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<entry id="1">
<attribute id="abstract">
<text>Improved electron energy confinement in tokamak plasmas, related to
internal transport barriers, has been linked to nonmonotonic current
density profiles. This is difficult to prove experimentally since
usually the current profiles evolve continuously and current injection
generally requires significant input power. New experiments are
presented, in which the inductive current is used to generate positive
and negative current density perturbations in the plasma center, with
negligible input power. These results demonstrate unambiguously for the
first time that the electron confinement can be modified significantly
solely by perturbing the current density profile.</text>
</attribute>
<attribute id="author">
<person first="O" last="Sauter"/>
<person first="S" last="Coda"/>
<person first="TP" last="Goodman"/>
<person first="MA" last="Henderson"/>
<person first="R" last="Behn"/>
<person first="A" last="Bottino"/>
<person first="E" last="Fable"/>
<person first="A" last="Martynov"/>
<person first="P" last="Nikkola"/>
<person first="C" last="Zucca"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>BOOTSTRAP CURRENT</text>
<text>TCV TOKAMAK</text>
</attribute>
<attribute id="source">
<text>
<content>PHYSICAL REVIEW LETTERS</content>
<attribute id="volume">
<text>94</text>
</attribute>
<attribute id="abbrev">
<text>PHYS REV LETT</text>
<text>Phys. Rev. Lett.</text>
</attribute>
<attribute id="issn">
<id value="0031-9007"/>
</attribute>
<attribute id="number">
<text>10</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Inductive current density perturbations to probe electron internal
transport barriers in tokamaks</text>
</attribute>
<attribute id="ut">
<id value="000227838900030"/>
</attribute>
</entry>
<entry id="2">
<attribute id="abstract">
<text>Results from an extensive database analysis of JET density profiles in
stationary conditions show that the density peaking factor n(e0)/&lt;
n(e)&gt; in JET H modes increases from near 1.2 at high collisionality to
around 1.5 as the plasma collisionality decreases towards the values
expected for ITER. This result confirms an earlier observation on AUG.
The density peaking behaviour of L modes is remarkably different from
that of H modes, scaling with overall plasma shear as (n(e0)/&lt; n(e)&gt;
similar to 1.5l(i)), independently of collisionality. H-mode density
profiles show no shear dependence, except at the lowest
collisionalities. No evidence for L-Te, L-Ti, rho* or beta dependences
has been obtained. Carbon impurity density profiles from charge
exchange spectroscopy are always less peaked than electron density
profiles and usually flat in H modes. The peaking of the electron
density profiles, together with the flatness of the impurity density
profiles, are favourable for fusion performance if they can be
extrapolated to ignited conditions.</text>
</attribute>
<attribute id="author">
<person first="H" last="Weisen"/>
<person first="A" last="Zabolotsky"/>
<person first="C" last="Angioni"/>
<person first="I" last="Furno"/>
<person first="X" last="Garbet"/>
<person first="C" last="Giroud"/>
<person first="H" last="Leggate"/>
<person first="P" last="Mantica"/>
<person first="A" last="Mazon"/>
<person first="J" last="Weiland"/>
<person first="L" last="Zabeo"/>
<person first="KD" last="Zastrow"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>L-MODE PLASMAS</text>
<text>PARTICLE PINCH</text>
<text>ASDEX UPGRADE</text>
<text>INVERSION</text>
<text>TOKAMAK</text>
<text>PROFILE</text>
<text>SHAPE</text>
<text>TCV</text>
</attribute>
<attribute id="source">
<text>
<content>NUCLEAR FUSION</content>
<attribute id="issn">
<id value="0029-5515"/>
</attribute>
<attribute id="number">
<text>2</text>
</attribute>
<attribute id="volume">
<text>45</text>
</attribute>
<attribute id="abbrev">
<text>NUCL FUSION</text>
<text>Nucl. Fusion</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>L1-L4</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Collisionality and shear dependences of density peaking in JET and
extrapolation to ITER</text>
</attribute>
<attribute id="ut">
<id value="000227818500001"/>
</attribute>
</entry>
<entry id="3">
<attribute id="abstract">
<text>JET plasmas with reverse magnetic field feature a different SOL flow
than those with normal field. The observed carbon fuelling efficiency
from injecting methane gas was similar in reverse and normal field.
EDGE2D modeling used an externally applied force to create the SOL
flows, without specifying the origin of the force. The resulting flow
agreed reasonably with the experimental values between the separatrix
and 4 cm mid-plane depth in the SOL. The effect of the flow on the
calculated carbon screening was 5-15% higher carbon fuelling efficiency
for the low flow velocity with reverse field. (c) 2004 Elsevier B.V.
All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="JD" last="Strachan"/>
<person first="B" last="Alper"/>
<person first="G" last="Corrigan"/>
<person first="SK" last="Erents"/>
<person first="C" last="Giroud"/>
<person first="A" last="Korotkov"/>
<person first="H" last="Leggate"/>
<person first="GF" last="Matthews"/>
<person first="RA" last="Pitts"/>
<person first="J" last="Spence"/>
<person first="M" last="Stamp"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>SCRAPE-OFF LAYER</text>
<text>DIII-D</text>
<text>IMPURITIES</text>
<text>TRANSPORT</text>
<text>DIVERTOR</text>
<text>PLASMAS</text>
<text>JT-60U</text>
<text>EDGE</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>25-29</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Methane screening in JET reverse field experiments</text>
</attribute>
<attribute id="ut">
<id value="000227789500005"/>
</attribute>
</entry>
<entry id="4">
<attribute id="abstract">
<text>Divertor surface temperatures are significantly affected by the
presence of deposited surface layers. This phenomenon can be used to
monitor deposited layer evolution on a shot-by-shot basis. It was found
that during an experimental campaign where the B x del B direction was
reversed that the outer target, normally an erosion zone, became a
deposition zone. (c) 2004 Published by Elsevier B.V.</text>
</attribute>
<attribute id="author">
<person first="P" last="Andrew"/>
<person first="JP" last="Coad"/>
<person first="Y" last="Corre"/>
<person first="T" last="Eich"/>
<person first="A" last="Herrmann"/>
<person first="GF" last="Matthews"/>
<person first="JI" last="Paley"/>
<person first="L" last="Pickworth"/>
<person first="RA" last="Pitts"/>
<person first="MF" last="Stamp"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>99-103</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Outer divertor target deposited layers during reversed magnetic field
operation in JET</text>
</attribute>
<attribute id="ut">
<id value="000227789500020"/>
</attribute>
</entry>
<entry id="5">
<attribute id="abstract">
<text>Asymmetries are a ubiquitous feature of the scrape-off layer (SOL) and
divertor plasmas in any tokamak and are thought to be driven primarily
by a variety of drift flows, the directions of which reverse with
reversal of the main toroidal field. The understanding of precisely how
these field dependent drifts combine to yield any given experimental
observation is still very much incomplete. A recent campaign of
reversed field operation at JET designed to match a variety of
discharges to their more frequently executed forward field counterparts
has been executed in an attempt to contribute to this understanding.
This paper summarises the most important findings from these
experiments and includes some new EDGE2D simulation results describing
the SOL flow. (c) 2004 Elsevier B.V. All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="RA" last="Pitts"/>
<person first="P" last="Andrew"/>
<person first="X" last="Bonnin"/>
<person first="AV" last="Chankin"/>
<person first="Y" last="Corre"/>
<person first="G" last="Corrigan"/>
<person first="D" last="Coster"/>
<person first="I" last="Duran"/>
<person first="T" last="Eich"/>
<person first="SK" last="Erents"/>
<person first="W" last="Fundamenski"/>
<person first="A" last="Huber"/>
<person first="S" last="Jachmich"/>
<person first="G" last="Kirnev"/>
<person first="M" last="Lehnen"/>
<person first="PJ" last="Lomas"/>
<person first="A" last="Loarte"/>
<person first="GF" last="Matthews"/>
<person first="J" last="Rapp"/>
<person first="C" last="Silva"/>
<person first="MF" last="Stamp"/>
<person first="JD" last="Strachan"/>
<person first="E" last="Tsitrone"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>SCRAPE-OFF LAYER</text>
<text>BOUNDARY PLASMA</text>
<text>MODELS</text>
<text>TOKAMAK</text>
<text>SOL</text>
<text>ASYMMETRIES</text>
<text>PARTICLE</text>
<text>DRIFTS</text>
<text>JT-60U</text>
<text>FLOW</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>146-153</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Edge and divertor physics with reversed toroidal field in JET</text>
</attribute>
<attribute id="ut">
<id value="000227789500029"/>
</attribute>
</entry>
<entry id="6">
<attribute id="abstract">
<text>The effect of field reversal on the JET MkIIGB-SRP divertor performance
has been investigated in L-mode density limit discharges. These
experiments show that the direction of the magnetic field has a
substantial effect on divertor physics, modifying the character of
detachment and density limits. Reversal of the ion del B-drift
direction away from the X-point results in a reduction of the density
limit of about 15%. In contrast to forward field direction, the
divertor parameters such as density and temperature as well as divertor
radiation distribution and power at the divertor target become more
symmetrical in the discharges with reversed field. The influence of
different field configurations on the divertor performance has been
analysed with respect to the dependence on density and heating power.
The experimental observations of out-in asymmetry in target power as
well as in the CIII-emission distribution is consistent with EDGE2D
simulations, which include the effect of drifts. (c) 2004 Elsevier B.V.
All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="A" last="Huber"/>
<person first="J" last="Rapp"/>
<person first="P" last="Andrew"/>
<person first="P" last="Coad"/>
<person first="G" last="Corrigan"/>
<person first="K" last="Erents"/>
<person first="W" last="Fundamenski"/>
<person first="LC" last="Ingesson"/>
<person first="S" last="Jachmich"/>
<person first="A" last="Korotkov"/>
<person first="GF" last="Matthews"/>
<person first="P" last="Mertens"/>
<person first="V" last="Philipps"/>
<person first="R" last="Pitts"/>
<person first="B" last="Schweer"/>
<person first="G" last="Sergienko"/>
<person first="M" last="Stamp"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>DIII-D</text>
<text>PLASMA</text>
<text>BEHAVIOR</text>
<text>PARTICLE</text>
<text>EDGE</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>241-245</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>The effect of field reversal on the JET MkIIGB-SRP divertor performance
in L-mode density limit discharges</text>
</attribute>
<attribute id="ut">
<id value="000227789500047"/>
</attribute>
</entry>
<entry id="7">
<attribute id="abstract">
<text>EDGE2D simulations show that high SOL flows can be generated when an
additional radial convective transport is applied in the SOL and
pedestal region along with a 'ballooning-like' poloidal variation in
transport. This model produces an inward particle flux at the inboard
side of the plasma along with an enhanced outward flux at the outer
midplane. Parallel Mach numbers can be produced at the top of the
machine which are comparable in magnitude to those observed by the JET
Mach probes. For the normal toroidal magnetic field direction, the
parallel flow Mach number is about M = 0.32 in this case. Applying
these two additional mechanisms also allows experimental outer to inner
target power and out-in divertor line emission intensity asymmetries to
be qualitatively reproduced. (c) 2004 Elsevier B.V. All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="GS" last="Kirnev"/>
<person first="G" last="Corrigan"/>
<person first="D" last="Coster"/>
<person first="SK" last="Erents"/>
<person first="W" last="Fundamenski"/>
<person first="GF" last="Matthews"/>
<person first="RA" last="Pitts"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>SCRAPE-OFF-LAYER</text>
<text>PLASMA-FLOW</text>
<text>POLOIDAL ASYMMETRIES</text>
<text>TARGET
ASYMMETRIES</text>
<text>TOKAMAK</text>
<text>TRANSPORT</text>
<text>JT-60U</text>
<text>TURBULENCE</text>
<text>PARTICLE</text>
<text>FLUXES</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>271-275</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>EDGE2D code simulations of SOL flows and in-out divertor asymmetries in
JET</text>
</attribute>
<attribute id="ut">
<id value="000227789500053"/>
</attribute>
</entry>
<entry id="8">
<attribute id="abstract">
<text>The toroidal field and plasma current were reversed in recent JET
experiments to yield a large number of good forward-reversed matched
pairs. The direction, magnitude and scaling of the poloidal energy
transport in the SOL can be explained by (neo-)classical drift-related
heat fluxes (E x B and/or B x del T) whose relative contribution scales
as rho(0s)/lambda(T sigma). Radial energy transport is largely
independent of the B x del B direction, consistent with classical ion
conduction. (c) 2004 Elsevier B.V. All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="W" last="Fundamenski"/>
<person first="P" last="Andrew"/>
<person first="K" last="Erents"/>
<person first="A" last="Huber"/>
<person first="G" last="Kirnev"/>
<person first="G" last="Matthews"/>
<person first="R" last="Pitts"/>
<person first="V" last="Riccardo"/>
<person first="S" last="Sipila"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>ELMY H-MODES</text>
<text>DIVERTOR</text>
<text>PLASMA</text>
<text>FIELD</text>
<text>ASYMMETRIES</text>
<text>PROFILES</text>
<text>REVERSAL</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>305-309</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Effect of B x del B direction on SOL energy transport in JET</text>
</attribute>
<attribute id="ut">
<id value="000227789500060"/>
</attribute>
</entry>
<entry id="9">
<attribute id="abstract">
<text>A comparative analysis of the spatial and temporal characteristics of
transient energy loads (ELMs and disruptions) on plasma facing
components (PFCs) in present tokamak devices and their extrapolation to
next step devices is presented. Type I ELMs lead to the expulsion of
energy by the plasma in helical structures with ballooning-like
features and toroidal numbers in the range n = 10-15. The plasma energy
is transported towards the divertor and the main chamber PFCs leading
to significant transient energy loads at these two locations on small
wetted area. The largest transient energy fluxes onto PFCs in tokamaks
are measured during the thermal quench of disruptions. These fluxes do
not exceed greatly those of large Type I ELMs, due to the much larger
wetted area for energy flux during the thermal quench compared to Type
I ELMs. The implications of these findings for the next step devices
are discussed. (c) 2004 Elsevier B.V. All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="T" last="Eich"/>
<person first="A" last="Herrmann"/>
<person first="G" last="Pautasso"/>
<person first="P" last="Andrew"/>
<person first="N" last="Asakura"/>
<person first="JA" last="Boedo"/>
<person first="Y" last="Corre"/>
<person first="ME" last="Fenstermacher"/>
<person first="JC" last="Fuchs"/>
<person first="W" last="Fundamenski"/>
<person first="G" last="Federici"/>
<person first="E" last="Gauthier"/>
<person first="B" last="Goncalves"/>
<person first="O" last="Gruber"/>
<person first="A" last="Kirk"/>
<person first="AW" last="Leonard"/>
<person first="A" last="Loarte"/>
<person first="GF" last="Matthews"/>
<person first="J" last="Neuhauser"/>
<person first="RA" last="Pitts"/>
<person first="V" last="Riccardo"/>
<person first="C" last="Silva"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>EDGE LOCALIZED MODES</text>
<text>SCRAPE-OFF LAYER</text>
<text>PARTICLE LOSSES</text>
<text>DIII-D</text>
<text>ASDEX-UPGRADE</text>
<text>HEAT-FLUX</text>
<text>H-MODES</text>
<text>ENERGY</text>
<text>JET</text>
<text>ITER</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>669-676</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Power deposition onto plasma facing components in poloidal divertor
tokamaks during type-I ELMS and disruptions</text>
</attribute>
<attribute id="ut">
<id value="000227789500133"/>
</attribute>
</entry>
<entry id="10">
<attribute id="abstract">
<text>The paper reviews recent theoretical and experimental results focussing
on the identification of the key factors controlling ELM energy and
particle losses both in natural ELMs and in the presence of external
controlling mechanisms. Present experiment and theory pointed out the
benefit of the high plasma shaping, high q(95) and high pedestal
density in reducing the ELM affected area and conductive energy losses
in Type I ELMs. Small benign ELMs regimes in present machines (EDA,
HRS, Type II, Grassy, QH, Type III in impurity seeded discharges at
high delta) and their relevance for ITER are reviewed. Recent studies
of active control of ELMs using stochastic boundaries, small pellets
and edge current generation are presented. (c) 2004 Elsevier B.V. All
rights reserved.</text>
</attribute>
<attribute id="author">
<person first="M" last="Becoulet"/>
<person first="G" last="Huysmans"/>
<person first="P" last="Thomas"/>
<person first="E" last="Joffrin"/>
<person first="F" last="Rimini"/>
<person first="P" last="Monier-Garbet"/>
<person first="A" last="Grosman"/>
<person first="P" last="Ghendrih"/>
<person first="V" last="Parail"/>
<person first="P" last="Lomas"/>
<person first="G" last="Matthews"/>
<person first="H" last="Wilson"/>
<person first="M" last="Gryaznevich"/>
<person first="G" last="Counsell"/>
<person first="A" last="Loarte"/>
<person first="G" last="Saibene"/>
<person first="R" last="Sartori"/>
<person first="A" last="Leonard"/>
<person first="P" last="Snyder"/>
<person first="T" last="Evans"/>
<person first="P" last="Gohil"/>
<person first="R" last="Moyer"/>
<person first="Y" last="Kamada"/>
<person first="N" last="Oyama"/>
<person first="T" last="Hatae"/>
<person first="K" last="Kamiya"/>
<person first="A" last="Degeling"/>
<person first="Y" last="Martin"/>
<person first="J" last="Lister"/>
<person first="J" last="Rapp"/>
<person first="C" last="Perez"/>
<person first="P" last="Lang"/>
<person first="A" last="Chankin"/>
<person first="T" last="Eich"/>
<person first="A" last="Sips"/>
<person first="J" last="Stober"/>
<person first="L" last="Horton"/>
<person first="A" last="Kallenbach"/>
<person first="W" last="Suttrop"/>
<person first="S" last="Saarelma"/>
<person first="S" last="Cowley"/>
<person first="J" last="Lonnroth"/>
<person first="M" last="Shimada"/>
<person first="A" last="Polevoi"/>
<person first="G" last="Federici"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="keyword">
<text>ELMY H-MODES</text>
<text>MHD STABILITY ANALYSIS</text>
<text>ASDEX UPGRADE</text>
<text>I ELMS</text>
<text>DIII-D</text>
<text>TRANSPORT BARRIERS</text>
<text>PELLET INJECTION</text>
<text>BOUNDARY PLASMA</text>
<text>PARTICLE LOSSES</text>
<text>HIGH-DENSITY</text>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>677-683</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>Edge localized modes control: experiment and theory</text>
</attribute>
<attribute id="ut">
<id value="000227789500134"/>
</attribute>
</entry>
<entry id="11">
<attribute id="abstract">
<text>If an ELM is a peeling of flux surfaces from the plasma, due to a
broken separatrix, current density is lost as well as particles and
energy. The fast loss of a current-carrying plasma layer modifies the
plasma equilibrium, leading to sudden shifts in the strike points at
each ELM, towards the plasma centre. An experimental study of this
conjectured model of the ELM has been made at JET, showing that in all
cases of Type I ELMs studied, strike point shifts were observed. In two
cases studied in detail, the estimated equilibrium changes provoked by
flux surface peeling agree qualitatively with the observed strike point
shifts. (c) 2004 Elsevier B.V. All rights reserved.</text>
</attribute>
<attribute id="author">
<person first="ER" last="Solano"/>
<person first="S" last="Jachmich"/>
<person first="F" last="Villone"/>
<person first="N" last="Hawkes"/>
<person first="Y" last="Corre"/>
<person first="RA" last="Pitts"/>
<person first="A" last="Loarte"/>
<person first="B" last="Alper"/>
<person first="K" last="Guenther"/>
<person first="A" last="Koroktov"/>
<person first="M" last="Stamp"/>
<person first="P" last="Andrew"/>
<person first="SA" last="Arshad"/>
<person first="J" last="Conboy"/>
<person first="T" last="Bolzonella"/>
<person first="E" last="Rachlew"/>
<person first="M" last="Kempenaars"/>
<person first="A" last="Cenedese"/>
<person first="D" last="Testa"/>
</attribute>
<attribute id="doctype">
<txo group="doctype" id="3"/>
</attribute>
<attribute id="source">
<text>
<content>JOURNAL OF NUCLEAR MATERIALS</content>
<attribute id="issn">
<id value="0022-3115"/>
</attribute>
<attribute id="number">
<text>1-3</text>
</attribute>
<attribute id="volume">
<text>337-39</text>
</attribute>
<attribute id="abbrev">
<text>J NUCL MATER</text>
<text>J. Nucl. Mater.</text>
</attribute>
<attribute id="year">
<text>2005</text>
</attribute>
<attribute id="pages">
<text>747-750</text>
</attribute>
</text>
</attribute>
<attribute id="title">
<text>ELMS and strike point jumps</text>
</attribute>
<attribute id="ut">
<id value="000227789500147"/>
</attribute>
</entry>
</pyblio-db>

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