Thermohydraulics of rib-roughened helium gas running cooling channels for first wall applications

Ruck, Sebastian; Arbeiter, Frederik

doi:10.1016/j.fusengdes.2016.01.029

Cited by 13 publications

(5 citation statements)

References 24 publications

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“…The present analysis has been performed under the assumption that the parallel-cooled FW shares the same hydraulic design of the series-cooled FW; indeed, the th ermalhydraulics of a parallel FW was not designed yet, and hence it should be possible to further reduce the maximum temperature in the FW without increasing the mass flow rate: in this case, in fact, the FW would become a totally independent component, which could be redesigned in order to withstand such higher heat fluxes (we have not considered the adoption of suitable heat transfer promoters, already under investigation [21], or of the "half-monoblock FW" design proposed by the HCPB design team [22]). Note that the use of heat transfer promoters, such as those analyzed in [21], in the "series" cooling option could actually yield the same result of the parallel option: this would still lead to an increased pressure drop (up to 2.8× [21]), but without increasing the mass flow rate, limiting the increase in the compression power. Eventually, the different solutions could also be mixed, combining half-monoblock FW, heat transfer promoters and parallel FW [22].…”

Section: Results Of Getthem Whole Segment Analysismentioning

confidence: 99%

Thermal-Hydraulic Analysis of the EU DEMO Helium-Cooled Pebble Bed Breeding Blanket Using the GETTHEM Code

Froio

Cismondi²,

Savoldi

et al. 2018

IEEE Trans. Plasma Sci.

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The GEneral Tokamak THErmal-hydraulic Model -GETTHEM has been updated to the most recent version of the EU DEMO Helium-Cooled Pebble Bed (HCPB) Breeding Blanket (BB) design. The GETTHEM results are first benchmarked in a controlled case against the results of 3D Computational Fluid-Dynamics computations, showing an acceptable accuracy despite the inherent simplifications in the GETTHEM model. GETTHEM is then applied to the evaluation of the poloidal hot-spot temperature distribution in an entire BB segment, showing that the maximum temperature in the EUROFER structures overcomes the design limit of 550 °C by more than 50 °C in some Blanket Modules. A possible mitigation strategy is then proposed and analyzed, based on the idea of cooling the First Wall in parallel with the breeding zone, showing that this solution would allow having the EUROFER in its working temperature range in the entire segment, although at the expense of a larger pressure drop.

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Section: Results Of Getthem Whole Segment Analysismentioning

confidence: 99%

Thermal-Hydraulic Analysis of the EU DEMO Helium-Cooled Pebble Bed Breeding Blanket Using the GETTHEM Code

Froio

Cismondi²,

Savoldi

et al. 2018

IEEE Trans. Plasma Sci.

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“…The limited capability is caused by the relatively low thermal conductivity of the heat sink material Eurofer. Analyses so far show that this limit can be respected during normal operation [2][3]. However, in case of normal and off normal transients the heat flux on the FW can exceed well the above-mentioned limit.…”

Section: Introductionmentioning

confidence: 86%

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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“…Ribbed surfaces and other turbulence or secondary flow inducing channel inserts can increase the heat transfer coefficient by factor 3-4. Alternatives are tested by experiments and by high fidelity fluid dynamics simulations, like the detached eddy (DES) technique [41]. Available fabrication techniques, in line with the general fabrication steps of the FW are a key issue for this work.…”

Section: Blanket Fw and Limitersmentioning

confidence: 99%

Objectives and status of EUROfusion DEMO blanket studies

Boccaccini

Aiello

Aubert

et al. 2016

Fusion Engineering and Design

179

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The design of a DEMO reactor requires the design of a blanket system suitable of reliable T production and heat extraction for electricity production. In the frame of the EUROfusion Consortium activities, the Breeding Blanket Project has been constituted in 2014 with the goal to develop concepts of Breeding Blankets for the EU PPPT DEMO; this includes an integrated design and R&D program with the goal to select after 2020 concepts on fusion plants for the engineering phase. The design activities are presently focalized around a pool of solid and liquid breeder blanket with helium, water and PbLi cooling. Development of tritium extraction and control technology, as well manufacturing and development of solid and PbLi breeders are part of the Programme.

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Thermohydraulics of rib-roughened helium gas running cooling channels for first wall applications

Cited by 13 publications

References 24 publications

Thermal-Hydraulic Analysis of the EU DEMO Helium-Cooled Pebble Bed Breeding Blanket Using the GETTHEM Code

Thermal-Hydraulic Analysis of the EU DEMO Helium-Cooled Pebble Bed Breeding Blanket Using the GETTHEM Code

European DEMO first wall shaping and limiters design and analysis status

Objectives and status of EUROfusion DEMO blanket studies

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