Design and qualification of an on-line permeator for the recovery of tritium from lead-lithium eutectic breeding alloy

被引：12

作者：

Veredas, G. ^{[1
]}

Fradera, J. ^{[2
]}

Fernandez, I. ^{[1
]}

Batet, L. ^{[2
]}

Penalva, I. ^{[3
]}

Mesquida, L. ^{[4
]}

Abella, J. ^{[4
]}

Sempere, J. ^{[4
]}

Martinez, I. ^{[5
]}

Herrazti, B. ^{[5
]}

Sedano, L. ^{[1
]}

机构：

[1] EURATOM CIEMAT Fus Assoc, Breeding Blanket Tech Unit, E-28040 Madrid, Spain

[2] Tech Univ Catalonia UPC, Dept Phys & Nucl Engn, E-08028 Barcelona, Spain

[3] Univ Basque Country, Dept Nucl Engn & Fluid Mech, E-48103 Bilbao, Spain

[4] Univ Ramon Llull, ETS Inst Quim Sarria, E-08017 Barcelona, Spain

[5] SENER Ingn & Sistemas, E-08025 Barcelona, Spain

来源：

FUSION ENGINEERING AND DESIGN | 2011年 / 86卷 / 9-11期

关键词：

Tritium breeding; Tritium self-sufficiency; Tritium recovery; Permeator;

D O I：

10.1016/j.fusengdes.2011.03.077

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：

The fast and efficient recovery of bred tritium represents a major milestone of tritium breeding technologies R&D and is key for the demonstration of fusion reactor fuel self-sufficiency. For lead-lithium eutectic, diverse technologies are currently being investigated and qualified. Permeator Against Vacuum (PAV) solution represents a firm candidate because: (i) runs as a single-step process for tritium on-line recovery, (ii) works passively allowing to be thermally governed, (iii) can be easily in-pipe integrated in Pb15.7Li loop systems and (iv) can be conceived with high compactness. An optimal design of a PAV requires a detailed hydraulic design optimization for established operational ranges. An optimal PAV design is proposed and qualified by numerical simulation. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：2365 / 2369

页数：5

共 37 条

[1] Design of a permeator against vacuum for tritium extraction from eutectic lithium-lead in a DCLL DEMO
Garcinuno, Belit
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Moreno, Carlos
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FUSION ENGINEERING AND DESIGN, 2017, 117 : 226 - 231
[2] The solubility of helium in lead-lithium eutectic alloy
Sedano, L.
Esteban, G. A.
Cavaro, M.
Iraola, E.
Abdulrahman, A.
Batet, L.
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NUCLEAR MATERIALS AND ENERGY, 2022, 31
[3] Experimental Qualification of New Instrumentation for Lead-Lithium Eutectic in IELLLO Facility
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FUSION ENGINEERING AND DESIGN, 2020, 156 (156)
[4] MHD TECHNIQUE FOR PRODUCTION OF LEAD-LITHIUM EUTECTIC ALLOY
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Freibergs, F. E.
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[5] Interaction of tritium and helium with lead-lithium eutectic under reactor irradiation
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Zaurbekova, Zhanna
Tulubayev, Eugeniy
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[6] Evaluation of the response time of H-concentration probes for tritium sensors in lead-lithium eutectic alloy
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Abella, J.
FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 1397 - 1401
[7] Temperature dependence of the liquid eutectic lead-lithium alloy density
Alchagirov Boris B.
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[8] Tritium Extraction from Lithium-Lead Eutectic Alloy: Experimental Characterization of a Permeator against Vacuum Mock-Up at 450?
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ENERGIES, 2023, 16 (07)
[9] Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility
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Rapisarda, David
Fernandez-Berceruelo, Ivan
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FUSION ENGINEERING AND DESIGN, 2017, 124 : 871 - 875
[10] Experimental design of tritium extraction loop from lead lithium eutectic
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