JET contributions to ITER technology issues

被引：7

作者：

Grisolia, C ^{[1
]}

Rosanvallon, S

Coad, P

Bekris, N

Braet, J

Brennan, D

Brichard, B

Counsell, G

Day, C

Likonen, J

Piazza, G

Poletiko, C

Rubel, M

Semerok, A

机构：

[1] CEN Cadarache, EURATOM Assoc, DSM, DRFC, F-13108 St Paul Les Durance, France

[2] EFDA Close Support Unit, Culham Sci Ctr, Abingdon OX14 43DB, Oxon, England

[3] UKAEA, EURATOM Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England

[4] Forschungszentrum Karlsruhe, EURATOM Assoc, D-76021 Karlsruhe, Germany

[5] CEN SCK, EURATOM Assoc, B-2400 Mol, Belgium

[6] EURATOM, TEKES, VTT Proc, FIN-02044 Espoo, Finland

[7] CEN Cadarache, DEN, DTN, EURATOM Assoc, F-13108 St Paul Les Durance, France

[8] EURATOM, Royal Inst Technol, Alfven Lab, S-10044 Stockholm, Sweden

[9] CEA Saclay, EURATOM Assoc, F-91191 Gif Sur Yvette, France

来源：

FUSION ENGINEERING AND DESIGN | 2006年 / 81卷 / 1-7期

关键词：

ITER; JET; technology; tritium inventory control; R&D program;

D O I：

10.1016/j.fusengdes.2005.08.033

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 Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore is best suited to the study of tritium and fusion-related issues. A large variety of activities are performed within the JET fusion technology task force (FT-TF). In this paper, some topics such as erosion/deposition and material transport, characterisation of flakes and detritiation techniques are highlighted. Recent examples of results obtained on waste management studies are also given. Data on some ITER-relevant components that have been tested at JET, such as a pumping cryopanel and hardened optics fibers, are presented. In all fields, the work to be addressed in future JET work programmes is discussed. (c) 2005 Elsevier B.V. All rights reserved.

引用

页码：149 / 154

页数：6

共 7 条

[1] Characterisation of flakes generated in JET after DD and DT plasma operations [J].

Bekris, N ;

Coad, JP ;

Penzhorn, RD ;

Knipe, S ;

Doerr, L ;

Rolli, R ;

Nägele, W .

JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :659-663

[2]

DAY C, 2004, P 7 TRIT SCI TECHN C

[3] The removal of co-deposited hydrocarbon films from plasma facing components using high-power pulsed flashlamp irradiation [J].

Gibson, KJ ;

Counsell, GF ;

Curran, C ;

Forrest, MJ ;

Kay, MJ ;

Watkins, KG .

JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :565-569

[4] Beryllium accumulation at the inner divertor of JET [J].

Likonen, J ;

Vainonen-Ahlgren, E ;

Coad, JP ;

Zilliacus, R ;

Renvall, T ;

Hole, DE ;

Rubel, M ;

Arstila, K ;

Matthews, GF ;

Stamp, M .

JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :60-64

[5] Material migration in divertor tokamaks [J].

Matthews, GF .

JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :1-9

[6]

POLETIKO C, 2004, P 7 TRIT SCI TECHN C

[7]

ROSANVALLON S, 2004, P 7 TRIT SCI TECHN C

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