Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project

Nevo, Alessandro Del; Arena, P.; Caruso, Gianfranco; Chiovaro, P.; Maio, P.A. Di; Eboli, Marica; Edemetti, Francesco; Forgione, Nicola; Forte, Ruggero; Froio, Antonio; Giannetti, Fabio; Gironimo, Giuseppe Di; Jiang, Kecheng; Liu, S.; Moro, F.; Mozzillo, Rocco; Savoldi, Laura; Tarallo, Andrea; Tarantino, M.; Tassone, Alessandro; Utili, Marco; Villari, R.; Zanino, Roberto; Martelli, Emanuela

doi:10.1016/j.fusengdes.2019.03.040

Cited by 136 publications

(86 citation statements)

References 29 publications

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“…the HCPB and the WCLL, with limited R&D activity on the other concepts (e.g. dual coolant lithium led (DCLL)), see figure 9 [65,66]. Accordingly, one of the two helium-cooled test blanket module in ITER, the one using lithium lead as a breeder/multiplier (HCLL) has been replaced with a WCLL.…”

Section: Breeding Blanketmentioning

confidence: 99%

Overview of the DEMO staged design approach in Europe

Federici¹,

Bachmann²,

et al. 2019

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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.

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Section: Breeding Blanketmentioning

confidence: 99%

Overview of the DEMO staged design approach in Europe

Federici¹,

Bachmann²,

et al. 2019

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“…In the European DEMO (EU-DEMO) fusion reactor, the Breeding Blanket (BB) component accomplishes several functions [1,2]. Firstly, it acts as a cooling device.…”

Section: Introductionmentioning

confidence: 99%

“…The computational activity presented in this paper deals with the WCLL option. It foresees the usage of water at typical Pressurized Water Reactor (PWR) thermodynamic conditions (295-328 • C and 15.5 MPa) as coolant [1,2]. The blanket relies on liquid lithium-lead as breeder, neutron multiplier and tritium carrier and on Eurofer as structural material.…”

Section: Introductionmentioning

confidence: 99%

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Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category

et al. 2021

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The Breeding Blanket (BB) is one of the key components of the European Demonstration (EU-DEMO) fusion reactor. Its main subsystems, the Breeder Zone (BZ) and the First Wall (FW), are cooled by two independent cooling circuits, called Primary Heat Transfer Systems (PHTS). Evaluating the BB PHTS performances in anticipated transient and accident conditions is a relevant issue for the design of these cooling systems. Within the framework of the EUROfusion Work Package Breeding Blanket, it was performed a thermal-hydraulic analysis of the PHTS during transient conditions belonging to the category of “Decrease in Coolant System Flow Rate”, by using Reactor Excursion Leak Analysis Program (RELAP5) Mod3.3. The BB, the PHTS circuits, the BZ Once Through Steam Generators and the FW Heat Exchangers were included in the study. Selected transients consist in partial and complete Loss of Flow Accident (LOFA) involving either the BZ or the FW PHTS Main Coolant Pumps (MCPs). The influence of the loss of off-site power, combined with the accident occurrence, was also investigated. The transient analysis was performed with the aim of design improvement. The current practice of a standard Pressurized Water Reactor (PWR) was adopted to propose and study actuation logics related to each accidental scenario. The appropriateness of the current PHTS design was demonstrated by simulation outcomes.

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“…Such a component is in charge of removing the nuclear heat deposited in the PbLi of the dual coolant lithium lead (DCLL) breeding blanket (BB) [2], producing steam suitable to properly feed the turbine unit, ensuring an efficient conversion of the thermal power to electricity. Moreover, the same design is suitable for removing the power deposited in the PbLi in case of unbalance in the water coolant lithium lead (WCLL) BB [3]. One of the configurations selected for DEMO purposes was the steam generator with bayonet tubes (SGBT) [4].…”

Section: Introductionmentioning

confidence: 99%

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

et al. 2021

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The present paper describes the experimental campaign executed at the ENEA Brasimone Research Centre aiming at supporting the development of a PbLi/water heat exchanger suitable for the lithium–lead loops of the dual coolant lithium lead and the water cooled lithium lead breeding blankets of the EU DEMO fusion reactor. The experiments were performed in a test section named HERO, installed inside the main vessel of the lead–bismuth eutectic-cooled pool-type facility CIRCE. The test section hosts a steam generator bayonet tube mock-up in relevant scale, which was selected as a promising configuration for DEMO purposes. For the thermal-hydraulic characterization of the component, five tests were executed at different water pressures (6, 8, 12 MPa, two tests at 10 MPa), and liquid metal flow rates (40, 33, 27, 20, 10 kg/s). The experimental outcomes proved the technological feasibility of this novel steam generator and its suitability for the DEMO PbLi loops. The activity was completed with a post-test analysis using two versions of the system code RELAP5. Because the experiments were executed with lead–bismuth eutectic, a scaling analysis is proposed to find the equivalence with PbLi. RELAP5 code was applied to recalculate the experimental data using PbLi as working fluid.

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Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project

Cited by 136 publications

References 29 publications

Overview of the DEMO staged design approach in Europe

Overview of the DEMO staged design approach in Europe

Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

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