Status of the EU DEMO HCLL breeding blanket design development

Aubert, Julien; Aiello, G.; Arena, P.; Barrett, T.; Boccaccini, Lorenzo Virgilio; Bongioví, G.; Boullon, Rémi; Cismondi, F.; Critescu, Ion; Domalapally, Phani Kumar; Forest, Laurent; Jaboulay, Jean-Charles; Kiss, Béla; Morin, Alexandre; Peyraud, Justine; Porempovics, G.; Utili, Marco; Vála, L.

doi:10.1016/j.fusengdes.2018.04.133

Cited by 29 publications

(14 citation statements)

References 10 publications

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“…The MHD pressure drop in the blanket itself is relatively low but that in the feeding ducts is expected to be high due to higher velocities compared to the blanket channels. Reference [29] reports maximum pressure drop of 0.332 MPa in outboard segment and 0.230 MPa in inboard segment of the EU DEMO HCLL blanket. Tritium permeation from PbLi into He flows is a serious safety issue for all HCLL blankets.…”

Section: Examples Of Lm Breeding Blankets and Their Pressure Dropmentioning

confidence: 99%

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Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

Smolentsev

2021

Fluids

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In blankets of a fusion power reactor, liquid metal (LM) breeders, such as pure lithium or lead-lithium alloy, circulate in complex shape blanket conduits for power conversion and tritium breeding in the presence of a strong plasma-confining magnetic field. The interaction of the magnetic field with induced electric currents in the breeder results in various magnetohydrodynamic (MHD) effects on the flow. Of them, high MHD pressure losses in the LM breeder flows is one of the most important feasibility issues. To design new feasible LM breeding blankets or to improve the existing blanket concepts and designs, one needs to identify and characterize sources of high MHD pressure drop, to understand the underlying physics of MHD flows and to eventually define ways of mitigating high MHD pressure drop in the entire blanket and its sub-components. This article is a comprehensive review of earlier and recent studies of MHD pressure drop in LM blankets with a special focus on: (1) physics of LM MHD flows in typical blanket configurations, (2) development and testing of computational tools for LM MHD flows, (3) practical aspects associated with pumping of a conducting liquid breeder through a strong magnetic field, and (4) approaches to mitigation of the MHD pressure drop in a LM blanket.

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Section: Examples Of Lm Breeding Blankets and Their Pressure Dropmentioning

confidence: 99%

“…, where m = a/s. After substituting Equations (28) and (29) into Equations (24) and 26, the momentum and the energy equation become independent of x:…”

Section: Mhd Flows With Buoyancy Effectsmentioning

confidence: 99%

Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

Smolentsev

2021

Fluids

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“…Within the framework of HCLL design activities [5], 3 different concepts (Optimized Conservative, Advanced [6,7], Advanced-Plus [8]) have been assessed. All the concepts use Eurofer steel as structural material, Helium at the pressure of 8 MPa as coolant and the eutectic alloy Pb-15.7Li enriched at 90% in 6Li as breeder, neutron multiplier and tritium carrier.…”

Section: Hcll "Optimized Conservative" Conceptmentioning

confidence: 99%

On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

Bongioví

Aiello

Aubert

et al. 2018

Fusion Engineering and Design

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Within the framework of EUROfusion R&D activities a research campaign has been performed at CEA-Saclay, in close collaboration with the University of Palermo, in order to investigate thermal and thermomechanical performances of the "Optimized Conservative" concept of DEMO Helium-Cooled Lithium Lead breeding blanket (HCLL). Attention has been paid to the HCLL outboard equatorial module (OEM) when subjected to the steady state nominal loading scenario. To this purpose three simplified 3D models, characterized by an increasing level of detail, have been set-up taking into account, firstly, a single radial-toroidal slice, then a basic module geometric unity composed by two adjacent slices and adding, lastly, the peripheral poloidal region. This latter 3D model has allowed the assessment of the Caps potential influence on the module thermal and thermomechanical behaviour.For each investigated 3D model, thermal and thermomechanical analyses have been performed and a stress linearization procedure has been carried out in order to verify the fulfilment of the criteria prescribed by the RCC-MRx 2015 code. The study has been performed adopting a numerical approach, based on the Finite Element Method (FEM), and adopting the Siemens NX v. 10.0 software in order to discretize the geometric domain, whereas thermal and thermomechanical calculations have been carried out using the Cast3M 2015 FEM code.The obtained results, herewith reported and critically discussed, allow predicting a good thermal and mechanical behaviour of the "Optimized Conservative" concept of DEMO HCLL OEM, even if some small modifications to the module cooling scheme should be performed in order to avoid the insurgence of hotspots where temperature is slightly above the Eurofer limit temperature (550 °C). This will entail, from the mechanical point of view, a reduction of the secondary stress amount which is the main responsible of the failure in RCC-MRx criteria verification within First Wall-Side Wall bend region.

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“…The heat transfer between PbLi and water plays an important role in fusion technology because three out of four candidate EU breeding blankets [1] rely on this heavy liquid metal (HLM) as breeder and/or coolant [2][3] [4]. The PbLi/water heat exchangers or steam generators are envisaged in the PbLi loop, where the PbLi main issues are investigated [5].…”

Section: Introductory Remarksmentioning

confidence: 99%

Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment

Narcisi

Giannetti

Martelli

et al. 2019

Fusion Engineering and Design

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The Power Conversion System (PCS) is designed to remove heat from PHTSs and to ensure an efficient thermal power conversion to electricity. The Dual Coolant Lithium Lead (DCLL) breeding blanket concept is based on two coolant fluids flowing into two independent circuits: a helium circuit, cooling first wall, and a PbLi circuit, removing heat generated in the breeding zone (BZ). The steam generator connected to PbLi system is prototypical, therefore experimental tests are required to demonstrate technological feasibility, performances and to assess capability of codes in providing reliable simulations of the behavior. The objective of the activity is to support the design of a PbLi/water steam generator and the experimental campaign defining test matrix and expected outcomes. Two steam generator configurations are analyzed using a modified version of RELAP5/Mod3.3 (R5): the Steam Generator Bayonet Tube (SGBT) and the Helical Coil Steam Generator (HCSG). The experimental mock-up of these configurations will be tested in CIRCE facility at ENEA Brasimone RC, which is currently the largest and most powerful heavy liquid metal facility in operation. Finally, numerical simulations are employed to support the design of the mock-ups and the experimental campaign.

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Status of the EU DEMO HCLL breeding blanket design development

Cited by 29 publications

References 10 publications

Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

Physical Background, Computations and Practical Issues of the Magnetohydrodynamic Pressure Drop in a Fusion Liquid Metal Blanket

On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO

Steam Generator mock-up preliminary design suitable for Pb-Li technology demonstration and code assessment

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