Optimization of the first wall for the DEMO water cooled lithium lead blanket

Aubert, Julien; Aiello, G.; Bachmann, Christian; Maio, P.A. Di; Giammusso, R.; Puma, A. Li; Morin, Alexandre; Tincani, A.

doi:10.1016/j.fusengdes.2015.01.008

Cited by 27 publications

(6 citation statements)

References 2 publications

(9 reference statements)

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“…A single module segmentation approach is adopted with the blanket being segmented only in the toroidal direction [2]. To preserve the Eurofer mechanical properties, the steel bulk and interface temperature must not exceed 823 K (550 • C) during normal operation [3]. Four alternative configurations are currently being studied to identify advantages and key issues, in order to select the reference configuration that will be further developed in the next years.…”

Section: Introductionmentioning

confidence: 99%

MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization

Tassone

Caruso

Giannetti

et al. 2019

Fusion Engineering and Design

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In the Water-Cooled Lithium Lead (WCLL) blanket, a critical problem faced by the design is to ensure that the breeding zone (BZ) is properly cooled to avoid the loss of mechanical properties in the structural materials. CFD simulations are performed using ANSYS CFX to assess the cooling system performances accounting for the magnetic field effect in the sub-channel closest to the first wall (FW). Here, intense buoyancy forces (Gr ≈ 10 10) interact with the pressure-driven flow (Re ≈ 10 3) in a MHD mixed convection regime. A constant magnetic field, parallel to the toroidal direction, is assumed with Ha = 8550. The walls bounding the channel and the water pipes are modeled as perfectly conducting. The magnetic field is found to dampen the velocity fluctuations triggered by the buoyancy forces and the flow is similar to a forced convection regime. The PbLi heat transfer coefficient is reduced to one-third of its ordinary hydrodynamic value and, consequently, hot-spots close to the FW are observed, where T Max ≈ 1000 K. Optimization strategies for the BZ cooling system layout are proposed and implemented in the CFD model, thus fulfilling the design criterion.

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Section: Introductionmentioning

confidence: 99%

MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization

Tassone

Caruso

Giannetti

et al. 2019

Fusion Engineering and Design

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“…The steady-state BB thermal condition also depends on the outlet temperature of the BB coolant: ~328 • C in case of water and ~500 • C in case of helium. In the verification of the BB supports we considered the more extreme temperature state in the range ~[300-500], [19], established in the case of helium, see Fig. 15.…”

Section: Thermal Conditionsmentioning

confidence: 99%

Mechanical support concept of the DEMO breeding blanket

Bachmann

Gliss

Härtl

et al. 2021

Fusion Engineering and Design

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“…This may prove to be an appropriate level for a uniform, normal scenario load; but peaked loads due to magnetic field ripple, plasma transients, wall dimensional intolerance, etc, could be an order of magnitude higher. Baseline FW concepts are based on helium and water cooling of EUROFER channels [10][11][12][13][14], which are reported to have heat flux limits of about 1 MW/m 2 and 1.5 MW/m 2 , respectively. Importantly, these limits are based on engineering analyses however they neither account for irradiated material properties nor the presence of the tungsten armour.…”

Section: Fw Conceptsmentioning

confidence: 99%

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

Barrett

Ellwood

Pérez

et al. 2016

Fusion Engineering and Design

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The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while also allowing sufficient neutron transmission to the tritium breeding blankets. A systems approach using advanced numerical analysis is vital to realising viable solutions for these first wall and divertor PFCs. Here, we present the system requirements and describe bespoke thermo-mechanical and thermo-hydraulic assessment procedures which have been used as tools for design. The current first wall and divertor designs are overviewed along with supporting analyses. The PFC solutions employed will necessarily vary around the wall, depending on local conditions, and must be designed in an integrated manner by analysis and physical testing.

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Optimization of the first wall for the DEMO water cooled lithium lead blanket

Cited by 27 publications

References 2 publications

MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization

MHD mixed convection flow in the WCLL: Heat transfer analysis and cooling system optimization

Mechanical support concept of the DEMO breeding blanket

Progress in the engineering design and assessment of the European DEMO first wall and divertor plasma facing components

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