Long-term fuel retention in JET ITER-like wall

K. Heinola*, A. Widdowson, J. Likonen, E. Alves, A. Baron-Wiechec, N. Barradas, S. Brezinsek, N. Catarino, P. Coad, S. Koivuranta, S. Krat, G. F. Matthews, M. Mayer, P. Petersson, L. Aho-Mantila, M. Airila, O. Asunta, C. S. Chang, S. Collins, J. ErikssonL. G. Eriksson, J. Evans, X. Gao, M. Groth, A. Hakola, A. R. Horton, M. Hughes, J. Karhunen, T. Koskela, T. Kurki-Suonio, S. Lee, G. Liu, Y. Liu, J. Lopez, J. Lopez, T. Makkonen, D. L. Martin, J. Miettunen, S. Moradi, D. Moulton, S. Ranjan, A. Salmi, M. I. K. Santala, C. Silva, A. Sinha, P. Siren, T. J. Smith, Y. Sun, P. Thomas, L. Yao, JET Contributors

*Corresponding author for this work

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Post-mortem studies with ion beam analysis, thermal desorption, and secondary ion mass spectrometry have been applied for investigating the long-term fuel retention in the JET ITER-like wall components. The retention takes place via implantation and co-deposition, and the highest retention values were found to correlate with the thickness of the deposited impurity layers. From the total amount of retained D fuel over half was detected in the divertor region. The majority of the retained D is on the top surface of the inner divertor, whereas the least retention was measured in the main chamber on the mid-plane of the inner wall limiter. The recessed areas of the inner wall showed significant contribution to the main chamber total retention. Thermal desorption spectroscopy analysis revealed the energetic T from DD reactions being implanted in the divertor. The total T inventory was assessed to be >0.3 mg.

Original languageEnglish
Article number014075
Number of pages7
JournalPhysica Scripta
VolumeT167
DOIs
Publication statusPublished - 20 Feb 2016
MoE publication typeA1 Journal article-refereed
EventInternational Conference on Plasma-Facing Materials and Components for Fusion Applications - Aix-en-Provence, France
Duration: 18 May 201522 May 2015
Conference number: 15

Keywords

  • fusion energy
  • fuel retention
  • ion beam analysis
  • TDS
  • deposition

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