Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas
Identifieur interne : 004701 ( PascalFrancis/Corpus ); précédent : 004700; suivant : 004702Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas
Auteurs : T. E. Evans ; R. A. Moyer ; J. G. Watkins ; T. H. Osborne ; P. R. Thomas ; M. Becoulet ; J. A. Boedo ; E. J. Doyle ; M. E. Fenstermacher ; K. H. Finken ; R. J. Groebner ; M. Groth ; J. H. Harris ; G. L. Jackson ; R. J. La Haye ; C. J. Lasnier ; S. Masuzaki ; N. Ohyabu ; D. G. Pretty ; H. Reimerdes ; T. L. Rhodes ; D. L. Rudakov ; M. J. Schaffer ; M. R. Wade ; G. Wang ; W. P. West ; L. ZengSource :
- Nuclear fusion [ 0029-5515 ] ; 2005.
Descripteurs français
- Pascal (Inist)
- Plasma confiné, Confinement magnétique, Mode localisé bord, Phénomène transport plasma, Champ magnétique, Réacteur fusion nucléaire, Instabilité plasma, Réacteur tokamak, Ecoulement plasma, Temps confinement, Confinement énergie, Champ intense, Ligne magnétique, Ilot magnétique, Confinement plasma mode H, Etude expérimentale, 5255F, 5255R.
English descriptors
- KwdEn :
- Confined plasma, Confinement time, Edge localized modes, Energy confinement, Experimental study, H-mode plasma confinement, High field, Magnetic confinement, Magnetic fields, Magnetic islands, Magnetic line, Plasma flow, Plasma instability, Plasma transport processes, Thermonuclear reactors, Tokamak type reactors.
Abstract
Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τE) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψN ≤ 1.0) when q95 = 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, βN, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4-6 τE ) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1-2 τE. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER.
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Pour connaître la documentation sur le format Inist Standard.
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Format Inist (serveur)
NO : | PASCAL 05-0468530 INIST |
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ET : | Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas |
AU : | EVANS (T. E.); MOYER (R. A.); WATKINS (J. G.); OSBORNE (T. H.); THOMAS (P. R.); BECOULET (M.); BOEDO (J. A.); DOYLE (E. J.); FENSTERMACHER (M. E.); FINKEN (K. H.); GROEBNER (R. J.); GROTH (M.); HARRIS (J. H.); JACKSON (G. L.); LA HAYE (R. J.); LASNIER (C. J.); MASUZAKI (S.); OHYABU (N.); PRETTY (D. G.); REIMERDES (H.); RHODES (T. L.); RUDAKOV (D. L.); SCHAFFER (M. J.); WADE (M. R.); WANG (G.); WEST (W. P.); ZENG (L.) |
AF : | General Atomics, PO Box 85608/San Diego, CA 92186-5608/Etats-Unis (1 aut., 4 aut., 11 aut., 14 aut., 15 aut., 23 aut., 26 aut.); University of California San Diego/La Jolla, California/Etats-Unis (2 aut., 7 aut., 22 aut.); Sandia National Laboratory/Albuquerque, New Mexico/Etats-Unis (3 aut.); CEA-Cadarache Euratom Association/Cadarache/France (5 aut., 6 aut.); University of California/Los Angeles, California/Etats-Unis (8 aut., 21 aut., 25 aut., 27 aut.); Lawrence Livermore National Laboratory/Livermore, California/Etats-Unis (9 aut., 12 aut., 16 aut.); FZ-Jülich Euratom Association/Jülich/Allemagne (10 aut.); Australian National University/Canberra/Australie (13 aut., 19 aut.); National Institute for Fusion Science/Gifu-ken/Japon (17 aut., 18 aut.); Columbia University/New York, New York/Etats-Unis (20 aut.); Oak Ridge National Laboratory/Oak Ridge, Tennessee/Etats-Unis (24 aut.) |
DT : | Publication en série; Niveau analytique |
SO : | Nuclear fusion; ISSN 0029-5515; Coden NUFUAU; Royaume-Uni; Da. 2005; Vol. 45; No. 7; Pp. 595-607; Bibl. 20 ref. |
LA : | Anglais |
EA : | Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τE) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψN ≤ 1.0) when q95 = 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, βN, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4-6 τE ) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1-2 τE. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER. |
CC : | 001B50B55F; 001B50B55 |
FD : | Plasma confiné; Confinement magnétique; Mode localisé bord; Phénomène transport plasma; Champ magnétique; Réacteur fusion nucléaire; Instabilité plasma; Réacteur tokamak; Ecoulement plasma; Temps confinement; Confinement énergie; Champ intense; Ligne magnétique; Ilot magnétique; Confinement plasma mode H; Etude expérimentale; 5255F; 5255R |
ED : | Confined plasma; Magnetic confinement; Edge localized modes; Plasma transport processes; Magnetic fields; Thermonuclear reactors; Plasma instability; Tokamak type reactors; Plasma flow; Confinement time; Energy confinement; High field; Magnetic line; Magnetic islands; H-mode plasma confinement; Experimental study |
SD : | Plasma confinado; Confinamiento energía; Línea magnética |
LO : | INIST-1614.354000132319240080 |
ID : | 05-0468530 |
Links to Exploration step
Pascal:05-0468530Le document en format XML
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<sourceDesc><biblStruct><analytic><title xml:lang="en" level="a">Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas</title>
<author><name sortKey="Evans, T E" sort="Evans, T E" uniqKey="Evans T" first="T. E." last="Evans">T. E. Evans</name>
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<author><name sortKey="Thomas, P R" sort="Thomas, P R" uniqKey="Thomas P" first="P. R." last="Thomas">P. R. Thomas</name>
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<author><name sortKey="Boedo, J A" sort="Boedo, J A" uniqKey="Boedo J" first="J. A." last="Boedo">J. A. Boedo</name>
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<affiliation><inist:fA14 i1="05"><s1>University of California</s1>
<s2>Los Angeles, California</s2>
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<series><title level="j" type="main">Nuclear fusion</title>
<title level="j" type="abbreviated">Nucl. fus.</title>
<idno type="ISSN">0029-5515</idno>
<imprint><date when="2005">2005</date>
</imprint>
</series>
</biblStruct>
</sourceDesc>
<seriesStmt><title level="j" type="main">Nuclear fusion</title>
<title level="j" type="abbreviated">Nucl. fus.</title>
<idno type="ISSN">0029-5515</idno>
</seriesStmt>
</fileDesc>
<profileDesc><textClass><keywords scheme="KwdEn" xml:lang="en"><term>Confined plasma</term>
<term>Confinement time</term>
<term>Edge localized modes</term>
<term>Energy confinement</term>
<term>Experimental study</term>
<term>H-mode plasma confinement</term>
<term>High field</term>
<term>Magnetic confinement</term>
<term>Magnetic fields</term>
<term>Magnetic islands</term>
<term>Magnetic line</term>
<term>Plasma flow</term>
<term>Plasma instability</term>
<term>Plasma transport processes</term>
<term>Thermonuclear reactors</term>
<term>Tokamak type reactors</term>
</keywords>
<keywords scheme="Pascal" xml:lang="fr"><term>Plasma confiné</term>
<term>Confinement magnétique</term>
<term>Mode localisé bord</term>
<term>Phénomène transport plasma</term>
<term>Champ magnétique</term>
<term>Réacteur fusion nucléaire</term>
<term>Instabilité plasma</term>
<term>Réacteur tokamak</term>
<term>Ecoulement plasma</term>
<term>Temps confinement</term>
<term>Confinement énergie</term>
<term>Champ intense</term>
<term>Ligne magnétique</term>
<term>Ilot magnétique</term>
<term>Confinement plasma mode H</term>
<term>Etude expérimentale</term>
<term>5255F</term>
<term>5255R</term>
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<front><div type="abstract" xml:lang="en">Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τ<sub>E</sub>
) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψ<sub>N</sub>
≤ 1.0) when q<sub>95</sub>
= 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, β<sub>N</sub>
, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4-6 τ<sub>E</sub>
) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1-2 τ<sub>E</sub>
. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER.</div>
</front>
</TEI>
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<fA08 i1="01" i2="1" l="ENG"><s1>Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas</s1>
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<fA11 i1="24" i2="1"><s1>WADE (M. R.)</s1>
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<fC01 i1="01" l="ENG"><s0>Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τ<sub>E</sub>
) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψ<sub>N</sub>
≤ 1.0) when q<sub>95</sub>
= 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, β<sub>N</sub>
, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4-6 τ<sub>E</sub>
) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1-2 τ<sub>E</sub>
. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER.</s0>
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<s5>54</s5>
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<fC03 i1="06" i2="3" l="FRE"><s0>Réacteur fusion nucléaire</s0>
<s5>55</s5>
</fC03>
<fC03 i1="06" i2="3" l="ENG"><s0>Thermonuclear reactors</s0>
<s5>55</s5>
</fC03>
<fC03 i1="07" i2="3" l="FRE"><s0>Instabilité plasma</s0>
<s5>56</s5>
</fC03>
<fC03 i1="07" i2="3" l="ENG"><s0>Plasma instability</s0>
<s5>56</s5>
</fC03>
<fC03 i1="08" i2="3" l="FRE"><s0>Réacteur tokamak</s0>
<s5>57</s5>
</fC03>
<fC03 i1="08" i2="3" l="ENG"><s0>Tokamak type reactors</s0>
<s5>57</s5>
</fC03>
<fC03 i1="09" i2="3" l="FRE"><s0>Ecoulement plasma</s0>
<s5>58</s5>
</fC03>
<fC03 i1="09" i2="3" l="ENG"><s0>Plasma flow</s0>
<s5>58</s5>
</fC03>
<fC03 i1="10" i2="3" l="FRE"><s0>Temps confinement</s0>
<s5>59</s5>
</fC03>
<fC03 i1="10" i2="3" l="ENG"><s0>Confinement time</s0>
<s5>59</s5>
</fC03>
<fC03 i1="11" i2="X" l="FRE"><s0>Confinement énergie</s0>
<s5>60</s5>
</fC03>
<fC03 i1="11" i2="X" l="ENG"><s0>Energy confinement</s0>
<s5>60</s5>
</fC03>
<fC03 i1="11" i2="X" l="SPA"><s0>Confinamiento energía</s0>
<s5>60</s5>
</fC03>
<fC03 i1="12" i2="3" l="FRE"><s0>Champ intense</s0>
<s5>61</s5>
</fC03>
<fC03 i1="12" i2="3" l="ENG"><s0>High field</s0>
<s5>61</s5>
</fC03>
<fC03 i1="13" i2="X" l="FRE"><s0>Ligne magnétique</s0>
<s5>62</s5>
</fC03>
<fC03 i1="13" i2="X" l="ENG"><s0>Magnetic line</s0>
<s5>62</s5>
</fC03>
<fC03 i1="13" i2="X" l="SPA"><s0>Línea magnética</s0>
<s5>62</s5>
</fC03>
<fC03 i1="14" i2="3" l="FRE"><s0>Ilot magnétique</s0>
<s5>63</s5>
</fC03>
<fC03 i1="14" i2="3" l="ENG"><s0>Magnetic islands</s0>
<s5>63</s5>
</fC03>
<fC03 i1="15" i2="3" l="FRE"><s0>Confinement plasma mode H</s0>
<s5>64</s5>
</fC03>
<fC03 i1="15" i2="3" l="ENG"><s0>H-mode plasma confinement</s0>
<s5>64</s5>
</fC03>
<fC03 i1="16" i2="3" l="FRE"><s0>Etude expérimentale</s0>
<s5>65</s5>
</fC03>
<fC03 i1="16" i2="3" l="ENG"><s0>Experimental study</s0>
<s5>65</s5>
</fC03>
<fC03 i1="17" i2="3" l="FRE"><s0>5255F</s0>
<s2>PAC</s2>
<s4>INC</s4>
<s5>91</s5>
</fC03>
<fC03 i1="18" i2="3" l="FRE"><s0>5255R</s0>
<s2>PAC</s2>
<s4>INC</s4>
<s5>92</s5>
</fC03>
<fN21><s1>332</s1>
</fN21>
<fN44 i1="01"><s1>PSI</s1>
</fN44>
<fN82><s1>PSI</s1>
</fN82>
</pA>
</standard>
<server><NO>PASCAL 05-0468530 INIST</NO>
<ET>Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas</ET>
<AU>EVANS (T. E.); MOYER (R. A.); WATKINS (J. G.); OSBORNE (T. H.); THOMAS (P. R.); BECOULET (M.); BOEDO (J. A.); DOYLE (E. J.); FENSTERMACHER (M. E.); FINKEN (K. H.); GROEBNER (R. J.); GROTH (M.); HARRIS (J. H.); JACKSON (G. L.); LA HAYE (R. J.); LASNIER (C. J.); MASUZAKI (S.); OHYABU (N.); PRETTY (D. G.); REIMERDES (H.); RHODES (T. L.); RUDAKOV (D. L.); SCHAFFER (M. J.); WADE (M. R.); WANG (G.); WEST (W. P.); ZENG (L.)</AU>
<AF>General Atomics, PO Box 85608/San Diego, CA 92186-5608/Etats-Unis (1 aut., 4 aut., 11 aut., 14 aut., 15 aut., 23 aut., 26 aut.); University of California San Diego/La Jolla, California/Etats-Unis (2 aut., 7 aut., 22 aut.); Sandia National Laboratory/Albuquerque, New Mexico/Etats-Unis (3 aut.); CEA-Cadarache Euratom Association/Cadarache/France (5 aut., 6 aut.); University of California/Los Angeles, California/Etats-Unis (8 aut., 21 aut., 25 aut., 27 aut.); Lawrence Livermore National Laboratory/Livermore, California/Etats-Unis (9 aut., 12 aut., 16 aut.); FZ-Jülich Euratom Association/Jülich/Allemagne (10 aut.); Australian National University/Canberra/Australie (13 aut., 19 aut.); National Institute for Fusion Science/Gifu-ken/Japon (17 aut., 18 aut.); Columbia University/New York, New York/Etats-Unis (20 aut.); Oak Ridge National Laboratory/Oak Ridge, Tennessee/Etats-Unis (24 aut.)</AF>
<DT>Publication en série; Niveau analytique</DT>
<SO>Nuclear fusion; ISSN 0029-5515; Coden NUFUAU; Royaume-Uni; Da. 2005; Vol. 45; No. 7; Pp. 595-607; Bibl. 20 ref.</SO>
<LA>Anglais</LA>
<EA>Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τ<sub>E</sub>
) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψ<sub>N</sub>
≤ 1.0) when q<sub>95</sub>
= 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, β<sub>N</sub>
, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4-6 τ<sub>E</sub>
) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1-2 τ<sub>E</sub>
. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER.</EA>
<CC>001B50B55F; 001B50B55</CC>
<FD>Plasma confiné; Confinement magnétique; Mode localisé bord; Phénomène transport plasma; Champ magnétique; Réacteur fusion nucléaire; Instabilité plasma; Réacteur tokamak; Ecoulement plasma; Temps confinement; Confinement énergie; Champ intense; Ligne magnétique; Ilot magnétique; Confinement plasma mode H; Etude expérimentale; 5255F; 5255R</FD>
<ED>Confined plasma; Magnetic confinement; Edge localized modes; Plasma transport processes; Magnetic fields; Thermonuclear reactors; Plasma instability; Tokamak type reactors; Plasma flow; Confinement time; Energy confinement; High field; Magnetic line; Magnetic islands; H-mode plasma confinement; Experimental study</ED>
<SD>Plasma confinado; Confinamiento energía; Línea magnética</SD>
<LO>INIST-1614.354000132319240080</LO>
<ID>05-0468530</ID>
</server>
</inist>
</record>
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