Objectives and status of EUROfusion DEMO blanket studies

Boccaccini, L.V.; Aiello, G.; Aubert, Julien; Bachmann, C.; Barrett, T.; Nevo, Alessandro Del; Demange, D.; Forest, Laurent; Hernández, Francisco A.; Norajitra, P.; Porempovic, G.; Rapisarda, D.; Sardain, P.; Utili, Marco; Vála, L.

doi:10.1016/j.fusengdes.2015.12.054

Cited by 179 publications

(79 citation statements)

References 39 publications

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“…Four different design options of a breeder blanket are under investigation in the PPPT programme [4]: a solid breeder blanket with Beryllium as neutron multiplier and Helium gas as coolant (HCPB-Helium Cooled Pebble Bed), a liquid metal blanket with PbLi as breeder and Helium gas as coolant (HCLL-Helium Cooled Lithium Lead), a liquid metal blanket with PbLi as breeder and water as coolant (WCLL-Water Cooled Lithium Lead), and another liquid metal blanket with PbLi acting both as breeder and coolant, and employing additionally Helium gas as In this paper an evaluation of the nuclear performance of these breeder blanket concepts is presented with regard to their potential and suitability for application in DEMO. The evaluation builds on the analyses performed within the PPPT breeder blanket programme for the initial design versions of the blankets produced in 2014.…”

Section: Introductionmentioning

confidence: 99%

Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

Fischer

Bachmann²,

Jaboulay

et al. 2016

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

Fischer

Bachmann²,

Jaboulay

et al. 2016

Fusion Engineering and Design

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“…For each SP configuration assessed, a proper 3D FEM model, reproducing the wavy SB already adopted in properly endowed with a potentially optimized SP configuration, is set up.…”

Section: Thermo‐mechanical Analysesmentioning

confidence: 99%

“…The water‐cooled lithium–lead (WCLL) BB is considered a candidate option for the European DEMO nuclear fusion reactor . It relies on EUROFER as a structural material; liquid lithium–lead (PbLi) 6 Li enriched at 90% as a breeder, neutron multiplier, and tritium carrier; and water as a coolant at pressurized water reactor conditions.…”

Section: Introductionmentioning

confidence: 99%

Advancements in DEMO WCLL breeding blanket design and integration

et al. 2017

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The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration Power Plant(DEMO) nuclear fusion reactor. This breeding blanket concept relies on the liquid lithium– lead as breeder–multiplier,pressurized water as coolant, and EUROFER as structural material. The current design is based on DEMO 2015speciﬁcations and represents the follow-up of the design developed in 2015. The single-module-segment approach isemployed. This is constituted by a basic geometry repeated along the poloidal direction. The power is removed by meansof radial–toroidal (i.e., horizontal) water cooling tubes in the breeding zone. The lithium–lead ﬂows in a radial–poloidaldirection. On the back of the segment, a 100-mm-thick plate is in charge of withstanding the loads due to normal operationand selected postulated initiating events. Water and lithium–lead manifolds are designed and integrated with a consistentprimary heat transport system, based on a reliable pressurized water reactor operating experience, and the lithium–leadsystem. Rationale and features of the single-module-segment water-cooled lithium–lead breeding blanket design arediscussed and supported by thermo-mechanic, thermo-hydraulic, and neutronic analyses. Preliminary integration withthe primary heat transfer system, the energy storage system, and the balance of plant is brieﬂy discussed. Open issues, areasof research, and development needs are ﬁnally pointed out

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“…Several concepts are being tested by the various Parties involved in the ITER project to study which is the most viable and economic concept. For the European DEMO four breeding blanket design concepts with different level of design/technology readiness are considered, based on water, helium and LiPb as coolants and a solid or LiPb as tritium breeder/neutron multiplier [29].…”

Section: Tritium Self-sufficiency (Mission 4)mentioning

confidence: 99%

Scientific and technical challenges on the road towards fusion electricity

Donné¹,

Federici²,

Litaudon³

et al. 2017

J. Inst.

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A: The goal of the European Fusion Roadmap is to deliver fusion electricity to the grid early in the second half of this century. It breaks the quest for fusion energy into eight missions, and for each of them it describes a research and development programme to address all the open technical gaps in physics and technology and estimates the required resources. It points out the needs to intensify industrial involvement and to seek all opportunities for collaboration outside Europe. The roadmap covers three periods: the short term, which runs parallel to the European Research Framework Programme Horizon 2020, the medium term and the long term.ITER is the key facility of the roadmap as it is expected to achieve most of the important milestones on the path to fusion power. Thus, the vast majority of present resources are dedicated to ITER and its accompanying experiments. The medium term is focussed on taking ITER into operation and bringing it to full power, as well as on preparing the construction of a demonstration power plant DEMO, which will for the first time demonstrate fusion electricity to the grid around the middle of this century. Building and operating DEMO is the subject of the last roadmap phase: the long term. Clearly, the Fusion Roadmap is tightly connected to the ITER schedule. Three key milestones are the first operation of ITER, the start of the DT operation in ITER and reaching the full performance at which the thermal fusion power is 10 times the power put in to the plasma. The Engineering Design Activity of DEMO needs to start a few years after the first ITER plasma, while the start of the construction phase will be a few years after ITER reaches full performance. In this way ITER can give viable input to the design and development of DEMO. Because the neutron fluence in DEMO will be much higher than in ITER, it is important to develop and validate materials that can handle these very high neutron loads. For the testing of the materials, a dedicated 14 MeV neutron source is needed. This DEMO Oriented Neutron Source (DONES) is therefore an important facility to support the fusion roadmap. K: Nuclear instruments and methods for hot plasma diagnostics; Instrumentation for neutron sources

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Objectives and status of EUROfusion DEMO blanket studies

Cited by 179 publications

References 39 publications

Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

Advancements in DEMO WCLL breeding blanket design and integration

Scientific and technical challenges on the road towards fusion electricity

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