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Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor

Author

Listed:
  • Marco Utili

    (ENEA Brasimone, Camugnano, 40032 Bologna, Italy)

  • Ciro Alberghi

    (Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, Italy)

  • Roberto Bonifetto

    (CIEMAT-LNF, Av. Complutense 40, 28040 Madrid, Spain)

  • Luigi Candido

    (Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, Italy)

  • Aldo Collaku

    (Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, Italy)

  • Belit Garcinuño

    (CIEMAT-LNF, Av. Complutense 40, 28040 Madrid, Spain)

  • Michal Kordač

    (Centrum Výzkumu Řež (CVR), Hlavní 130, 250 68 Husinec-Řež, Czech Republic)

  • Daniele Martelli

    (ENEA Brasimone, Camugnano, 40032 Bologna, Italy)

  • Rocco Mozzillo

    (CREATE, Engineering School of Basilicata University, Campus Macchia, Romana, 85100 Potenza, Italy)

  • Francesca Papa

    (DIAEE Department, Sapienza University of Rome, 00186 Rome, Italy)

  • David Rapisarda

    (CIEMAT-LNF, Av. Complutense 40, 28040 Madrid, Spain)

  • Laura Savoldi

    (Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, Italy)

  • Fernando R. Urgorri

    (CIEMAT-LNF, Av. Complutense 40, 28040 Madrid, Spain)

  • Domenico Valerio

    (Dipartimento Energia “Galileo Ferraris”, Politecnico di Torino, 10129 Torino, Italy)

  • Alessandro Venturini

    (ENEA Brasimone, Camugnano, 40032 Bologna, Italy)

Abstract

The latest progress in the design of the water-cooled lithium–lead (WCLL) tritium extraction and removal (TER) system for the European DEMO tokamak reactor is presented. The implementation and optimization of the conceptual design of the TER system are performed in order to manage the tritium concentration in the LiPb and ancillary systems, to control the LiPb chemistry, to remove accumulated corrosion and activated products (in particular, the helium generated in the BB), to store the LiPb, to empty the BB segments, to shield the equipment due to LiPb activation, and to accommodate possible overpressure of the LiPb. The LiPb volumes in the inboard (IB) and outboard (OB) modules of the BB are separately managed due to the different pressure drops and required mass flow rates in the different plasma operational phases. Therefore, the tritium extraction is managed by 6 LiPb loops: 4 loops for the OB segments and 2 loops for the IB segments. Each one is a closed loop with forced circulation of the liquid metal through the TER and the other ancillary systems. The design presents the new CAD drawings and the integration of the TEU into the tokamak building, designed on the basis of an experimental characterization carried out for the permeator against vacuum (PAV) and gas–liquid contactor (GLC) technologies, the two most promising technologies for tritium extraction from liquid metal.

Suggested Citation

  • Marco Utili & Ciro Alberghi & Roberto Bonifetto & Luigi Candido & Aldo Collaku & Belit Garcinuño & Michal Kordač & Daniele Martelli & Rocco Mozzillo & Francesca Papa & David Rapisarda & Laura Savoldi , 2023. "Design and Integration of the WCLL Tritium Extraction and Removal System into the European DEMO Tokamak Reactor," Energies, MDPI, vol. 16(13), pages 1-27, July.
    • Handle: RePEc:gam:jeners:v:16:y:2023:i:13:p:5231-:d:1189181
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    Cited by:

    1. Francesca Papa & Alessandro Venturini & Gianfranco Caruso & Serena Bassini & Chiara Ciantelli & Angela Fiore & Vincenzo Cuzzola & Antonio Denti & Marco Utili, 2023. "Manufacturing of PAV-ONE, a Permeator against Vacuum Mock-Up with Niobium Membrane," Energies, MDPI, vol. 16(14), pages 1-12, July.

    More about this item

    Keywords

    TER; WCLL BB; DEMO; ITER; PAV; GLC;
    All these keywords.

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