inside-outside contrasts in irradiated and annealed tungsten as a fusion reactor material

Analysis of dislocation characteristics and inside-outside contrasts in irradiated and annealed tungsten as a fusion reactor material

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Kyoto Fusioneering’s Mission to Accelerate Fusion Energy: Technologies, Challenges and Role in Industrialisation

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