Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module

Ciampichetti, A.; Nitti, Francesco; Aiello, A.; Ricapito, I.; Liger, Karine; Demange, D.; Sedano, L.; Moreno, Carlos; Succi, M.

doi:10.1016/j.fusengdes.2012.01.047

Cited by 37 publications

(15 citation statements)

References 7 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…According to the latest EU-TBM baseline, cryogenic temperatures are totally abandoned, adopting a getter bed (GB) instead of CMSB, and a PERMCAT reactor (cf. Section 2.2) has been retained instead of the RB [8].…”

Section: Different Process Concepts For Hcpb-tesmentioning

confidence: 99%

Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO

Demange

Alecu

Bekris

et al. 2012

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Section: Different Process Concepts For Hcpb-tesmentioning

confidence: 99%

Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO

Demange

Alecu

Bekris

et al. 2012

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

“…The composition of the gas stream leaving the breeding zone includes He, HT, HTO, and H 2 . A cold trap (CT) separates the HTO [26,27], which is sent to the water detritiation system (WDS), while the rest of the mixture is sent to a pre-concentration unit (PCS in the Figure 1) for the extraction of the hydrogen isotopes in the form of HT. This stage is necessary because of the very low tritium concentration in the gas mixture that comes out of the breeding blanket.…”

Section: Tritium Extraction System For a Hcpb Breeding Blanketmentioning

confidence: 99%

“…Another getter bed material proposed for this application is based on the Zr-Co alloy. It uptakes hydrogen at room temperature and releases it when heated to 500-600 K [27]. This kind of getter exhibits excellent performance in terms of both sorption capacity (close to 100%) [30] and hydrogen uploading (H/ZrCo ratio up to 1.8) [31].…”

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

View full text Add to dashboard Cite

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 ).

show abstract

“…HTW will also be present in the purge gas of the solid breeder blanket. According to the latest design review [11,12] tritiated water shall be removed from the helium purge gas using an adsorption column, i.e. a molecular sieve bed (MSB) containing zeolite material and operated at room temperature.…”

Section: Introductionmentioning

confidence: 99%

Development of a technical scale PERMCAT reactor for processing of highly tritiated water

Welte

Demange

Wagner

et al. 2012

Fusion Engineering and Design

Self Cite

View full text Add to dashboard Cite

Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module

Cited by 37 publications

References 7 publications

Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO

Overview of R&D at TLK for process and analytical issues on tritium management in breeder blankets of ITER and DEMO

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

Development of a technical scale PERMCAT reactor for processing of highly tritiated water

Contact Info

Product

Resources

About