Cold trap and cryogenic molecular sieve adsorber: components for tritium extraction from the purge gas of the HCPB-breeder blanket for ITER

Bekris, N.; Caldwell-Nichols, C.; Hutter, E.

doi:10.1016/s0920-3796(03)00227-8

Cited by 13 publications

(9 citation statements)

References 4 publications

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“…Anyway, in all the getter beds the uptake time tends to be minor compared to that of the desorption time; such a characteristic requires the use of several separation units and then an increase of the tritium inventory. Cryogenic molecular sieve beds absorb tritium at low temperature (i.e., liquid nitrogen), while the tritium is released by heating up to 150 K. As reported in the literature [32][33][34], this technology allows for high efficiencies of separation (95%-99%).…”

Section: Pre-concentration Stage (Pcs)mentioning

confidence: 99%

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

et al. 2016

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Abstract:Dense self-supported Pd-alloy membranes are used to selectively separate hydrogen and hydrogen isotopes. In particular, deuterium (D) and tritium (T) are currently identified as the main elements for the sustainability of the nuclear fusion reaction aimed at carbon free power generation. In the fusion nuclear reactors, a breeding blanket produces the tritium that is extracted and purified before being sent to the plasma chamber in order to sustain the fusion reaction. In this work, the application of Pd-alloy membranes has been tested for recovering tritium from a solid breeding blanket through a helium purge stream. Several simulations have been performed in order to optimize the design of a Pd-Ag multi-tube module in terms of geometry, operating parameters, and membrane module configuration (series vs. parallel). The results demonstrate that a pre-concentration stage before the Pd-membrane unit is mandatory because of the very low tritium concentration in the He which leaves the breeding blanket of the fusion reactor. The most suitable operating conditions could be reached by: (i) increasing the hydrogen partial pressure in the lumen side and (ii) decreasing the shell pressure. The preliminary design of a membrane unit has been carried out for the case of the DEMO fusion reactor: the optimized membrane module consists of an array of 182 Pd-Ag tubes of 500 mm length, 10 mm diameter, and 0.100 mm wall thickness (total active area of 2.85 m 2 ).

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Section: Pre-concentration Stage (Pcs)mentioning

confidence: 99%

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

et al. 2016

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“…Quasi-continuous operation for removal and recovery is achieved having several traps working alternatively in adsorption and regeneration mode. A first TES concept for ITER TBM using a cold trap (for Q 2 O) followed by a cryogenic molecular sieve bed (for Q 2 ) has been experimentally validated for ITER operation at the technical scale [8].…”

Section: Current Tes Conceptsmentioning

confidence: 99%

A new combination of membranes and membrane reactors for improved tritium management in breeder blanket of fusion machines

Demange

Stämmler

Kind

2011

Fusion Engineering and Design

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“…At low temperature, hydrogen and other small polar gas molecules like O 2 and N 2 can be strongly absorbed in molecular sieves like zeolites [9][10][11][12], and helium is only very weakly absorbed at the same time. Thus, a cryogenic molecular sieve bed (CMSB) can be used to remove Q 2 from helium gas.…”

Section: Cryogenic Molecular Sieve Bedmentioning

confidence: 99%