Investigation on efficiency of gas liquid contactor used as tritium extraction unit for HCLL-TBM Pb-16Li loop

Utili, Marco; Aiello, A.; Laffi, L.; Malavasi, A.; Ricapito, I.

doi:10.1016/j.fusengdes.2016.03.067

Cited by 16 publications

(8 citation statements)

References 5 publications

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“…In 2007, TRIEX facility [11,12] was completed with three hydrogen permeation sensors (HPSs) used to measure tritium concentration in LiPb, qualified in a dedicated device. TRIEX had a ring design, chosen so that only the pressure drops had to be overcome.…”

Section: Motivations To the Upgradementioning

confidence: 99%

See 1 more Smart Citation

TRIEX-II: an experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

Utili¹,

Alberghi²,

Candido³

et al. 2022

Nucl. Fusion

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The experimental qualiﬁcation of the Tritium Extraction Unit (TEU) from the LiPb eutectic alloy (15.7 at. % Li), the breeder material of the Water-Cooled Lithium-Lead (WCLL) breeding blanket concept, is one of the fundamental items for the demonstration of tritium balance sustainability for ITER and DEMO fusion reactors. Several technologies have been proposed as TEU, but the selection of the reference technology can be carried out only after the experimental measurement of the tritium extraction eﬃciency. For this purpose, a dedicated facility, called TRIEX-II, was designed and installed at ENEA Brasimone research centre, Italy. The facility is able to qualify Gas-Liquid Contactor (GLC), Permeator Against Vacuum (PAV) and Liquid-Vacuum Contactor (LVC) technologies at diﬀerent temperatures, lithium-lead mass ﬂow rates and hydrogen isotopes concentrations. In TRIEX-II, the hydrogen or deuterium, used to simulate tritium, are solubilised inside the LiPb with a dedicated saturator and are then extracted from the liquid metal in the GLC mock-up, which uses pure helium or a mixture constituted by helium and hydrogen as stripping gas and works in the temperature range between 300 and 500 °C.

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Section: Motivations To the Upgradementioning

confidence: 99%

“…In this technology, a gas and a liquid are brought into contact, allowing a diffusion exchange between them. The GLC of TRIEX-II is of the packed column type [12]. The packed columns are vertical columns filled with a packing which breaks the liquid flow and provides a large interfacial area between the liquid and the gas phases.…”

Section: Extractor (S300)mentioning

confidence: 99%

TRIEX-II: an experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

Utili¹,

Alberghi²,

Candido³

et al. 2022

Nucl. Fusion

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“…Tritium extraction from LiPb has been successfully demonstrated, and several different methods exist, including gas-liquid contactor [49], permeator against vacuum (PAV) [50], [51], [52], and vacuum sieve tray (VST) [9], [53]. The latter two can reach high extraction efficiencies of above 80%.…”

Section: B Liquid Lithium-leadmentioning

confidence: 99%

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

Pearson¹,

Baus²,

Konishi³

et al. 2022

IEEE Trans. Plasma Sci.

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This article outlines Kyoto Fusioneering's (KF's) initial engineering and development activities for its self-cooled lithium lead-type blanket: Self-Cooled Yuryo Lithium-Lead Advanced (SCYLLA©). We provide details on overall design, including an initial tritium breeding ratio (TBR) assessment via neutronics analysis, as well as the status of SCYLLA©-relevant R&D. This includes silicon carbide composite (SiC f /SiC) manufacturing techniques, tritium extraction, materials compatibility, and heat transfer, which are being explored via collaboration with Kyoto University. Results of previous work in relation to this R&D are presented. Permeability coefficients indicate a promising property of SiC f /SiC tritium hermeticity at high temperatures. Tritium extraction technology via vacuum sieve tray (VST) is shown to be demonstrated at engineering scale. A local TBR of up to 1.4 can be achieved with the SCYLLA© configuration. Fabrication methods for various SiC f /SiC components including the blanket module, heat exchanger, and flow path components are provided. A tritium compatible high-temperature SiC f /SiC heat exchanger is discussed. Commercial viability and reactor adaptability are considered as a theme throughout. Finally, KF's plans to build a facility for demonstration reactor relevant testing of a SCYLLA© prototype in the mid-2020s, which will provide a significant step toward commercial fusion energy, are presented.

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“…The characterization of gas-liquid contactors was performed in flowing PbLi using a structured packing with a specific surface of 750 m 2 m −3 [26]. Following those results, the behavior of the system was later analyzed with a packing of 350 m 2 m −3 by varying the liquid metal/gas flow rate ratio showing an efficiency in the range of 25%-30% [27]. Due to the complexity of the system and to the maximum efficiency achieved for one stage (30% [27]), in order to obtain an efficiency of 80%-90% [23,24], required by DEMO, it is necessary to use four or five stages with relevant complexity of the system.…”

Section: Dcll Ters Designmentioning

confidence: 99%

“…Following those results, the behavior of the system was later analyzed with a packing of 350 m 2 m −3 by varying the liquid metal/gas flow rate ratio showing an efficiency in the range of 25%-30% [27]. Due to the complexity of the system and to the maximum efficiency achieved for one stage (30% [27]), in order to obtain an efficiency of 80%-90% [23,24], required by DEMO, it is necessary to use four or five stages with relevant complexity of the system. Nevertheless, further modeling activities showed that the efficiency could be improved by adding hydrogen or deuterium to the stripping gas or by optimizing the geometry of the column.…”

Section: Dcll Ters Designmentioning

confidence: 99%

The tritium extraction and removal system for the DCLL-DEMO fusion reactor

Garcinuño

Rapisarda

Antunes³

et al. 2018

Nucl. Fusion

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During the pre-conceptual design phase of DEMO, different alternatives have been explored to be implemented as tritium extraction and removal system (TERS) for the blanket concepts considered in EUROfusion. The TERS is conceived to extract tritium from the breeder and to route it to the Tritium Plant for final processing. A careful review showed that those blankets operated with PbLi should use the permeation against vacuum (PAV) technique as primary option which is based on a one-step, fully continuous procedure. In this paper, a conceptual design of the TERS for the dual coolant lithium lead (DCLL) breeding blanket is presented, based on the European DEMO2015 layout (18 sectors, 2037 MW fusion power). The P&ID of the proposed TERS, integrated in the DCLL-PbLi loop, includes valves and instrumentation, as well as a revised design of the DCLL-PAV. The dimensioning of the permeator considered a tritium extraction efficiency of 80%. An exhaustive investigation on the vacuum system needed for the PAV is also presented. The choice of the most promising vacuum systems took into account the reliability and tritium compatibility of both high and rough pumps. Their pumping requirements, which are dependent on the PAV efficiency, tritium solubility and tritium partial pressure in the loop, are also discussed in this work.

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Investigation on efficiency of gas liquid contactor used as tritium extraction unit for HCLL-TBM Pb-16Li loop

Cited by 16 publications

References 5 publications

TRIEX-II: an experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

TRIEX-II: an experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

Overview of Kyoto Fusioneering’s SCYLLA© (“Self-Cooled Yuryo Lithium-Lead Advanced”) Blanket for Commercial Fusion Reactors

The tritium extraction and removal system for the DCLL-DEMO fusion reactor

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