The design of the ITER first wall panels

Mitteau, R.; Calcagno, B.; Chappuis, P.; Eaton, R.; Gicquel, S.; Chen, J.; Labusov, A.; Martín, A.; Merola, M.; Raffray, R.; Ulrickson, M.; Zacchia, F.

doi:10.1016/j.fusengdes.2013.05.030

Cited by 49 publications

(19 citation statements)

References 5 publications

(2 reference statements)

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“…This will be made with a view to expected inhomogeneous heat loads. As an example, the largest segment of a beryllium first wall castellation in ITER has a maximum lateral dimension of 50 mm × 50 mm [45,46]. In the course of our industrial up-scale study, we will use these dimensions as a merit, trying to explore the feasibility of larger SMART samples at the same time.…”

Section: Industrial Up-scale and Interfacesmentioning

confidence: 99%

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: Industrial Up-scale and Interfacesmentioning

confidence: 99%

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Litnovsky

Klein

Tan

et al. 2021

Metals

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“…To allow handling interface at the front of the limiter similar solution to that of ITER is sought [23], whereby the central part of the limiter, where the interface is located, would have to be shadowed by the PFCs.…”

Section: Inboard Mid-plane Limiter (Iml)mentioning

confidence: 99%

European DEMO first wall shaping and limiters design and analysis status

Vízváry

Bachmann²,

Barrett

et al. 2020

Fusion Engineering and Design

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“…As stated above, shaping of the wall in 3-D is essential to manage charged particle wall loads. In ITER the wall is a wall-limiter split into individual water-cooled high heat flux (HHF) panels [5], and each panel is shaped to effectively spread the power arising from plasma start-up and burn phases (normal and off-normal transients) and in order to protect panel exposed edges [6]. Further shaping requirements arise as the wall must be robust against misalignment, for example due to realistic assembly and fabrication tolerances, thermal expansion and magnetic eccentricity.…”

Section: Wall Shapingmentioning

confidence: 99%

Designs and technologies for plasma-facing wall protection in EU DEMO

et al. 2019

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The EU DEMO plasma is almost completely enveloped by large breeding blanket segments for tritium breeding and power extraction. Shaping of the blanket plasma-facing wall in 3-D may prove to be essential, but this strategy alone is not sufficient to protect against anticipated transient plasma events. The high heat flux wall-limiter approach used in ITER is not thought to be viable in a tritium self-sufficient power reactor, and so in EU DEMO wall protection using discrete limiters is pursued. Two types of discrete limiter are described in this paper. One is an equatorial port limiter designed to handle the power during the plasma start-up phase making use of water-cooled tungsten/CuCrZr monoblock technology. The second is the upper limiter, featuring a plasma-facing component designed specifically for extreme transient loading due to a vertical displacement event. The heat flux channeling and thermal barrier features of this design are shown to considerably reduce CuCrZr pipe temperature, and so reduce the likelihood of catastrophic failure. A preliminary neutronic calculation has shown that the impact of these discrete limiters on overall tritium breeding ratio is relatively low.

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The design of the ITER first wall panels

Cited by 49 publications

References 5 publications

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

Advanced Self-Passivating Alloys for an Application under Extreme Conditions

European DEMO first wall shaping and limiters design and analysis status

Designs and technologies for plasma-facing wall protection in EU DEMO

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