Thermal Response of Tritiated Codeposits from JET and TFTR to Transient Heat Pulses

Skinner, C.H.; Bekris, N.; Coad, J. P.; Gentile, C.; Hassanein, A.; Reiswig, R.D.; Willms, S.

doi:10.1238/physica.topical.103a00034

Cited by 32 publications

(13 citation statements)

References 13 publications

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“…5. (1) The matrix areas contain voids [19] that can trap codeposited tritium more effectively than the fiber bundles. (2) Since the crystal perfection of such matrix carbon is generally poorer than that of the carbon fiber (in other words, carbon matrix is softer than fiber), the matrix areas are very likely to be eroded preferentially, resulting in dug area.…”

Section: Discussionmentioning

confidence: 99%

Measurement of Tritium Surface Distribution on TFTR Bumper Limiter Tiles

Sugiyama

Tanabe

Skinner

et al. 2004

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The tritium surface distribution on graphite tiles used in the TFTR bumper limiter and exposed to TFTR D-T discharges from 1993 to 1997 was measured by the Tritium Imaging Plate Technique (TIPT). The TFTR bumper limiter shows both re-/co-deposition and erosion. The tritium images for all tiles measured are strongly correlated with erosion and deposition patterns, and long-term tritium retention was found in the re-/co-depositions and flakes.The CFC tiles located at erosion dominated areas clearly showed their woven structure in their tritium images owing to different erosion yields between fibers and matrix. Significantly high tritium retention was observed on all sides of the erosion tiles, indicating carbon transport via repetition of local erosion/deposition cycles.

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Section: Discussionmentioning

confidence: 99%

Measurement of Tritium Surface Distribution on TFTR Bumper Limiter Tiles

Sugiyama

Tanabe

Skinner

et al. 2004

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“…Several other methods for tritium and co-deposit removal have been proposed and tested under laboratory conditions. They are based on chemical decomposition (H and He glow plasma with water vapour [25], O 2 -He glow [29]), pulsed irradiation [26,27] or mechanical treatment of surfaces with co-deposits [36]. Irradiation with a laser [27] or flash light [29] stimulates desorption of H isotopes and disintegration of co-deposits.…”

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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“…While helpful, this would not resolve the problem and retention predictions still need to be validated against experiments in detached plasmas. The likely formation of new mixed materials on plasma facing surfaces adds further uncertainties [1,26,27]. To minimise risk ITER should have the capability for rapidly and efficiently removing the worst credible level of tritium retention (a capability to remove just the most likely, median estimate of retention implies a 50% risk it will be insufficient).…”

Section: How Well Is the Underlying Physics Understood ?mentioning

confidence: 99%

Is carbon a realistic choice for ITER's divertor?

Skinner¹,

Federici²

2006

Phys. Scr.

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Tritium retention by codeposition with carbon on the divertor target plate is predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of codeposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.

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Thermal Response of Tritiated Codeposits from JET and TFTR to Transient Heat Pulses

Cited by 32 publications

References 13 publications

Measurement of Tritium Surface Distribution on TFTR Bumper Limiter Tiles

Measurement of Tritium Surface Distribution on TFTR Bumper Limiter Tiles

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

Is carbon a realistic choice for ITER's divertor?

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