Performance of a hydrogen sensor in Pb–16Li

Ciampichetti, A.; Zucchetti, Massimo; Ricapito, I.; Utili, Marco; Aiello, A.; Benamati, G.

doi:10.1016/j.jnucmat.2007.03.250

Cited by 26 publications

(6 citation statements)

References 7 publications

(9 reference statements)

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“…This measurement is mandatory for the correct operation of a tokamak and, in particular, for the control of the tritium inventory in the Li-breeding blanket. Based on the PAV concept, membrane tubes made of iron or Nb have been studied for the measurement of the tritium into LiPb [39,40]: these tubes are immersed into liquid LiPb and their lumen side is vacuum-pumped and connected to a detecting system (e.g., a mass spectrometer). Neglecting the mass-transfer resistance due to the boundary layers and the recombination reactions, from the expressions (15) and (16), it is possible to establish the relationship between the concentration of the tritium into the LiPb and the permeation flux measured by the detecting system:C H = K S J th/Pe M …”

Section: Resultsmentioning

confidence: 99%

“…The tests have shown a quick degradation of the Nb sensor (the permeation flux decreased during testing due to the oxidation of the membrane surface) while the iron sensor could not be easily operated in steady-state conditions because of the long time required to achieve the hydrogen pressure equilibrium [39]. In this view, a porous ceramic membrane made of materials characterized by low reactivity at high temperatures (alumina, zirconia, SiC, etc.)…”

Section: Resultsmentioning

confidence: 99%

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Membrane Processes for the Nuclear Fusion Fuel Cycle

Tosti

Pozio

2018

Membranes

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This paper reviews the membrane processes for the nuclear fusion fuel cycle—namely, the treatment of the plasma exhaust gases and the extraction of tritium from the breeding blankets. With respect to the traditional processes, the application of membrane reactors to the fusion fuel cycle reduces the tritium inventory and processing time, thus increasing the safety and availability of the system. As an example, self-supported Pd-alloy membrane tubes have been studied for the separation of hydrogen and its isotopes from both gas- and liquid-tritiated streams through water-gas shift and isotopic swamping reactions. Furthermore, this paper describes an innovative membrane system (Membrane Gas–Liquid Contactor) for the extraction of hydrogen isotopes from liquid LiPb blankets. Porous membranes are exposed to the liquid metal that penetrates the pores without passing through them, then realizing a gas–liquid interface through which the mass transfer of hydrogen isotopes takes place. Compared to the conventional hydrogen isotope extraction processes from LiPb that use the “permeator against vacuum” concept, the proposed process significantly reduces mass-transfer resistance by improving the efficiency of the tritium recovery system.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Membrane Processes for the Nuclear Fusion Fuel Cycle

Tosti

Pozio

2018

Membranes

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“…Tritium concentration in PbLi (TS): placed before and after the PAV in order to know the tritium concentration in PbLi and therefore the PAV efficiency. Sensors for measuring the permeation of hydrogen isotopes have been demonstrated to be a suitable technique for this purpose [38,39]. The sensor consists in a hollow capsule with a membrane permeable to hydrogen.…”

Section: Instrumentationmentioning

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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“…The experimental device developed is be able to: The permeation sensor measures the hydrogen (and its isotopes) concentration in liquid Pb-15.7Li [11]. Different kinds of sensors, with permeable capsule made of iron and niobium, were developed and qualified in the past.…”

Section: State Of the Art Of The Investigation Of Hydrogen Isotopes Imentioning

confidence: 99%