The European Breeding Blanket Test Facility: An integrated device to test European helium cooled TBMs in view of ITER

被引：16

作者：

Utili, M. ^{[1
]}

Tincani, A. ^{[1
]}

Aiello, A. ^{[1
]}

Ricapito, I. ^{[1
]}

Coccoluto, G. ^{[1
]}

机构：

[1] ENEA Brasimone, I-40032 Bologna, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2009年 / 84卷 / 7-11期

关键词：

EBBTF; DEMO; ITER;

D O I：

10.1016/j.fusengdes.2009.02.030

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 activities of testing and qualification of the two European Test Blanket Modules (TBMs) to be installed in ITER as well as their main ancillary circuits are of outstanding importance in view of the experimental activities planned during ITER lifetime. Having in mind this purpose the EBBTF has been designed and installed at ENEA Brasimone Research Centre in order to meet the important requirements coming directly from the scientific Communities to tests and qualify blanket components and technologies in view of ITER and DEMO reactors. ENEA is responsible for the activities of design, construction and installation of the system at ENEA Brasimone and for all of them different national companies have been involved. Essentially, EBBTF consists of the upgraded HeFus3 helium loop coupled with a new lead lithium loop named IELLLO (integrated European Lead Lithium LOop). The two loops working together will be able to test the HCLL and HCPB mock-up, up to 1:1 scale. The device and its original design solution are described in this paper. (c) 2009 Elsevier B.V. All rights reserved.

引用

页码：1881 / 1886

页数：6

共 50 条

[31] Hot Helium Leak Test of ITER blanket shield block
Leng, Zhen
Chen, Jiming
Wang, Kun
Wang, Pinghuai
Xu, Min
FUSION ENGINEERING AND DESIGN, 2020, 153
[32] European proposal for an ITER water-cooled solid breeder blanket
NET Team, Garching, Germany
Fusion Eng Des, pt A (423-429):
[33] The European ITER test blanket modules: Progress in development of fabrication technologies towards standardization
Zmitko, Milan
Thomas, Noel
LiPuma, Antonella
Forest, Laurent
Cogneau, Laurence
Rey, Joerg
Neuberger, Heiko
Poitevin, Yves
FUSION ENGINEERING AND DESIGN, 2016, 109 : 1687 - 1691
[34] Three-dimensional neutronics analysis of the European HCPB blanket test module in ITER
Fischer, U
Donne, MD
FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 835 - 842
[35] Design description and performance analyses of the European HCPB test blanket system in ITER feat
Boccaccini, LV
Bekris, N
Chen, Y
Fischer, U
Gordeev, S
Hermsmeyer, S
Hutter, E
Kleefeldt, K
Malang, S
Schleisiek, K
Schmuck, I
Schnauder, H
Tsige-Tamirat, H
FUSION ENGINEERING AND DESIGN, 2002, 61-62 : 339 - 344
[36] The European LGS test facility
Myers, R. M.
Calia, D. Bonaccini
Devaney, N.
Esposito, S.
Goodsell, S. J.
Goncharov, A.
Guerra, J. C.
de Chatellus, H. Guillet
Harrison, M. A.
Holzloehner, R.
Marchetti, E.
Morris, T. J.
Pinna, E.
Pique, J-P.
Rabien, S.
Reyes, M.
Ribak, E.
Rutten, R. G. M.
Schnetler, H.
Strachan, M.
Stuik, R.
Talbot, R. G.
Tulloch, S. M.
ASTRONOMICAL ADAPTATIVE OPTICS SYSTEMS AND APPLICATIONS III, 2007, 6691
[37] Design approach for the main ITER test blanket modules for the EU helium cooled lithium-lead blankets
Rampal, G
Gatelet, D
Giancarli, L
Laffont, G
Li-Puma, A
Salavy, JF
Rigal, E
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) : 695 - 700
[38] Study of the helium-cooled lithium lead test blanket module nuclear behaviour under irradiation in ITER
Chiovaro, P.
Di Maio, P. A.
Vella, G.
FUSION ENGINEERING AND DESIGN, 2009, 84 (12) : 2178 - 2186
[39] On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER
Chiovaro, P
Di Maio, PA
Oliveri, E
Vella, G
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) : 677 - 686
[40] Achievements of the ELISE test facility in view of the ITER NBI
Heinemann, B.
Wuenderlich, D.
Kraus, W.
Bonomo, F.
Fantz, U.
Froeschle, M.
Mario, I
Riedl, R.
Wimmer, C.
FUSION ENGINEERING AND DESIGN, 2019, 146 : 455 - 459

← 1 2 3 4 5 →