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

Marco Utili (), Ciro Alberghi, Roberto Bonifetto, Luigi Candido, Aldo Collaku, Belit Garcinuño, Michal Kordač, Daniele Martelli, Rocco Mozzillo, Francesca Papa, David Rapisarda, Laura Savoldi, Fernando R. Urgorri, Domenico Valerio and Alessandro Venturini
Additional contact information
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

Energies, 2023, vol. 16, issue 13, 1-27

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.

Keywords: TER; WCLL BB; DEMO; ITER; PAV; GLC (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2023
References: View complete reference list from CitEc
Citations: View citations in EconPapers (1)

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