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