Standardized integration of ITER diagnostics Equatorial Port Plugs

Guirao, J.; Walsh, Michael J.; Udintsev, V. S.; Iglesias, Silvia; Giacomin, T.; Bertalot, L.; Shigin, P.; Kochergin, M. M.; Alexandrov, E.; Zvonkov, A. V.; Ivantsivskiy, M.; Fang, Tongzhen; Hu, Qiya; Rodríguez, Eduardo; Ordieres, J.; Juárez, R.; Blanchard, A.

doi:10.1016/j.fusengdes.2019.02.126

Cited by 17 publications

(3 citation statements)

References 2 publications

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“…WC is not preferred due to its heavy mass, which causes problems in the remote maintenance. B 4 C is an attractive option as it is also used in the shielding material for the diagnostics ports of ITER [36].…”

Section: Nuclear Analysesmentioning

confidence: 99%

The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

et al. 2023

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Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO program to optimize the helium cooled pebble bed (HCPB) breeding blanket. A gate review was conducted for the entire European DEMO program at the conclusion of the PCD phase. This article presents a summary of the design evolution and the rationale behind the HCPB breeding blanket concept for the European DEMO. The main performance metrics, including nuclear, thermal hydraulics, thermal mechanical, and tritium permeation behaviors, are reported. These figures demonstrate that the HCPB breeding blanket is a highly effective tritium-breeding and robust driver blanket concept for the European DEMO. In addition, three alternative concepts of interest were explored. Furthermore, this article outlines the upcoming design and R&D activities for the HCPB breeding blanket during the Concept Design phase (2021–2027).

show abstract

Section: Nuclear Analysesmentioning

confidence: 99%

The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

et al. 2023

View full text Add to dashboard Cite

show abstract

“…WC is not preferred due to its heavy mass, causing problem on remote maintenance. B4C is an attractive option as it is also used in the shielding material for the diagnostics ports of ITER [32].…”

Section: Nuclear Analysesmentioning

confidence: 99%

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

Zhou¹,

Hernández²,

Pereslavtsev³

et al. 2023

Preprint

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Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO programme to optimize the Helium Cooled Pebble Bed (HCPB) breeding blanket. A Gate Review was conducted for the entire European DEMO programme at the conclusion of the PCD phase. This article presents a summary of the design evolution and the rationale behind the HCPB breeding blanket concept for the European DEMO. The main performance metrics, including nuclear, thermal hydraulics, thermal mechanical, and tritium permeation behaviors, are reported. These figures demonstrate that the HCPB breeding blanket is a highly effective tritium-breeding and robust driver blanket concept for the European DEMO. In addition, three alternative concepts of interest were explored. Furthermore, this article outlines the upcoming design and R&D activities for the HCPB breeding blanket during the Concept Design phase (2021-2027).

show abstract

Section: Nuclear Analysesmentioning

confidence: 99%

The European DEMO HCPB Breeding Blanket: Design Status at the Conclusion of Pre-Concept Design Phase

Zhou¹,

Hernández²,

Pereslavtsev³

et al. 2023

Preprint

View full text Add to dashboard Cite

Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO programme to optimize the Helium Cooled Pebble Bed (HCPB) breeding blanket. A gate review was conducted for the entire European DEMO programme at the conclusion of the PCD phase. This article presents a summary of the design evolution and the rationale behind the HCPB breeding blanket concept for the European DEMO. The main performance metrics, including nuclear, thermal hydraulics, thermal mechanical, and tritium permeation behaviors, are reported. These figures demonstrate that the HCPB breeding blanket is a highly effective tritium-breeding and robust driver blanket concept for the European DEMO. In addition, three alternative concepts of interest were explored. Furthermore, this article outlines the upcoming design and R&D activities for the HCPB breeding blanket during the Concept Design phase (2021-2027).

show abstract

Standardized integration of ITER diagnostics Equatorial Port Plugs

Cited by 17 publications

References 2 publications

The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

The European DEMO HCPB Breeding Blanket: Design Status at the Conclusion of Pre-Concept Design Phase

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