Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO

被引:28
作者
Garcinuno, Belit [1 ]
Rapisarda, David [1 ]
Fernandez, Ivan [1 ,2 ,3 ]
Moreno, Carlos [1 ]
Palermo, Iole [1 ]
Ibarra, Angel [1 ]
机构
[1] CIEMAT, LNF, Madrid, Spain
[2] UNED, Fdn Ingn Energet, Madrid, Spain
[3] UNED, Dept Ingn Energet, Madrid, Spain
关键词
Fusion; DCLL; Tritium; Permeation against vacuum; Membrane; HYDROGEN PERMEABILITY; COMPATIBILITY; DEUTERIUM; CORROSION;
D O I
10.1016/j.fusengdes.2016.06.036
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
One of the most important issues in future fusion power plants is the extraction of tritium generated in the breeders in order to achieve self-sufficiency. When the breeder is a liquid metal one of the most promising techniques is the Permeation Against Vacuum, whose principle is based on tritium diffusion through a permeable membrane in contact with the liquid metal carrier and its further extraction by a vacuum pump. A conceptual design of permeator has been developed, taking into account the features of a DEMO reactor with a Dual Coolant Lithium Lead (DCLL) breeder blanket. The study is based on the analysis of different membranes and geometries aiming at the overall efficiency (extraction capability) of the device, as well as its compatibility with the breeder material. The permeator is based on a rectangular section multi-channel distribution where the liquid metal channels and vacuum channels are alternated in order to maximize the contact area and therefore to promote tritium transport from the bulk to the walls. The resulting permeator design has an excellent estimated extraction efficiency, of 80%, in a relatively compact device. (C) 2016 EURATOM. Published by Elsevier B.V. All rights reserved.
引用
收藏
页码:226 / 231
页数:6
相关论文
共 26 条
[1]   Initial DEMO tokamak design configuration studies [J].
Bachmann, Christian ;
Aiello, G. ;
Albanese, R. ;
Ambrosino, R. ;
Arbeiter, F. ;
Aubert, J. ;
Boccaccini, L. ;
Carloni, D. ;
Federici, G. ;
Fischer, U. ;
Kovari, M. ;
Li Puma, A. ;
Loving, A. ;
Maione, I. ;
Mattei, M. ;
Mazzone, G. ;
Meszaros, B. ;
Palermo, I. ;
Pereslavtsev, P. ;
Riccardo, V. ;
Sardain, P. ;
Taylor, N. ;
Villari, S. ;
Vizvary, Z. ;
Vaccaro, A. ;
Visca, E. ;
Wenninger, R. .
FUSION ENGINEERING AND DESIGN, 2015, 98-99 :1423-1426
[2]  
Basile A, 2013, WOODHEAD PUBL SER EN
[3]  
Crank J., 1975, The Mathematics of Diffusion, V2nd
[4]   HYDROGEN-PERMEABLE METAL MEMBRANES FOR HIGH-TEMPERATURE GAS SEPARATIONS [J].
EDLUND, D ;
FRIESEN, D ;
JOHNSON, B ;
PLEDGER, W .
GAS SEPARATION & PURIFICATION, 1994, 8 (03) :131-136
[5]   Compatibility of refractory metals and beryllium with molten Pb-17Li [J].
Feuerstein, H ;
Grabner, H ;
Oschinski, J ;
Horn, S .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :1383-1386
[6]   Corrosion behaviour of Al based tritium permeation barriers in flowing Pb-17Li [J].
Glasbrenner, H ;
Konys, J ;
Voss, Z ;
Wedemeyer, O .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :1360-1363
[7]  
Gnanasekaran T, 2012, WOODHEAD PUBL SER EN, P301
[8]   Microstructure and hydrogen permeability in Nb-Ti-Co multiphase alloys [J].
Hashi, K. ;
Ishikawa, K. ;
Matsuda, T. ;
Aoki, K. .
JOURNAL OF ALLOYS AND COMPOUNDS, 2006, 425 (1-2) :284-290
[9]   VACUUM PERMEATOR ANALYSIS FOR EXTRACTION OF TRITIUM FROM DCLL BLANKETS [J].
Humrickhouse, Paul W. ;
Merrill, Brad J. .
FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (02) :295-302
[10]   HYDROGEN AND DEUTERIUM TRANSPORT THROUGH TYPE-304 STAINLESS-STEEL AT ELEVATED-TEMPERATURES [J].
KATSUTA, H ;
FURUKAWA, K .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1981, 18 (02) :143-151