Reassessment of tritium content in CFC tiles exposed to the JET D-T campaign in 1997

被引:0
作者
Likonen, J. [1 ]
Bekris, N. [2 ]
Coad, J. P. [3 ]
Ayres, C. [3 ]
Gotts, N. [3 ]
Jepu, I. [3 ,4 ]
Zayachuk, Y. [3 ]
Widdowson, A. [3 ]
Wilson, I. [3 ]
Catarino, N. [5 ]
de Alves, E. [5 ]
JET Contributors
机构
[1] VTT Tech Res Ctr Finland, POB 1000, FIN-02044 Espoo, Finland
[2] Karlsruhe Inst Technol, Tritium Lab Karlsruhe IAP TLK, POB 76021, Karlsruhe, Germany
[3] United Kingdom Atom Energy Author, Culham Ctr Fus Energy, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[4] Natl Inst Laser Plasma & Radiat Phys NILPRP, Magurele 077125, Romania
[5] Univ Lisbon, Inst Super Tecn, IPFN, P-1049001 Lisbon, Portugal
基金
英国工程与自然科学研究理事会;
关键词
JET; Tritium retention; Deposition; Pyrolysis; TDS; DEPTH PROFILES; RETENTION; CARBON; DETRITIATION; BERYLLIUM; DIVERTOR;
D O I
10.1016/j.nme.2022.101312
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
In 2019 two MkIIA divertor tiles (6IN3 and 4BN4) exposed during DTE1 were retrieved at CCFE for Thermal Desorption Spectroscopy (TDS) and pyrolysis analyses. A set of samples were prepared using a coring technique. The highest tritium (T) inventories were found in the shadowed corner of the inner divertor due to asymmetric deposition. TDS analyses indicated that T is desorbed at rather high temperatures with maximum release peaks at-590 and 820 degrees C. A few samples were reannealed at 850 degrees C using the same heating procedure and it turned out that a further-40-50 % of T was still released indicating that the annealing procedure used does not empty the sample completely. Pyrolysis results for thin disks cut from the surface of the tile were somewhat higher than the corresponding TDS results. T amounts were also investigated as a function of depth from the tile surface up to a depth of-4.5 mm and T was detected at these depths. Comparison was also made with old results obtained with the pyrolysis technique and a PIN-diode method a few years after the DTE1 experiment, allowing for the natural decay and off-gassing of T. Our results agree within a factor of-3 with these results.
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共 18 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]   Thermal desorption spectrometry of beryllium plasma facing tiles exposed in the JET tokamak [J].
Baron-Wiechec, A. ;
Heinola, K. ;
Likonen, J. ;
Alves, E. ;
Catarino, N. ;
Coad, J. P. ;
Corregidor, V. ;
Jepu, I. ;
Matthews, G. F. ;
Widdowson, A. ;
Abduallev, S. ;
Abhangi, M. ;
Abreu, P. ;
Afzal, M. ;
Aggarwal, K. M. ;
Ahlgren, T. ;
Ahn, J. H. ;
Aho-Mantila, L. ;
Aiba, N. ;
Airila, M. ;
Albanese, R. ;
Aldred, V. ;
Alegre, D. ;
Alessi, E. ;
Aleynikov, P. ;
Alfier, A. ;
Alkseev, A. ;
Allinson, M. ;
Alper, B. ;
Alves, E. ;
Ambrosino, G. ;
Ambrosino, R. ;
Amicucci, L. ;
Amosov, V. ;
Sunden, E. Andersson ;
Angelone, M. ;
Anghel, M. ;
Angioni, C. ;
Appel, L. ;
Appelbee, C. ;
Arena, P. ;
Ariola, M. ;
Arnichand, H. ;
Arshad, S. ;
Ash, A. ;
Ashikawa, N. ;
Aslanyan, V. ;
Asunta, O. ;
Auriemma, F. ;
Austin, Y. .
FUSION ENGINEERING AND DESIGN, 2018, 133 :135-141
[3]   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
[4]   Tritium depth profiles in 2D and 4D CFC tiles from JET and TFTR [J].
Bekris, N ;
Skinner, CH ;
Berndt, U ;
Gentile, CA ;
Glugla, M ;
Schweigel, B .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :501-506
[5]   Ex-situ tritium removal from JET tiles using RF inductive heating [J].
Bekris, N. ;
Coad, J. R. ;
Sugiyama, K. ;
Caldwell-Nichols, C. ;
Tanabe, T. ;
Kloppe, B. ;
Rolli, R. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :1137-1141
[6]   Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data [J].
Catarino, N. ;
Barradas, N. P. ;
Corregidor, V. ;
Widdowson, A. ;
Baron-Wiechec, A. ;
Coad, J. P. ;
Heinola, K. ;
Rubel, M. ;
Alves, E. ;
Abhangi, M. ;
Abreu, P. ;
Aftanas, M. ;
Afzal, M. ;
Aggarwal, K. M. ;
Aho-Mantila, L. ;
Ahonen, E. ;
Aints, M. ;
Airila, M. ;
Albanese, R. ;
Alegre, D. ;
Alessi, E. ;
Aleynikov, P. ;
Alfier, A. ;
Alkseev, A. ;
Allan, P. ;
Almaviva, S. ;
Alonso, A. ;
Alper, B. ;
Alsworth, I. ;
Alves, D. ;
Ambrosino, G. ;
Ambrosino, R. ;
Amosov, V. ;
Andersson, F. ;
Andersson Sunden, E. ;
Angelone, M. ;
Anghel, A. ;
Anghel, M. ;
Angioni, C. ;
Appel, L. ;
Apruzzese, G. ;
Arena, P. ;
Ariola, M. ;
Arnichand, H. ;
Arnoux, G. ;
Arshad, S. ;
Ash, A. ;
Asp, E. ;
Asunta, O. ;
Atanasiu, C. V. .
NUCLEAR MATERIALS AND ENERGY, 2017, 12 :559-563
[7]   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
[8]  
Dörr L, 2005, FUSION SCI TECHNOL, V48, P358
[9]   Preparation for commissioning of materials detritiation facility at Culham Science Centre [J].
Kresina, Michal ;
Decanis, Christelle ;
Newman, Mark ;
Clements, Christopher ;
Wilson, Ian ;
Coombs, David ;
Utard, Aurelien ;
Canas, Daniel ;
Abduallev, S. ;
Abhangi, M. ;
Abreu, P. ;
Afzal, M. ;
Aggarwal, K. M. ;
Ahlgren, T. ;
Ahn, J. H. ;
Aho-Mantila, L. ;
Aiba, N. ;
Airila, M. ;
Albanese, R. ;
Aldred, V. ;
Alegre, D. ;
Alessi, E. ;
Aleynikov, P. ;
Alfier, A. ;
Alkseev, A. ;
Allinson, M. ;
Alper, B. ;
Alves, E. ;
Ambrosino, G. ;
Ambrosino, R. ;
Amicucci, L. ;
Amosov, V. ;
Sunden, E. Andersson ;
Angelone, M. ;
Anghel, M. ;
Angioni, C. ;
Appel, L. ;
Appelbee, C. ;
Arena, P. ;
Ariola, M. ;
Arnichand, H. ;
Arshad, S. ;
Ash, A. ;
Ashikawa, N. ;
Aslanyan, V. ;
Asunta, O. ;
Auriemma, F. ;
Austin, Y. ;
Avotina, L. ;
Axton, M. D. .
FUSION ENGINEERING AND DESIGN, 2018, 136 :1391-1395
[10]   Deuterium retention in the divertor tiles of JET ITER-Like wall [J].
Lahtinen, A. ;
Likonen, J. ;
Koivuranta, S. ;
Hakola, A. ;
Heinola, K. ;
Ayres, C. F. ;
Baron-Wiechec, A. ;
Coad, J. P. ;
Widdowson, A. ;
Raisanen, J. ;
Abhangi, M. ;
Abreu, P. ;
Aftanas, M. ;
Afzal, M. ;
Aggarwal, K. M. ;
Aho-Mantila, L. ;
Ahonen, E. ;
Aints, M. ;
Airila, M. ;
Albanese, R. ;
Alegre, D. ;
Alessi, E. ;
Aleynikov, P. ;
Alfier, A. ;
Alkseev, A. ;
Allan, P. ;
Almaviva, S. ;
Alonso, A. ;
Alper, B. ;
Alsworth, I. ;
Alves, D. ;
Ambrosino, G. ;
Ambrosino, R. ;
Amosov, V. ;
Andersson, F. ;
Andersson Sunden, E. ;
Angelone, M. ;
Anghel, A. ;
Anghel, M. ;
Angioni, C. ;
Appel, L. ;
Apruzzese, G. ;
Arena, P. ;
Ariola, M. ;
Arnichand, H. ;
Arnoux, G. ;
Arshad, S. ;
Ash, A. ;
Asp, E. ;
Asunta, O. .
NUCLEAR MATERIALS AND ENERGY, 2017, 12 :655-661