Materials and design of the European DEMO blankets

Boccaccini, L.V.; Giancarli, L.; Janeschitz, G.; Hermsmeyer, S.; Poitevin, Y.; Cardella, A.; Diegele, E.

doi:10.1016/j.jnucmat.2004.04.125

Cited by 80 publications

(49 citation statements)

References 23 publications

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“…On the other hand, within Fusion, one of the most promising designs for DEMO is foreseen to have liquid lead-lithium eutectic as tritium breeder [4].…”

Section: Introductionmentioning

confidence: 99%

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Bosch¹,

Bosch²,

Sapundjiev³

et al. 2008

Journal of Nuclear Materials

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The susceptibility of the ferritic-martensitic steels T91 and EUROFER97 to liquid metal embrittlement (LME) in lead alloys has been examined under various conditions. T91, which is currently the most promising candidate material for the high temperature components of the future accelerator driven system (ADS) was tested in liquid lead bismuth eutectic (LBE), whereas the reduced activation steel, EUROFER97 which is under consideration to be the structural steel for fusion reactors was tested in liquid lead lithium eutectic. These steels, similar in microstructure and mechanical properties in the unirradiated condition were tested for their susceptibility to LME as function of temperature (150-450°C) and strain rate (1 Â 10 À3 -1 Â 10 À6 s À1 ). Also, the influence of pre-exposure and surface stress concentrators was evaluated for both steels in, respectively, liquid PbBi and PbLi environment. To assess the LME effect, results of the tests in liquid metal environment are compared with tests in air or inert gas environment. Although both unirradiated and irradiated smooth ferritic-martensitic steels do not show any or little deterioration of mechanical properties in liquid lead alloy environment compared to their mechanical properties in gas as function of temperature and strain rate, pre-exposure or the presence of surface stress concentrators does lead to a significant decrease in total elongation for certain test conditions depending on the type of liquid metal environment. The results are discussed in terms of wetting enhanced by liquid metal corrosion or crack initiation processes.

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“…On the other hand, within Fusion, one of the most promising designs for DEMO is foreseen to have liquid lead-lithium eutectic as tritium breeder [4].…”

Section: Introductionmentioning

confidence: 99%

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Bosch¹,

Bosch²,

Sapundjiev³

et al. 2008

Journal of Nuclear Materials

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“…Un-irradiated material properties were considered. It is assumed to have materials homogeneous, uniform and isotropic and their thermo-mechanical properties depend uniquely on temperature as indicated in [16][17][18][19]. Finally, EUROFER mechanical behaviour has been simulated adopting a linear elastic model.…”

Section: Materials Propertiesmentioning

confidence: 99%

“…Finally, EUROFER mechanical behaviour has been simulated adopting a linear elastic model. According to [16][17][18][19] these assumptions may be considered a reasonable approximation given the early state in the WCLL blanket design development.…”

Section: Materials Propertiesmentioning

confidence: 99%

Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module

et al. 2014

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Within the framework of DEMO R&D activities, a research cooperation has been launched between ENEA-Brasimone, CEA-Saclay and the University of Palermo to investigate the thermo-mechanical behaviour of the outboard equatorial module of the DEMO1 Water-Cooled Lithium Lead (WCLL) blanket, both under normal operation and over-pressurization steady state scenarios. The research campaign has been carried out following a theoretical-computational approach based on the finite element method (FEM) and adopting a qualified commercial FEM code. In particular, two different three-dimensional FEM models of the WCLL blanket module have been set-up to be used for normal operation and over-pressurization analysis, respectively. The former reproduces realistically the WCLL blanket module central poloidal–radial region, including one breeder cell in the toroidal direction and all the five cells in the radial one. The latter simulates the entire module segment box, without including the breeder and its cooling tubes. Two set of uncoupled steady state thermo-mechanical analyses have been carried out with reference to the investigated loading scenarios. In particular, under normal operation scenario (level A) the module has been supposed to undergo both 15.5 MPa coolant pressure on its cooling channels walls and thermal deformations due to the flat-top plasma operational state thermal field, while under over-pressurization scenario (level D) it has been assumed to experience 15.5 MPa coolant pressure on its segment box internal walls while operating at normal operation thermal level. Results obtained are presented and critically discussed according to the SDC IC code

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“…Physical and chemical properties of liquid metals (LiPb eutectic) as for instance the low melting and high boiling temperatures, the chemical inertness with water or oxygen, makes LiPb favourable candidates as core coolant of fusion reactor blanket. The liquid LiPb breeder blanket concept has been explored extensively in the EU, US and China as a design option for DEMO blankets for fusion power reactors [1][2][3][4][5][6] and TBM (test blanket module) concepts (HCLL-the helium-cooled lithium lead, DCLL-the dual-cooled lithium lead) to be tested in ITER due to their potential with regard to economy and safety [7][8][9]. In China, two options for liquid LiPb blanket concepts with their own features and design details of the FDS-II, DLL and SLL breeder blankets, are adopted [10][11][12][13].…”

Section: Introductionmentioning

confidence: 99%

Analysis of flow and MHD pressure drop in liquid metal LiPb duct with flow channel inserts

Wang

Chan

Zhu

2011

Fusion Engineering and Design

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Materials and design of the European DEMO blankets

Cited by 80 publications

References 23 publications

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Liquid metal embrittlement susceptibility of ferritic–martensitic steel in liquid lead alloys

Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module

Analysis of flow and MHD pressure drop in liquid metal LiPb duct with flow channel inserts

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