Evaluation of the high temperature oxidation of W-Cr-Zr self-passivating alloys

Tan, Xiao–Yue; Klein, F.; Litnovsky, A.; Wegener, T.; Schmitz, J.; Linsmeier, Ch.; Coenen, J. W.; Breuer, U.; Rasiński, M.; Li, P.; Luo, Lai Ma; Wu, Yucheng

doi:10.1016/j.corsci.2018.11.022

Cited by 28 publications

(9 citation statements)

References 21 publications

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“…The first step in the production is the mechanical alloying of the source W, Cr and Y powders. This step is treated as virtually inevitable and used by all research groups working on self-passivating alloys worldwide [11,22,[24][25][26][27][28]. The following step is the sintering of the alloyed powder.…”

Section: Oxidation Performancementioning

confidence: 99%

“…The ongoing investigations reveal, e.g., a potential for an improvement via the further optimization of the FAST sintering. Dedicated research [28,43,44] demonstrates, e.g., a significant effect imposed by the sintering current on the microstructure of the alloy. Exploratory studies aiming at further optimizing of the thermo-mechanical properties of SMART systems are an important ongoing research activity.…”

Section: Thermo-mechanical Qualificationmentioning

confidence: 99%

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Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Litnovsky

Klein

Tan

et al. 2021

Metals

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Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials for the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operation of the future power plant. Modern SMART materials contain chromium as a passivating element, yttrium as an active element and a tungsten base matrix. An overview of the research and development program on SMART materials is presented and all major areas of the structured R&D are explained. Attaining desired performance under accident and regular plasma conditions are vital elements of an R&D program addressing the viability of the entire concept. An impressive more than 104-fold suppression of oxidation, accompanied with more than 40-fold suppression of sublimation of tungsten oxide, was attained during an experimentally reproduced accident event with a duration of 10 days. The sputtering resistance under DEMO-relevant plasma conditions of SMART materials and pure tungsten was identical for conditions corresponding to nearly 20 days of continuous DEMO operation. Fundamental understanding of physics processes undergone in the SMART material is gained via fundamental studies comprising dedicated modeling and experiments. The important role of yttrium, stabilizing the SMART alloy microstructure and improving self-passivating behavior, is under investigation. Activities toward industrial up-scale have begun, comprising the first mechanical alloying with an industrial partner and the sintering of a bulk SMART alloy sample with dimensions of 100 mm × 100 mm × 7 mm using an industrial facility. These achievements open the way to further expansion of the SMART technology toward its application in fusion and potentially in other renewable energy sources such as concentrated solar power stations.

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Section: Oxidation Performancementioning

confidence: 99%

Section: Thermo-mechanical Qualificationmentioning

confidence: 99%

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Litnovsky

Klein

Tan

et al. 2021

Metals

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“…[85,86] A new system under consideration is currently W-Cr-Zr. [101,102] The general need for self-passivating materials was identified early on and is embedded in a general effort to study and develop new solutions for materials in fusion reactors, [1,5,42] and hence has also lead to a wide international visibility. [103] For an integrated approach, combination with composite materials also ought to be considered.…”

Section: W Alloysmentioning

confidence: 99%

“…The detailed understanding of the underlying oxidation and sublimation mechanisms is also important . A new system under consideration is currently W–Cr–Zr …”

Section: Materials For Fusionmentioning

confidence: 99%

Fusion Materials Development at Forschungszentrum Jülich

Coenen

2020

Adv Eng Mater

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Material issues pose a significant challenge for the design of future fusion reactors. From a historic point of view, the material mix used for the first wall of a fusion reactor has continually evolved, from original steel vessels to carbon and other low-Z materials such as beryllium to tungsten as the primary candidate for a reactor's first wall armor and divertor material. For materials considered for fusion applications, a highly integrated approach is necessary. Resilience against neutron damage, good power exhaust, and oxidation resistance during accidental air ingress are design relevant issues while deciding on new materials or improving upon baseline materials. Neutron-induced effects, e.g., transmutation adding to embrittlement, retention, and changes to thermomechanical properties, are crucial to material performance. In this contribution, the recent progress (2013-2019) in fusion materials development for current and future fusion devices, at Forschungszentrum Jülich GmbH, with activities focussing on advanced materials and their characterization is given. It is a continuation and extension of the work given by Coenen et al.

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“…This means that PFMs are required to possess at least a good resistance to particle sputtering, good thermal conductivity and high melting point. Tungsten (W) with decision advantages of the highest melting point (approximately 3410 °C) in all metals, high density, excellent thermal conductivity (approximately 173 W m −1 K −1 at room temperature), high sputtering threshold and low tritium retention is considered as one main promising candidate material for PFMs in the future fusion reactor [the demonstration reactor or China fusion engineering testing reactor (CFTER)] [7,8].…”

Section: Introductionmentioning

confidence: 99%

Manufacturing of tungsten and tungsten composites for fusion application via different routes

2019

Tungsten

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Tungsten is a refractory metal with the highest melting point of all metals, which is considered as a promising candidate material for plasma-facing materials in the future fusion reactor. However, tungsten faces several challenges from intrinsic embrittlement, irradiation embrittlement and recrystallization embrittlement during the operation of the fusion reactor. To satisfy the fusion engineering application, an advanced tungsten material with the fine grain and dense microstructure is required and developed. This paper briefly introduces the application background of the tungsten materials and mainly illustrates a series of common techniques for manufacturing advance tungsten materials, such as powder preparation technologies, bulk densification techniques, continuous processing technologies and the coating and additive manufacturing technologies. Furthermore, the development prospects for manufacturing techniques of tungsten materials are also presented in the end. Considering the tungsten materials employed in the fusion engineering application, combining these scalable techniques of the wet-chemical method, pressureless sintering and continuous deformation processing techniques would be the possible research and development routes to realize the manufacture of the advanced tungsten materials.

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Evaluation of the high temperature oxidation of W-Cr-Zr self-passivating alloys

Cited by 28 publications

References 21 publications

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Fusion Materials Development at Forschungszentrum Jülich

Manufacturing of tungsten and tungsten composites for fusion application via different routes

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