Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant

Palermo, Iole; Veredas, G.; Gómez-Ros, J.M.; Sanz, J.; Ibarra, Á.

doi:10.1088/0029-5515/56/1/016001

Cited by 10 publications

(3 citation statements)

References 38 publications

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“…This arrangement was mainly motivated by the use of the EUROFER as structural material, since having a complete 'banana' (or single module) segment as in previous DCLL concepts (e.g. [38,45]) would imply a large route for the liquid metal, which has to maintain the temperature between 300 and 550 • C. This short operational window, together with the large path through the segment (typically >10 m length), means that the velocity of the PbLi has to be really high, of the order of dm s −1 . The direct implication is the rising of MHD phenomena, causing important pressure drops and, in addition, an enhancement of the corrosion rate [46].…”

Section: Perspectives Of the Ht-dcll And Conceptual Proposalmentioning

confidence: 99%

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

Rapisarda

Fernández-Berceruelo²,

García³

et al. 2021

Nucl. Fusion

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During the last years CIEMAT has been leading the activities in the European Program to develop an integral breeding blanket with advanced performances to work in a realistic DEMO scenario. This blanket is the dual coolant lithium lead (DCLL) working at a limited temperature in order to allow the use of conventional materials and technologies. The design of this blanket was finished, including the definition of the tritium extraction system and tritium simulations. Then, determined by the selection of other two concepts as driver blankets for DEMO, the focus was put on developing a novel BB still based on the DCLL concept but working at higher temperatures, thus increasing the plant net efficiency. In this work, a summary of the status of the DCLL is presented, together with some ideas for developing an advanced high temperature DCLL in the near future.

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Section: Perspectives Of the Ht-dcll And Conceptual Proposalmentioning

confidence: 99%

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

Rapisarda

Fernández-Berceruelo²,

García³

et al. 2021

Nucl. Fusion

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“…Parametric models of all four EU blanket designs were generated to demonstrate the design tool. These include the helium-cooled pebble bed blanket (HCPB) [8][9][10], helium-cooled lithium lead blanket (HCLL) [11,12], water-cooled lithium lead blanket (WCLL) [13] and dual-coolant lithium lead blanket (DCLL) [14]. The process has been broken down into two parts, the first flowchart (see figure 1) summarizes the construction of all the non-breeder zone components, this includes the first wall, armour and rear plates.…”

Section: Geometry Creationmentioning

confidence: 99%

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

et al. 2019

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Breeding blankets are designed to ensure tritium self-sufficiency in deuterium–tritium fusion power plants. In addition to this, breeder blankets play a vital role in shielding key components of the reactor, and provide the main source of heat which will ultimately be used to generate electricity. Blanket design is critical to the success of fusion reactors and integral to the design process. Neutronic simulations of breeder blankets are regularly performed to ascertain the performance of a particular design. An iterative process of design improvements and parametric studies are required to optimize the design and meet performance targets. Within the EU DEMO program the breeding blanket design cycle is repeated for each new baseline design. One of the key steps is to create three-dimensional models suitable primarily for use in neutronics, but could be used in other computer-aided design (CAD)-based physics and engineering analyses. This article presents a novel blanket design tool which automates the process of producing heterogeneous 3D CAD-based geometries of the helium-cooled pebble bed, water-cooled lithium lead, helium-cooled lithium lead and dual-coolant lithium lead blanket types. The paper shows a method of integrating neutronics, thermal analysis and mechanical analysis with parametric CAD to facilitate the design process. The blanket design tool described in this paper provides parametric geometry for use in neutronics and engineering simulations. This paper explains the methodology of the design tool and demonstrates use of the design tool by generating all four EU blanket designs using the EU DEMO baseline. Neutronics and heat transfer simulations using the models have been carried out. The approach described has the potential to considerably speed up the design cycle and greatly facilitate the integration of multiphysics studies.

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“…All the related engineering and technological activities are included in the Eurofusion Horizon Europe Work Package Prospectives R&D: Stellarator Power Plant Studies (WPPRD SPPS). Among these activities, and exploiting the large experience in BB design for DEMO tokamak [8][9][10][11][12][13][14][15], CIEMAT is leading the development of a Dual Coolant Lithium Lead (DCLL) Breeding Blanket (BB) for the HELIAS device [16]. Such a concept, which is detailed in Section 2, has high potentialities to answer the specific challenges posed by the complex HELIAS configuration.…”

Section: Introductionmentioning

confidence: 99%

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

Sosa

Palermo

2023

Energies

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The Stellarator Power Plant Studies Prospective R&D Work Package in 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 a HELIAS configuration, which is 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, such as the use of fully detached First Wall (FW) based on liquid metal Capillary Porous Systems (CPS). The 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 in simplifying the BB integration and improving 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 drastically reduce the radiation damage received by the blanket by 29% in some of the selected configurations along with a small decrease of 4.9% in TBR. This could even be improved to just a 3.8% TBR reduction by using a graphite reflector. Such an impact on the TBR is considered affordable, and the results presented, although preliminary in essence, have shown the existence of margins for further development of the FW CPS concept for HELIAS, as they have been not found, at least to date, to be significant showstoppers for the use of this technological solution.

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Neutronic design studies of a conceptual DCLL fusion reactor for a DEMO and a commercial power plant

Cited by 10 publications

References 38 publications

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

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

Multiphysics analysis with CAD-based parametric breeding blanket creation for rapid design iteration

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

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