Zeolite membranes and palladium membrane reactor for tritium extraction from the breeder blankets of ITER and DEMO

Demange, D.; Borisevich, O.; Gramlich, N.; Wagner, Robert; Welte, S.

doi:10.1016/j.fusengdes.2013.05.102

Cited by 14 publications

(3 citation statements)

References 31 publications

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“…binary (H 2 /He) and ternary (H 2 /He/H 2 O) gas mixtures [6][7][8]. The results evidenced relatively high permeance but limited selectivity for single gases.…”

Section: Introductionmentioning

confidence: 96%

Experimental study of permeation and selectivity of zeolite membranes for tritium processes

Borisevich

Antunes

Demange

2015

Fusion Engineering and Design

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“…binary (H 2 /He) and ternary (H 2 /He/H 2 O) gas mixtures [6][7][8]. The results evidenced relatively high permeance but limited selectivity for single gases.…”

Section: Introductionmentioning

confidence: 96%

Experimental study of permeation and selectivity of zeolite membranes for tritium processes

Borisevich

Antunes

Demange

2015

Fusion Engineering and Design

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“…GLC is being considered as a candidate for the TERS of the European Demonstration power plant (DEMO) as well. However, scaling this technique up to DEMO size is considered an important challenge [7]. For designing the DEMO TERS, the so called Permeation Against Vacuum (PAV) technique has been chosen as a reference for many years [8].…”

Section: Introductionmentioning

confidence: 99%

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

et al. 2023

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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.

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“…For ITER this issue can be dealt with, since the generation of tritium is around 0.11 mg d −1 (HCLL) and 0.17 mg d −1 (HCPB) [9]. Meanwhile, the generation in a DCLL-DEMO is 3 orders of magnitude higher, around 400 g d −1 [10], and, therefore, tritium processing in ITER is too far to be considered as a reliable baseline for the DEMO outer fuel cycle [11]. Another technological step is the PbLi mass flow to be processed in the loops, between 0.1 and 1 kg s −1 in the HCLL-TBM and above 2000 kg s −1 in DCLL DEMO.…”

Section: Introductionmentioning

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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Zeolite membranes and palladium membrane reactor for tritium extraction from the breeder blankets of ITER and DEMO

Cited by 14 publications

References 31 publications

Experimental study of permeation and selectivity of zeolite membranes for tritium processes

Experimental study of permeation and selectivity of zeolite membranes for tritium processes

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

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

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