WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Nevo, Alessandro Del; Martelli, Emanuela; Agostini, P.; Arena, P.; Bongioví, G.; Caruso, Gianfranco; Gironimo, Giuseppe Di; Maio, P.A. Di; Eboli, Marica; Giammusso, R.; Giannetti, Fabio; Giovinazzi, Andrea; Mariano, G.; Moro, F.; Mozzillo, Rocco; Tassone, Alessandro; Rozzia, Davide; Tarallo, Andrea; Tarantino, M.; Utili, Marco; Villari, R.

doi:10.1016/j.fusengdes.2017.03.020

Cited by 93 publications

(15 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…GETTHEM currently comprises models for the cooling loops of the Helium-Cooled Pebble Bed (HCPB) [4] and Water-Cooled Lithium-Lead (WCLL) [5] Breeding Blanket (BB) concepts and has been already successfully applied to the Manuscript received November 13,2017 This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No. 633053.…”

Section: Introductionmentioning

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.

View full text Add to dashboard Cite

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.

show abstract

Section: Introductionmentioning

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.

View full text Add to dashboard Cite

show abstract

“…were not yet available, the composition used here corresponds to that optimized for the thicker 2015 DEMO blankets [20,21].…”

Section: Preliminary Calculation Of the Impact On Tritium Breedingmentioning

confidence: 99%

“…Two blanket module configurations are analysed, 1) Helium-Cooled Pebble-Bed (HCPB 2015 v3 [20]) and 2) Water-Cooled Lead-Lithium (WCLL BB 2015 [21]). Solid models representing the outer equatorial port limiter and the upper port limiter were generated using CAD software (see Figure 6) and converted into a MCNP constructive solid geometry using the McCad conversion tool [22].…”

Section: Preliminary Calculation Of the Impact On Tritium Breedingmentioning

confidence: 99%

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

et al. 2019

View full text Add to dashboard Cite

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.

show abstract

“…The breeding blanket provides the functions of breeding tritium, removing nuclear heat from the plasma, and shielding of the vacuum vessel and other components from the direct neutron flux. The water-cooled lithium-lead (WCLL) blanket design [8,9] is a set of modular boxes that form the inner wall of the tokamak, through which LiPb flows slowly to generate tritium. A set of coolant pipes manufactured from Eurofer-97 carry water in a radialtoroidal direction to extract the heat deposited (Fig.…”

Section: Plant Descriptionmentioning

confidence: 99%

The possible effect of high magnetic fields on the aqueous corrosion behaviour of Eurofer

Burrows

Baron-Wiechec

Harrington

et al. 2018

Fusion Engineering and Design

View full text Add to dashboard Cite

In defining the corrosion control requirements for DEMO, the impact of the mixed Eurofer-97/AISI 316 steel system and plant specific effects should be considered throughout, in particular, the effect of the intense magnetic fields present. A substantial amount of data related to corrosion resistance of structural materials is available for industrial applications in fission, but applies to different materials and neutronic conditions. Experimental work is being carried out under the DEMO Breeding Blanket Project of the EUROfusion programme, which will further develop the understanding of irradiation effects. However, there is very limited information regarding magnetic field-assisted corrosion under conditions relevant for the fusion environment readily available in the literature. This work reviews current knowledge and progress in establishing the possible influence of the intense magnetic field on corrosion behaviour of the main structural material, Eurofer-97, in the breeding blanket. To support the relevance of this problem statement, preliminary corrosion experimental results of Eurofer-97 coupons, obtained by using a simple apparatus that allows exposure to a magnetic field intensity of 0.88 T and temperatures up to 80°C in water at atmospheric pressure, are presented as an initial qualitative investigation of possible magnetic field related effects.

show abstract

WCLL breeding blanket design and integration for DEMO 2015: status and perspectives

Cited by 93 publications

References 8 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

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

The possible effect of high magnetic fields on the aqueous corrosion behaviour of Eurofer

Contact Info

Product

Resources

About