The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification

Zmítko, M.; Carin, Yann; Thomas, N.M.; Simon, Perikles; Li-Puma, A.; Forest, Laurent; Tosi, Jérôme; Aiello, G.; Cogneau, Laurence; Rey, J.; Neuberger, Heiko; Aktaa, Jarir; Gaganidze, E.; Zhang, K.; Pierredon, N.; Lejeail, Y.; Lamagnere, P.; Poitevin, Y.

doi:10.1016/j.fusengdes.2017.04.051

Cited by 36 publications

(4 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The strategic vision is to retain the basic structure and advantages of RAFM steels while improving their operational performance. Some target requirements are to operate in a higher temperature range and to be able to withstand neutron damage up to 70 dpa (with the possibility of extending this target to about 150 dpa), while keeping their reduced activation properties [ 11 , 23 , 60 , 74 ]. Within EUROfusion, two clear goals have been adopted for EUROFER97: DBTT reduction with the objective of using it in water-cooled designs.…”

Section: Structural Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

View full text Add to dashboard Cite

This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

show abstract

Section: Structural Materialsmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

View full text Add to dashboard Cite

show abstract

“…Hence, its crucial integrated functions and reliability in DEMO and future power plant are by no means assured. ITER presents a first and unique opportunity to test the response of breeding blanket materials and representative component mock-ups, specifically called test blanket modules (TBMs) at relevant operating conditions, in an actual fusion environment, albeit at very low neutron fluences (see for example [61,64] and references therein).…”

Section: Breeding Blanketmentioning

confidence: 99%

Overview of the DEMO staged design approach in Europe

Federici¹,

Bachmann²,

et al. 2019

View full text Add to dashboard Cite

This paper describes the status of the pre-conceptual design activities in Europe to advance the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in operation around the middle of this century with the main aims of demonstrating the production of few hundred MWs of net electricity, the feasibility of operation with a closedtritium fuel cycle, and maintenance systems capable of achieving adequate plant availability. This is expected to benefit as much as possible from the ITER experience, in terms of design, licensing, and construction. Emphasis is on an integrated design approach, based on system engineering, which provides a clear path for urgent R&D and addresses the main design integration issues by taking account critical systems interdependencies and inherent uncertainties of important design assumptions (physics and technology). A design readiness evaluation, together with a technology maturation and down selection strategy are planned through structured and transparent Gate Reviews. By embedding industry experience in the design from the beginning it will ensure that early attention is given to technology readiness and industrial feasibility, costs, maintenance, power conversion, nuclear safety and licensing aspects.

show abstract

“…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

View full text Add to dashboard Cite

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.

show abstract

The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification

Cited by 36 publications

References 9 publications

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Overview of the DEMO staged design approach in Europe

Eurofusion-DEMO Divertor - Cassette Design and Integration

Contact Info

Product

Resources

About