Membrane gas-liquid contactor for tritium extraction from Pb-Li alloys

Fusion Engineering and Design - Tập 158 - Trang 111737 - 2020
Silvano Tosti1, Alfonso Pozio2, Luca Farina1, Marco Incelli1, Alessia Santucci1, David Alique3
1ENEA, FSN Dept., CR ENEA Frascati, Via E. Fermi 45, 00044, Frascati, RM, Italy
2ENEA, DTE Dept., CR ENEA Casaccia, Via Anguillarese 301, 00123, S. Maria di Galeria, RM, Italy
3Department of Chemical, Energy and Mechanical Technology, Rey Juan Carlos University, c/ Tulipán s/n, 28933 Móstoles, Spain

Tài liệu tham khảo

Federici, 2019, An overview of the EU breeding blanket design strategy as an integral partof the DEMO design effort, Fusion Eng. Des., 141, 30, 10.1016/j.fusengdes.2019.01.141 Boccaccini, 2016, Objectives and status of EUROfusion DEMO blanket studies, Fusion Eng. Des., 109–111, 1199, 10.1016/j.fusengdes.2015.12.054 S.Fukada, 2018, Study of hydrogen recovery from Li-Pb using packed tower, Fusion Eng. Des., 135, 74, 10.1016/j.fusengdes.2018.07.016 Kinjo, 2017, Experiment on recovery of hydrogen isotopes from Li17Pb83 blanket by liquid-gas contact, Fusion Sci. Technol., 71, 520, 10.1080/15361055.2017.1293426 Alpy, 2000, Hydrogen extraction from Pb–17Li: results with a 800 mm high packed column, Fusion Eng. Des., 49–50, 775, 10.1016/S0920-3796(00)00461-0 Sacristán, 2012, Design, performance and manufacturing analysis for a compact permeator, Fusion Eng. Des., 87, 1495, 10.1016/j.fusengdes.2012.03.044 Martínez, 2012, Optimizing tritium extraction from a Permeator Against Vacuum (PAV) by dimensional design using different tritium transport modeling tools, Fusion Eng. Des., 87, 1466, 10.1016/j.fusengdes.2012.03.035 Park, 2018, The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C, Fusion Eng. Des., 136, 623, 10.1016/j.fusengdes.2018.03.042 Garcinuno, 2017, Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility, Fusion Eng. Des., 124, 871, 10.1016/j.fusengdes.2017.02.060 Tosti, 2018, Membrane processes for the nuclear fusion fuel cycle, Membranes, 8, 96, 10.3390/membranes8040096 A. Pozio, S. Tosti, F. Marini, Processo a supporto poroso per l’estrazione di idrogeno ed isotopi da metalli liquidi, e relativo apparato, Italian Patent Grant n. 102018000003185 (23.03.2020, priority 01.03.2018). Mas de les Valls, 2008, Lead-lithium eutectic material database for nuclear fusion technology, J. Nucl. Phys. Mater. Sci. Radiat. Appl., 376, 353 Furones, 2018, Interlayer properties of in-situ oxidized porous stainless steel for preparation of composite Pd membranes, ChemEngineering, 2, 10.3390/chemengineering2010001 Batistoni, 2012, Neutronics experiments for uncertainty assessment of tritium breeding in HCPB and HCLL blanketmock-ups irradiated with 14MeV neutrons, Nucl. Eng., 52 Reiter, 1991, Solubility and diffusivity of hydrogen isotopes in liquid Pb-17Li, Fusion Eng. Des., 14, 207, 10.1016/0920-3796(91)90003-9 Fukada, 2017, Experiment to recover tritium from Li-Pb blanket and understanding chemistry of the Li17Pb83–H system, Fusion Sci. Technol., 72, 374 Tosti, 2017, Ceramic membranes for processing plasma enhancement gases, Fusion Eng. Des., 124, 928, 10.1016/j.fusengdes.2017.01.010 Terai, 1991, Mass transfer coefficient of tritium from molten lithium-lead alloy (Li17Pb83) to environmental gas under neutron irradiation, Fusion Eng. Des., 17, 237, 10.1016/0920-3796(91)90064-W Volkl, 1975, Hydrogen diffusion in metals, 303 Forcey, 1990, Investigation of structure dependence of diffusivity, solubility, and permeability of hydrogen in hot rolled low carbon steels, Mater. Sci. Technol., 6, 357, 10.1179/mst.1990.6.4.357