TRITIUM PROCESSING FOR THE EUROPEAN TEST BLANKET SYSTEMS: CURRENT STATUS OF THE DESIGN AND DEVELOPMENT STRATEGY

被引:4
作者
Ricapito, I. [1 ]
Calderoni, P. [1 ]
Poitevin, Y. [1 ]
Aiello, A. [2 ]
Utili, M. [2 ]
Demange, D. [3 ]
机构
[1] Fus Energy, Barcelona 08019, Spain
[2] ENEA, I-40032 Camugnano, Bo, Italy
[3] Karlsruhe Inst Technol, D-76021 Karlsruhe, Germany
关键词
Availability - Binary alloys - Breeding blankets - Lead alloys - Breeder reactors - Helium - Lithium alloys;
D O I
10.13182/FST14-T75
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
Tritium processing technologies of the two European Test Blanket Systems (TBS), HCLL (Helium Cooled Lithium Lead) and HCPB (Helium Cooled Pebble Bed), play an essential role in meeting the main objectives of the TBS experimental campaign in ITER. The compliancy with the ITER interface requirements, in terms of space availability, service fluids, limits on tritium release, constraints on maintenance, is driving the design of the TBS tritium processing systems. Other requirements come from the characteristics of the relevant TBM and the scientific programme that has to be developed and implemented. This paper identifies the main requirements for the design of the TBS tritium systems and equipment and, at the same time, provides an updated overview on the current design status, mainly focusing onto the tritium extractor from Pb-16Li and TBS tritium accountancy. Considerations are also given on the possible extrapolation to DEMO breeding blanket.
引用
收藏
页码:543 / 546
页数:4
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Ricapito, I. ;
Bede, O. ;
Boccaccini, L. V. ;
Ciampichetti, A. ;
Ghidersa, B. ;
Guerrini, L. ;
Laesser, R. ;
Neuberger, H. ;
Poitevin, Y. ;
Salavy, J. F. .
FUSION ENGINEERING AND DESIGN, 2010, 85 (7-9) :1154-1161