Tritium Extraction Systems for the European HCLL/HCPB TBMs

被引：15

作者：

Ricapito, I. ^{[1
]}

Ciampichetti, A. ^{[2
]}

Benamati, G. ^{[1
]}

Zucchetti, M. ^{[2
]}

机构：

[1] CR Brasimone, ENEA FPN FISING, I-40033 Camugnano, Bo, Italy

[2] Politecn Torino, DENER, I-10129 Turin, Italy

来源：

FUSION SCIENCE AND TECHNOLOGY | 2008年 / 54卷 / 01期

关键词：

D O I：

10.13182/FST08-A1775

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 challenging issues for the TBM (Test Blanket Module) testing campaign foreseen in ITER is the operation of TES (Tritium Extraction Systems). This is essential not only to prove the ability to manage correctly the bred tritium but also to validate and qualify the neutronic codes for the prediction of tritium production in view of their use in future fusion plants. Two are the European candidates to be tested in ITER: the HCPB (Helium Cooled Pebble Bed) TBM and the HCLL (Helium Cooled Lithium Lead) TBM. For both these TBM concepts the following points have been addressed in this work: a) the gas stream to be processed by TES b) the TES process flow diagram c) a first assessment of the required space.

引用

页码：107 / 112

页数：6

共 8 条

[1]

Boccaccini L.V., 2005, DESIGN DESCRIPTION D

[2] The European test blanket module systems:: Design and integration in ITER [J].

Boccaccini, LV ;

Salavy, JF ;

Lässer, R ;

Puma, AL ;

Meyder, R ;

Neuberger, H ;

Poitevin, Y ;

Rampal, G .

FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :407-414

[3] Strategy for the blanket testing in ITER [J].

Boccaccini, LV ;

Fischer, U ;

Kleefeldt, K ;

Malang, S ;

Schleisiek, K .

FUSION ENGINEERING AND DESIGN, 2002, 61-62 :423-429

[4]

BOCCACCINI LV, 2001, DESIGN DESCRIPTION D

[5]

DAUD WRW, 2001, P 2 AS OC DRY C BAT

[6]

LAESSER R, 2004, P 7 INT C TRIT SCI T, V48, P337

[7]

MEYDER R, 2006, TW2TTBB001BDEL1D FZK

[8]

van Dissel S.C., 1998, INDIGENOUS KNOWLEDGE, V6, P8

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