The European ITER Test Blanket Modules: Current status of fabrication technologies development and a way forward

Zmítko, M.; Galabert, Jose; Thomas, N.M.; Forest, Laurent; Bucci, Philippe; Cogneau, Laurence; Rey, J.; Neuberger, Heiko; Poitevin, Y.

doi:10.1016/j.fusengdes.2015.06.064

Cited by 14 publications

(3 citation statements)

References 5 publications

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“…With the collaboration of an industrial partner, a preliminary manufacturing sequence including machining, welding and NDT steps is proposed. The preliminary assessment takes into account know-how on Eurofer manufacturing and assembly technologies assessed of the ITER TBMs (Test Blanket Modules) [7], [8], [9] and [10] and the DEMO BB (Breeding Blanket) [11], [12] and [13]. Two main routes are envisaged:…”

Section: Shielding Linermentioning

confidence: 99%

Eurofusion-DEMO Divertor - Cassette Design and Integration

Mazzone

You

Bachmann³

et al. 2020

Fusion Engineering and Design

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The Eurofusion-DEMO design will complete the Pre Conceptual Design phase (PCD) with a PCD Gate, named G1, scheduled to take place in Q4 2020 that will focus on assessing the feasibility of the plant and its main components prior to entering into the Conceptual Design phase. In the paper first an overview is given of the Eurofusion-DEMO Divertor Assembly including design and interface description, systems and functional requirements, load specification, system classification, manufacturing procedures and cost estimate. Then critical issues are discussed and potential design solutions are proposed, e.g.: -Neutron material damage limits of the different (structural) materials present in the divertor assembly (as CuCrZr, Eurofer) and in the vacuum vessel (AISI 316L(N)-IG); -Temperature hot spots in parts of the divertor assembly exposed to high nuclear heating and high heat radiation (from the plasma core or the separatrix) causing difficulties for active or passive cooling (e.g. cassette body structure, liner support structures, mechanical supports, divertor toroidal rails); -Arrangement and design of plasma-facing components and liner with pumping slot in the divertor cassette to enable pumping of exhaust gases from the lower port.

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Section: Shielding Linermentioning

confidence: 99%

Eurofusion-DEMO Divertor - Cassette Design and Integration

Mazzone

You

Bachmann³

et al. 2020

Fusion Engineering and Design

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“…These technologies have been developed in framework of the TBM programme under F4E, under EUROfusion or in national funded programme of association like CEA and KIT. In the TBM Programme [43] large contracts have been launched in the past few years for the assessment of fabrication technologies and procedures of the HCLL/HCPB TBM sub-components, like first wall, cooling and stiffening plates, and side caps; the investigated technologies are based on fusion and diffusion welding of EUROFER-97 steel as well as spark-erosion and bending. This work has developed preliminary fabrication/welding procedure specifications complying with codes and standards (RCC-MRx) and the manufacturing and characterisation of feasibility mock-ups.…”

Section: Blanket Manufacturingmentioning

confidence: 99%

Objectives and status of EUROfusion DEMO blanket studies

Boccaccini

Aiello

Aubert

et al. 2016

Fusion Engineering and Design

179

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The design of a DEMO reactor requires the design of a blanket system suitable of reliable T production and heat extraction for electricity production. In the frame of the EUROfusion Consortium activities, the Breeding Blanket Project has been constituted in 2014 with the goal to develop concepts of Breeding Blankets for the EU PPPT DEMO; this includes an integrated design and R&D program with the goal to select after 2020 concepts on fusion plants for the engineering phase. The design activities are presently focalized around a pool of solid and liquid breeder blanket with helium, water and PbLi cooling. Development of tritium extraction and control technology, as well manufacturing and development of solid and PbLi breeders are part of the Programme.

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“…Also, issues related to the large-scale manufacturing of components required for DEMO must be considered, since TBM is a oneof-its-kind component: manufacturing techniques selected for TBM could prove economically not viable for DEMO. Development and qualification of manufacturing processes for TBM are being carried out under contract by F4E [17]. Two manufacturing processes of elementary TBM sub-components (FW, SC, SP, CP), are being considered: the 'laser weld + HIP' process and the two step HIP process (figure 4).…”

Section: Impact On Selected Manufacturing Techniques and Associated R...mentioning

confidence: 99%

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

et al. 2017

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The helium cooled lithium lead (HCLL) blanket concept was originally developed in CEA at the beginning of 2000: it is one of the two European blanket concepts to be tested in ITER in the form of a test blanket module (TBM) and one of the four blanket concepts currently being considered for the DEMOnstration reactor that will follow ITER. The TBM is a highly optimized component for the ITER environment that will provide crucial information for the development of the DEMO blanket, but its design needs to be adapted to the DEMO reactor. With respect to the TBM design, reduction of the steel content in the breeding zone (BZ) is sought in order to maximize tritium breeding reactions. Different options are being studied, with the potential of reaching tritium breeding ratio (TBR) values up to 1.21. At the same time, the design of the back supporting structure (BSS), which is a DEMO specific component that has to support the blanket modules inside the vacuum vessel (VV), is ongoing with the aim of maximizing the shielding power and minimizing pumping power. This implies a re-engineering of the modules' attachment system. Design changes however, will have an impact on the manufacturing and assembly sequences that are being developed for the HCLL-TBM. Due to the differences in joint configurations, thicknesses to be welded, heat dissipation and the various technical constraints related to the accessibility of the welding tools and implementation of non-destructive examination (NDE), the manufacturing procedure should be adapted and optimized for DEMO design. Laser welding instead of TIG could be an option to reduce distortions. The time-of-flight diffraction (TOFD) technique is being investigated for NDE. Finally, essential information expected from the HCLL-TBM program that will be needed to finalize the DEMO design is discussed.

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The European ITER Test Blanket Modules: Current status of fabrication technologies development and a way forward

Cited by 14 publications

References 5 publications

Eurofusion-DEMO Divertor - Cassette Design and Integration

Eurofusion-DEMO Divertor - Cassette Design and Integration

Objectives and status of EUROfusion DEMO blanket studies

Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMO

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