Enhanced D-T supershot performance at high current using extensive lithium conditioning in TFTR

Mansfield, D.K.; Strachan, J.D.; Bell, M.G.; Scott, S.D.; Budny, R.; Bell, R.E.; Bitter, M.; Darrow, D.S.; Fredrickson, E. D.; Grek, B.

doi:10.2172/64326

Cited by 3 publications

(3 citation statements)

References 11 publications

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“…[8][9][10] The added lithium yielded unanticipated improvements in energy confinement time, fusion power, stored energy, and the Lawson triple product nT E . 11,12 Since then, lithium has been used in CDX-U 13 , FTU 14 , DIII-D 15 , TJ-II 16 , T-11M 17 , EAST 18 , and NSTX. 19 NSTX has pioneered and advanced lithium wall conditioning over a phased effort.…”

Section: Introductionmentioning

confidence: 99%

Differentiating the role of lithium and oxygen in retaining deuterium on lithiated graphite plasma-facing components

et al. 2014

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Laboratory experiments have been used to investigate the fundamental interactions responsible for deuterium retention in lithiated graphite. Oxygen was found to be present and play a key role in experiments that simulated NSTX lithium conditioning, where the atomic surface concentration can increase to >40% when deuterium retention chemistry is observed. Quantum-classical molecular dynamic simulations elucidated this oxygendeuterium effect and showed that oxygen retains significantly more deuterium than lithium in a simulated matrix with 20% lithium, 20% oxygen, and 60% carbon.Simulations further show that deuterium retention is even higher when lithium is removed from the matrix. Experiments artificially increased the oxygen content in graphite to ~16% and then bombarded with deuterium. XPS showed depletion of the oxygen and no enhanced deuterium retention, thus demonstrating that lithium is essential in retaining the oxygen that thereby retains deuterium.

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Section: Introductionmentioning

confidence: 99%

Differentiating the role of lithium and oxygen in retaining deuterium on lithiated graphite plasma-facing components

et al. 2014

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“…As was noted above, the effect of tungsten on the plasma effective charge is planned to be decreased by implementing modes with a dynamic coating of the surfaces with a thin lithium film. To this end, various lithium technologies are considered, namely, injection of lithium dust into the edge plasma [11], pellet injection [24,25], laser sput tering of lithium [26], and lithium evaporation [27].…”

Section: Key Divertor Elementsmentioning

confidence: 99%

Concept of the divertor of a fusion neutron source based on a spherical tokamak

et al. 2012

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A concept of the divertor and the technology for organizing the edge plasma in a fusion neutron source based on a spherical tokamak (FNS ST) are described. The experimental data on the characteristics of the peripheral plasma in modern tokamaks are extrapolated to the FNS ST conditions with the help of semi analytical models. The effects depending on the magnetic configuration and on the geometry and mate rials of the divertor and the first wall elements are considered. Possible designs of the FNS ST divertor and the first wall are described. Using an original model, it is shown that the maximum density of the heat flux at the divertor plates in a double null magnetic configuration does not exceed 5-6 MW/m 2 , which complies with modern engineering capabilities. Methods for further improvement of the FNS ST divertor concept are analyzed.

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“…It was observed that achievement of these supershots was strongly correlated to wall conditioning, particularly with boron and lithium [1,2]. The decommissioning of TFTR shortly after these observations were made prevented a further probing of the phenomenon at this scale; nonetheless, the effort to understand how the machine wall state could influence tokamak operation continued on a smaller scale, with CDX-U being the first small device fully devoted to study the effect of lithium on tokamak performance [3].…”

Section: Introductionmentioning

confidence: 99%

Design of an experimental test stand for the study of liquid lithium film stability

Nieto-Pérez

Ramos

2011

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

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The benefits of having the walls of fusion devices partially or even totally covered with lithium are widely recognized, as evidenced by the growing number of experimental devices with programs devoted to lithium wall conditioning.There are, however, many outstanding questions regarding technology aspects of lithium handling when placed in a tokamak experiment. The present work describes the preliminary design activities of a test facility devoted to the study of liquid lithium, in particular film stability when thermal gradients are present on downward-facing surfaces. The capability of studying the effect of thermodynamic compatibility between the liquid and the substarte will also be possible in this facility. Two mechanisms for film formation are being considered: condensed films formed from evaporative material, and creeping films formed by flow of metal from a liquid reservoir. Results from finite element modeling for stagnant and flowing films coupled with thermal effects are presented; these simulations will be bench marked against experimental observations once the facility is constructed.The facility will also have the capability of studying MHD effects, since it will be attached to the TPM-IU tokamak, a small machine currently under construction. The expected TPM-IU toroidal field is expected to be on the order of 0.3 T. The coupling of the liquid lithium test stand to the small tokamak will allow the study of liquid lithium flows subjected to full toroidal fields, with no end effects as in previous experiments.

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Enhanced D-T supershot performance at high current using extensive lithium conditioning in TFTR

Cited by 3 publications

References 11 publications

Differentiating the role of lithium and oxygen in retaining deuterium on lithiated graphite plasma-facing components

Differentiating the role of lithium and oxygen in retaining deuterium on lithiated graphite plasma-facing components

Concept of the divertor of a fusion neutron source based on a spherical tokamak

Design of an experimental test stand for the study of liquid lithium film stability

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