Cool, High-Density Regime for Poloidal Divertors

Petravić, M.; Post, D.; Heifetz, D.; Schmidt, J.

doi:10.1103/physrevlett.48.326

Cited by 118 publications

(44 citation statements)

References 4 publications

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“…Such high pressures of a few tenths of a Torr occur rarely in tokamaks. However they have been routinely reached in the DITE bundle divertor [Fielding et al], and may be present in future, high-recycling, divertors [Petravic et al (1982), Hsu]. …”

Section: The Complete Modelmentioning

confidence: 99%

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Neutral Particle Transport

Heifetz

1986

Physics of Plasma-Wall Interactions in Controlled Fusion

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Section: The Complete Modelmentioning

confidence: 99%

“…5. It has been combined with a number of plasma codes, including a onedimensional one-fluid model [Post and Lackner], the SOLID one-dimensional, two-fluid code [Schneider and Lackner], the PLANET two-dimensional, twofluid code [Petravic et al (1982)], and the BALDUR one-dimensional radial transport code [Singer et al (1985B)]. …”

Section: '"mentioning

confidence: 99%

Neutral Particle Transport

Heifetz

1986

Physics of Plasma-Wall Interactions in Controlled Fusion

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“…Disruptions could liberate much carbon which would codeposit on nearby surfaces. The form of the carbon may be dust 33 particles. There should be efforts to diagnose the form of the ablated carbon in existing tokamaks.…”

Section: Vii2 Erosion/redepositionmentioning

confidence: 99%

“…The "gaseous-target" divertor [33] exemplifies theintegrated natureofthedivertor plasma mechanisms and PMI and HHF technologies.Successfultestin a linear configuration [34] is so far limitedto relatively small plasma sizes(coldneutral ionization mean-free-path knc< dp_ < thatforFrank-Condon neutral XFc).Integration ofthegaseous-target divertor intoITER willencounterthe issues of:I)theintegrity of plasma-neutral interface when Xr. c ¢ dpasma,2) thecompatibility of the impliedhigh n× with thedisruptionlimit nxc [27], and 3) thecompatibility of the impliedhigh nx with the H-mode operation [26].…”

mentioning

confidence: 99%

Facilities for technology testing of ITER divertor concepts, models, and prototypes in a plasma environment

Cohen¹

1991

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The exhaust of power and fusion-reaction products from ITER plasma are critical physics and technology issues from performance, safety, and reliability perspectives. PrefaceThere aremany classes ofproblems which must be addressedtomake controlled thermonuclearfusion a viableoption for energy production. Among the most .pressing, from performance,safety,, reliability,, and timeliness perspectives, are issuesassociated with the exhaustfrom the plasma of power and fusion-reaction products. Components designedtoaccomplishthesetasksforITER can only do so .marginally. Their application to a demonstration power plant is not considered probable. Serious doubts and uncertainties exist on both physics and engineering levels.A major reason for this poor situation is the very limited attention given to these power and panicle control issues in comparison with the efforts expended on core plasma confinement.Now that an extensive database for the core plasma has been established through two decades of focussed research supplemented by special task forces, e.g., the transport initiative, tokamak scientists throughout the world fusion program are expanding their interests into the edge plasma region. Extensive studies of divertors have started, highlighted by on-going ADP experiments on DIII-D and ALT-II studies on TEXTOR, and soon-to-start divertor experiments on ASDEXUpgrade, JET, JT-60U, and Alcator-Cmod.These may well answer those difficult edge physics questions raised by the ITER team and its predecessors on INTOR, Starfire, UWMAK, and other rector designs.There remain, however, technical challenges that cannot be answered in the present generation of tokamaks because of inadequate pulse lengths, fluences, .fluxes, or other parameters. Awareness of these deficiencies has led several groups of scientists to propose technology facilities to address these issues. The purpose of this Technical Requirements Documents is to present to the fusion community a coherent and complete description of the capabilities a technology test facility should have to address these divertor issues. Only through an aggressive technology test program, can adequate safety and reliability be attained.Part of this document is tutorial in that it explains why certain parameter values must be achieved. The choice of these parameters and their values are set by the detailed design requirements for the ITER device. This document grew out of results and discussions presented in a series of DOE-sponsored ITER workshops held at Princeton University's Plasma Physics Laboratory during 1989 -1991. I wish to thank Dr. Marvin Cohen of the US Department of Energy for his encouragement and direction in the preparation of this report. Samuel A. CohenPlasma Physics Laboratory Princeton University June 1991 Evaluation of the ITER divertor designThe US National ITER-CDA Review Panel reached the following conclusions: 1. The present divertor design is "marginally capable of achieving the ITER objectives." 2. Added "margin of assurance for achieving the tes...

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“…The most sophisti cated model is a two-dimensional (2-D) (dong and perpendicular to the field) code that haj been used to investigate divertor transport for conditions typical of present-day experiments [Poloidal Divertor Experi ment (PDX) and ASDEX] [8,9]. A common ingredient of these studies is a treatment of the neutral transport, which plays an important role in the buildup of density and temperature gradients along the field.…”

Section: Introductionmentioning

confidence: 99%

Two-point model for divertor transport

Galambos¹,

Peng²

1984

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Cool, High-Density Regime for Poloidal Divertors

Cited by 118 publications

References 4 publications

Neutral Particle Transport

Neutral Particle Transport

Facilities for technology testing of ITER divertor concepts, models, and prototypes in a plasma environment

Two-point model for divertor transport

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