The European Dual Coolant Lithium Lead breeding blanket for DEMO: status and perspectives

Rapisarda, D.; Fernández-Berceruelo, Iván; García, A. R.; Garcı́a, J.; Garcinuño, Belit; González, M.; Moreno, Carlos; Palermo, Iole; Urgorri, Fernando Roca; Ibarra, Á.

doi:10.1088/1741-4326/ac26a1

Cited by 27 publications

(7 citation statements)

References 47 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Therefore, new BB designs based on the existing Dual Coolant Lithium Lead (DCLL) BB concept developed for DEMO tokamak [14][15] [16][17] [18], have been explored readapting it to the 3D geometry of HELIAS and trying to answer the additional challenges that this complex configuration brings. Since in the DCLL BB concept the PbLi breeder is liquid, it could be potentially easier to adapt the BB to the HELIAS complex shape, comparing with solid BB concepts.…”

Section: The Dual Coolant Lithium Lead Bb Concept: Major Features And...mentioning

confidence: 99%

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Sosa¹,

Palermo²

2023

Preprint

View full text Add to dashboard Cite

The Stellarator Power Plant Studies Prospective R&amp;D Work Package among the Eurofusion Programme was settled to bring the stellarator engineering to maturity, so that stellarators and particularly the HELIAS (HELical-axis Advanced Stellarator) configuration could be a possible alternative to tokamaks. However, its complex geometry makes designing a Breeding Blanket (BB) that fully satisfies the requirements for such an HELIAS configuration a difficult task. Taking advantage of the acquired experience in BB design for DEMO tokamak, CIEMAT is leading the development of a Dual Coolant Lithium Lead (DCLL) BB for a HELIAS configuration. To answer the specific HELIAS challenges new and advanced solutions have been proposed, as the use of fully detached First Wall (FW) based on liquid metal Capillary Porous Systems (CPS). These proposed solutions have been studied in a simplified 1D model that can help to estimate the relative variations in Tritium Breeding Ratio (TBR) and displacement per atom (dpa) to verify their effectiveness to simplify the BB integration, improve the machine availability while keeping the main BB nuclear functions (i.e. tritium breeding, heat extraction and shielding). This preliminary study demonstrates that the use of FW CPS would reduce the radiation damage received by the blanket without compromising its tritium breeding performance.

show abstract

Section: The Dual Coolant Lithium Lead Bb Concept: Major Features And...mentioning

confidence: 99%

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Sosa¹,

Palermo²

2023

Preprint

View full text Add to dashboard Cite

show abstract

“…Under this assumption and using the mass balance equation (2), it is obtained the extra equation needed to close the system:…”

Section: Closed Loop Configurationmentioning

confidence: 99%

Theoretical evaluation of the tritium extraction from liquid metal flows through a free surface and through a permeable membrane

et al. 2023

Self Cite

View full text Add to dashboard Cite

Effective tritium extraction from PbLi flows is a requirement for the functioning of any PbLi based breeding blanket (BB) concept. For a continuous plant operation, the removal of the tritium dissolved in the PbLi has to be performed in line and sufficiently fast. Otherwise, tritium inventories in the liquid metal, start-up inventories and buffer inventories would be excessive from the safety point of view. Moreover, a slow response of the tritium extraction systems could also compromise the tritium self-sufficiency of the plant. A promising solution to this problem is to use highly permeable membranes in contact with the PbLi flow to promote the extraction via permeation. This technique is usually known as Permeation Against Vacuum (PAV). As an alternative, tritium could be extracted directly by permeation through a fluid free surface (FS) in contact with vacuum. In both configurations, the dynamics of tritium transport is ruled by a combination of convection, diffusion and surface recombination. In this paper, the tritium extraction processes in the FS and PAV configurations are studied in detail. For the first time, general analytical expressions for the extraction efficiency are derived for both techniques in a Cartesian geometry. These expressions are general in the sense that they do not impose any kind of assumption concerning the permeation regime of the membrane or the fluid boundary layer. The derived expressions have been used to analyze numerically the response of both configurations in a close loop system, such as the one of DEMO. The presented methodology allows comparing the FS and PAV configurations, assessing in which conditions one will be behave better than other.

show abstract

“…From all these designs and options, experts will decide which TBMs will be used in ITER with a view to their future implementation in DEMO. Because of this, a vast amount of reviews can be found regarding each of them [ 65 , 66 , 67 , 68 , 69 , 70 , 71 , 72 ].…”

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

The European Dual Coolant Lithium Lead breeding blanket for DEMO: status and perspectives

Cited by 27 publications

References 47 publications

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Neutronic Assessments towards a Novel First Wall Design for a Stellarator Fusion Reactor with Dual Coolant Lithium Lead Breeding Blanket

Theoretical evaluation of the tritium extraction from liquid metal flows through a free surface and through a permeable membrane

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

Contact Info

Product

Resources

About