Characterisation of flakes generated in JET after DD and DT plasma operations

被引:28
作者
Bekris, N
Coad, JP
Penzhorn, RD
Knipe, S
Doerr, L
Rolli, R
Nägele, W
机构
[1] Forschungszentrum Karlsruhe, EURATOM Assoc, Tritium Lab, D-76021 Karlsruhe, Germany
[2] Culham Sci Ctr, UKAEA Fus Assoc, EURATOM, Abingdon OX14 3DB, Oxon, England
[3] Forschungszentrum Karlsruhe, EURATOM Assoc, D-76021 Karlsruhe, Germany
关键词
carbon films; codeposition/tritium; erosion/deposition; flakes; JET divertor tiles;
D O I
10.1016/j.jnucmat.2004.09.072
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Approximately 1 g of the 150 g collected at the JET was send to the Tritium Laboratory Karlsruhe (TLK) for physico-chemical characterisation. The flakes were extensively analysed using several experimental tools, such as calorimetry, X-ray-diffraction, thermal desorption, helium pycnometry, scanning electron microscopy, etc. The specific surface area measurements according to the Brunauer-Emmett-Teller (BET) method, showed a value of about (4.7 +/- 0.3) m(2) g(-1) while their average tritium activity was estimated to be (1.17 +/- 0.1) TBq g(-1) (i.e. 3-3.3 mg of tritium per gram of flakes) and their average real density (1.69 +/- 0.02) g cm(-3). Based on these results we estimate that at the end of the remote tile exchange (RTE) at JET the 3.0 g of tritium which did not return to the AGHS after the DTE1 remained in the vessel mainly in form of flakes, i.e. approximately (950 +/- 80) g of flakes are still inside the machine. (c) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:659 / 663
页数:5
相关论文
共 15 条
[1]   Tritium retention and clean-up in JET [J].
Andrew, P ;
Brennan, PD ;
Coad, JP ;
Ehrenberg, J ;
Gadeberg, M ;
Gibson, A ;
Hillis, DL ;
How, J ;
Jarvis, ON ;
Jensen, H ;
Lässer, R ;
Marcus, F ;
Monk, R ;
Morgan, P ;
Orchard, J ;
Peacock, A ;
Pearce, R ;
Pick, M ;
Rossi, A ;
Schild, P ;
Schunke, B ;
Stork, D .
FUSION ENGINEERING AND DESIGN, 1999, 47 (2-3) :233-245
[2]  
BEKRIS N, 2003, 6858 FZK
[3]  
BOYER D, 1996, FUS TECHNOL, P1751
[4]   Dust characterization and analysis in Tore-Supra [J].
Chappuis, P ;
Tsitrone, E ;
Mayne, M ;
Armand, X ;
Linke, H ;
Bolt, H ;
Petti, D ;
Sharpe, JP .
JOURNAL OF NUCLEAR MATERIALS, 2001, 290 :245-249
[5]   Erosion/deposition issues at JET [J].
Coad, JP ;
Bekris, N ;
Elder, JD ;
Erents, SK ;
Hole, DE ;
Lawson, KD ;
Matthews, GF ;
Penzhorn, RD ;
Stangeby, PC .
JOURNAL OF NUCLEAR MATERIALS, 2001, 290 :224-230
[6]  
FRANCIS AC, 1999, ANAL RESULTS DATA JE
[7]   Removal of codeposited layers by ECR discharge cleaning [J].
Jacob, W ;
Landkammer, B ;
Wu, CH .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :552-556
[8]   Tritium off-gassing trials on dust and flakes from the JET MKIIA divertor [J].
Knipe, SJ ;
Bell, AC ;
Brennan, PD ;
Coad, JP ;
Manning, CJ ;
Perevezentsev, AN .
FUSION ENGINEERING AND DESIGN, 2001, 58-59 :383-387
[9]   Non-destructive tritium measurements of Mk IIA divertor tile by BIXS [J].
Matsuyama, M ;
Bekris, N ;
Glugla, M ;
Noda, N ;
Philipps, V ;
Watanabe, K .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :491-495
[10]   Dust and flakes in the JET MkIIa divertor, analysis and results [J].
Peacock, AT ;
Andrew, P ;
Cetier, P ;
Coad, JP ;
Federici, G ;
Hurd, FH ;
Pick, MA ;
Wu, CH .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :423-428