Studies of tritiated co-deposited layers in TFTR

Skinner, C.H.; Gentile, C.; Ascione, G.; Carpe, A.; Causey, R.A.; Hayashi, T.; Hogan, J.; Langish, S.; Nishi, M.; Shu, W.M.; Wampler, W.R.; Young, K. M.

doi:10.1016/s0022-3115(00)00643-7

Cited by 50 publications

(36 citation statements)

References 19 publications

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“…The TFTR inner wall limiter provided a large source of eroded carbon and 51% of the injected tritium was co-deposited on the limiter and vessel wall during plasma operations. This was in line with the prior experience with deuterium [15] and consistent with first principles calculations [14,16]. In JET, 35 g of tritium was injected into diverted plasmas over a 6 month campaign, mostly by gas puffing [17].…”

Section: Tritium Retentionsupporting

confidence: 83%

Is Carbon a Realistic Choice for ITER's Divertor?

Skinner¹,

Federici²

2005

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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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Section: Tritium Retentionsupporting

confidence: 83%

Is Carbon a Realistic Choice for ITER's Divertor?

Skinner¹,

Federici²

2005

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“…A large fraction of tritium was retained during DT plasma operations in TFTR and JET [6,7] and a comparison shows striking similarities and contrasts [8]. Tritium was retained by co-deposition with eroded carbon and by isotope exchange with previously retained deuterium ( fig.…”

Section: Tritium Experience In Contemporary Tokamaksmentioning

confidence: 98%

Tritium Issues in Next Step Devices

Skinner¹,

Federici²

2001

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“…Both machines observed that tritium retention in graphite is a serious concern. After extensive efforts to remove the tritium, 16% of the tritium, which went into the torus, remained inside the TFTR vacuum chamber and 12% in JET [89][90][91][92][93]. This is an unacceptable retention rate for future-burning plasma experiments and has motivated the development of novel in-situ techniques.…”

Section: Technology Associated With Deuterium-tritium Experimentsmentioning

confidence: 99%

Review of D-T Experiments Relevant to Burning Plasma Issues

Hawryluk¹

2001

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Progress in the performance of tokamak devices has enabled not only the production of significant bursts of fusion energy from deuterium-tritium (D-T) plasmas in the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET) but, more importantly, the initial study of the physics of burning magnetically confined plasmas. TFTR and JET, in conjunction with the worldwide fusion effort, have studied a broad range of topics including magnetohydrodynamic stability, transport, wave-particle interactions, the confinement of energetic particles, and plasma boundary interactions. D-T experiments differ in three principal ways from previous experiments: isotope effects associated with the use of deuterium-tritium fuel, the presence of fusion-generated alpha particles, and technology issues associated with tritium handling and increased activation. The effect of deuteriumtritium fuel and the presence of alpha particles is reviewed and placed in the perspective of the much larger worldwide database using deuterium fuel and theoretical understanding.Both devices have contributed substantially to addressing the scientific and technical issues associated with burning plasmas. However, future burning plasma experiments will operate with larger ratios of alpha heating power to auxiliary power and will be able to access additional alpha-particle physics issues. The scientific opportunities for extending our understanding of burning plasmas beyond that provided by current experiments is described.

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Studies of tritiated co-deposited layers in TFTR

Cited by 50 publications

References 19 publications

Is Carbon a Realistic Choice for ITER's Divertor?

Is Carbon a Realistic Choice for ITER's Divertor?

Tritium Issues in Next Step Devices

Review of D-T Experiments Relevant to Burning Plasma Issues

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