Plasma wall interaction and tritium retention in TFTR

Skinner, C.H.; Amarescu, E.; Ascione, G.; Blanchard, W.; Barnes, Cris W.; Batha, S. H.; Beer, M; Bell, M.G.; Bell, R.E.; Bitter, M.; Bretz, N.; Budny, R.; Bush, C. E.; Camp, Roderic Ai; Casey, M.; Collins, J.; Cropper, M.; Chang, Z.; Darrow, D. S.; Duong, H. H.; Durst, R.; Efthimion, P. C.; Ernst, D. R.; Fisch, Nathaniel J.; Fonck, R. J.; Fredrickson, E. D.; Fu, G. Y.; Furth, H. P.; Gentile, C.; Gibson, Marc A.; Gilbert, J.; Grek, B.; Grisham, L.; Hammett, G. W.; Hawryluk, R. J.; Herrmann, H. W.; Hill, K. W.; Hosea, J.; Janos, A.; Jassby, D.L.; Jobes, F. C.; Johnson, D. W.; Johnson, L. C.; Kamperschroer, J.; Kalish, M.; Kugel, H.; Langford, J.; Langish, S.; LaMarche, P. H.; LeBlanc, B.; Levinton, F. M.; Machuzak, J. S.; Majeski, R.; Manikam, J.; Mansfield, D. K.; Mazzucato, E.; McGuire, K.; Mika, R.; McKee, G. W.; Meade, D. M.; Medley, S. S.; Mikkelsen, D. R.; Mynick, H.E.; Mueller, D.; Nagy, A.; Nazikian, R.; Ono, M.; Owens, D. K.; Park, H.; Paul, S. F.; Pearson, Gavin; Петров, М. П.; Phillips, C. K.; Raftopoulos, S.; Ramsey, A. T.; Raucci, R.; Redi, M. H.; Rewoldt, G.; Rogers, J. H.; Roquemore, A. L.; Ruskov, E.; Sabbagh, S.A.; Schilling, G.; Schivell, J.; Schmidt, G. L.; Scott, S. D.; Šesnić, S.; Stratton, B.; Strachan, J.D.; Stevenson, T. N.; Stotler, D.P.; Synakowski, E. J.; Takahashi, H.; Tang, W. M.; Taylor, G.; Tighe, W.; Timberlake, J.; Halle, A. von; Goeler, S. von; Walters, R.T.; White, R. B.; Wilson, J. R.; Winston, Julius; Wong, K. L.; Young, K. M.; Zarnstorff, M. C.; Zweben, S. J.

doi:10.1016/s0022-3115(97)80041-4

Cited by 38 publications

(10 citation statements)

References 59 publications

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“…In JET, post-mortem analysis also yields about a 4% retention rate, but gas balance integrated over experimental campaigns indicates retention of 6%, with no noticeable influence of the wall temperature (320 or 200°C) [32]. During the DT experiments in TFTR [33] and in JET (1997JET ( -1998 [34], the immediate T retention has been shown to be about 40%…”

Section: Discussionmentioning

confidence: 99%

Gas balance and fuel retention in fusion devices

et al. 2007

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The evaluation of hydrogenic retention in present tokamaks is of crucial importance to estimate the expected tritium (T) vessel inventory in ITER, limited from safety considerations to 350g. In the framework of the European Task Force on Plasma Wall Interaction (EU TF on PWI) efforts are underway to investigate gas balance and fuel retention during discharges, and to compare the data obtained with those from post-mortem analysis of in-vessel components exposed over whole experimental campaigns. This paper summarizes the principal findings from coordinated studies on gas balance and fuel retention from a number of European tokamaks, viz. ASDEX-Upgrade (AUG), JET, TEXTOR and Tore Supra (TS). For most devices, the long-term retention fraction deduced from integrated particle balance is ∼ 10-20 %. This is larger than the ~3-4% deduced from post mortem analysis of plasma facing components (PFCs). However, from the database available for tokamaks with their main PFCs made of carbon, the important conclusion is that the T inventory limit (set by the working guideline for operations) could be reached in ITER within fewer than 100 discharges. This, therefore, would seriously impact on operation of the device unless efficient T removal processes were developed.

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Section: Discussionmentioning

confidence: 99%

Gas balance and fuel retention in fusion devices

et al. 2007

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“…Graphite and several types of CFC have been used in toroidal devices since seventies of the 20th century because of their excellent power handling capabilities. Issues related to the erosion rates and the formation of fuel-rich co-deposits were known, but their dramatic seriousness was recognised after full D-T campaigns in TFTR [14,15] and JET [16][17][18][19][20][21] operated with carbon walls: nearly 30% of the injected tritium was retained in the vessel, especially in the remote areas of the divertor, i.e. places shadowed from the direct plasma line-of-sight.…”

Section: Controlled Fusion and Plasma-wall Interactions: Impact On Ma...mentioning

confidence: 99%

Accelerator techniques and nuclear data needs for ion beam analysis of wall materials in controlled fusion devices

et al. 2023

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A brief overview of ion beam analysis methods and procedures in studies of materials exposed to fusion plasmas in controlled fusion devices with magnetic confinement is presented. The role of accelerator techniques in the examination and testing of materials for fusion applications is emphasised. Quantitative results are based on robust nuclear data sets, i.e. stopping powers and reaction cross-sections. Therefore, the work has three major strands: (i) assessment of fuel inventory and modification of wall materials by erosion and deposition processes; (ii) equipment development to perform cutting-edge research; (iii) determination of nuclear data for selected ion-target combinations. Advantages and limitations of methods are addressed. A note is also given on research facilities with capabilities of handling radioactive and beryllium-contaminated materials.

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“…Several methods of T removal and vessel clean-up were tested at TFTR and JET following full D-T campaigns [24,28]: tokamak discharges in D 2 fuelled plasma, H and He glow discharge cleaning, venting with oxygen. Tokamak discharges and hydrogen glow aim at the D-T and H-T isotope exchange.…”

Section: Erosion Zone Deposition Zone Detached Flaking Co-depositmentioning

confidence: 99%

“…The retention of radioactive tritium causes the most severe problems because methods must still be developed to accomplish the efficient release of fuel and/or decomposition and removal of co-deposits in order to ensure safe and economical reactor operation. A range of concepts has been proposed and tested in laboratories [24][25][26][27] and also inside tokamaks [28][29][30]. Fig.…”

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confidence: 99%

Structure Materials in Fusion Reactors: Issues Related to Tritium, Radioactivity and Radiation-Induced Effects

Rubel

2012

Fusion Science and Technology

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A concise overview is given on materials applied in fusion technology. The influence of plasma operation on the behaviour of reactor components and diagnostic systems is discussed with emphasis on effects caused by fast particles reaching the reactor wall. Issues related to primary and induced radioactivity are reviewed: tritium inventory and transmutation. Tritium breeding in the reactor blanket, separation of hydrogen isotopes and safety aspects in handling radioactively contaminated components are also included.

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Plasma wall interaction and tritium retention in TFTR

Cited by 38 publications

References 59 publications

Gas balance and fuel retention in fusion devices

Gas balance and fuel retention in fusion devices

Accelerator techniques and nuclear data needs for ion beam analysis of wall materials in controlled fusion devices

Structure Materials in Fusion Reactors: Issues Related to Tritium, Radioactivity and Radiation-Induced Effects

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