Initial DEMO tokamak design configuration studies

Bachmann, Christian; Aiello, G.; Albanese, R.; Ambrosino, R.; Arbeiter, Frederik; Aubert, Julien; Boccaccini, Lorenzo Virgilio; Carloni, D.; Federici, G.; Fischer, U.; Kovari, M.; Puma, A. Li; Loving, A.; Maione, Ivan Alessio; Mattei, M.; Mazzone, G.; Mészáros, B.; Palermo, Iole; Pereslavtsev, P.; Riccardo, V.; Sardain, P.; Nigel, Taylor; Villari, R.; Vízváry, Z.; Vaccaro, A.; Visca, E.; Wenninger, R.

doi:10.1016/j.fusengdes.2015.05.027

Cited by 58 publications

(30 citation statements)

References 12 publications

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“…The present paper reports the latest progress in the structural design study for the European DEMO divertor cassette body which has been conducted in the framework of the work package "Divertor" of the EUROfusion Consortium [1][2][3][4][5]. The structural design study serves as one of the major elements of preconceptual design of DEMO divertor cassette.…”

Section: Introductionmentioning

confidence: 99%

Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx

Frosi

Bachmann²,

Gironimo

et al. 2017

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx

Frosi

Bachmann²,

Gironimo

et al. 2017

Fusion Engineering and Design

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“…steam in the vacuum vessel) can be mitigated by re-condensing the steam in a pressure suppression pool. The inability to do so for helium cooled systems implies a need for a large expansion volume to accommodate a helium LOCA and initial studies point to the need of a very large expansion volume [1].…”

Section: Introductionmentioning

confidence: 99%

Preliminary evaluation of the expansion system size for a pressurized gas loop: application to a fusion reactor based on a helium-cooled blanket

Caruso

Nobili

2017

IJHT

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Some considerations to preliminarily design the size of the Expansion Volume (EV) and the relief pipes for a Vacuum Vessel Pressure Suppression System, to be adopted in a fusion reactor based on a helium cooled blanket, are presented. The volume of the EV depends on the total energy of the cooling system and it can be sized based on a required final pressure at equilibrium, by a simple energy balance. Two different EV solutions have been analysed: a "dry" EV and a "wet" EV. In this last, a certain amount of water could be mixed (by spraying or discharging in a pool) with the discharged helium, to reduce its temperature and allowing a lower size of the EV with respect to the "dry" solution. The pressure peak in vacuum vessel (VV) depends mainly on break area and flow area of the relief pipes and a simple formula to be used to size these pipes is suggested. The computer code CONSEN has been used to perform sensitivity analyses and to verify the methodology.

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“…The fuel cycle has a crucial role in the feasibility of a nuclear fusion plant. It must fulfill several tasks to allow tokamak operations, these are [8,9]: storage and delivery of D and T, tokamak fueling, tritium extraction from the breeding blanket, vacuum pumping from torus and plasma exhaust treatment, isotope separation, water detritiation, atmosphere and vent detritiation, tritium analysis, and accountability. Moreover, in the future fusion machines, two other important aspects have to be considered: the tritium burn-up fraction and the amount of tritium produced by the breeding blanket.…”

Section: Introductionmentioning

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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Initial DEMO tokamak design configuration studies

Cited by 58 publications

References 12 publications

Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx

Structural analysis of DEMO divertor cassette body and design study based on RCC-MRx

Preliminary evaluation of the expansion system size for a pressurized gas loop: application to a fusion reactor based on a helium-cooled blanket

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

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