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729
gas puffing in ELMy H-mode plasmas
, 2003
"... puffing in ELMy H-mode plasmas. Plasma Physics and Controlled Fusion, volume 45, ..."
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puffing in ELMy H-mode plasmas. Plasma Physics and Controlled Fusion, volume 45,
Role of Neutral in ELMy H-Mode Plasmas: 2D Transport Simulation with COCONUT
, 2000
"... Neutral penetration through SoL is studied for ELMy H-mode plasma with 2D transport code cocoNUT, which has been developed at JET Joint undertaking. Interaction between the neutral and the transport barrier is investigated, and it is shown that when increasing gas puffing ' sudden increase of E ..."
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Neutral penetration through SoL is studied for ELMy H-mode plasma with 2D transport code cocoNUT, which has been developed at JET Joint undertaking. Interaction between the neutral and the transport barrier is investigated, and it is shown that when increasing gas puffing ' sudden increase
Improved Performance in Long-pulse ELMy H-mode Plasmas with Internal Transport Barrier in JT-60U
"... Abstract. After installation of ferritic steel tiles (FSTs), fast ion losses due to toroidal field ripple have been reduced by 1/2~1/3. The increase in absorbed power at same injection power can reduce the required number of NB units to sustain a given βN, resulting in a better flexibility of torque ..."
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of torque input by increasing the available combination of tangential NB units. By making use of these advantages to sustain an internal transport barrier (ITB), the performance of long-pulse ELMy H-mode plasmas was improved in terms of sustained duration time for both high normalized beta (βN) and high
1 EX/P3-4 Pedestal dynamics in ELMy H-mode plasmas in JET
"... Abstract: The pedestal ELM dynamics has been studied on JET with improved diagnostic capability. The new High Resolution Thomson Scattering system enables detailed measurement of Te and ne pedestal profiles. A simple ELM coherent data selection technique is applied to select pre and post ELM profile ..."
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and plasma conditions. As a result the ELM convective losses are found to be a constant fraction of ~5-10 % the pedestal stored energy (Wped). In baseline ELMy H-mode the conductive energy losses vary greatly with collisionality (νe * ) from ~20 % of Wped at νe * <0.1 to ~5 % of Wped at νe *>0
ELM triggering by local pellet perturbations in type-I ELMy H-mode plasma at JET
, 2007
"... The pellet pacing ELM control concept developed at the mid sized tokamak ASDEX Upgrade is considered for the larger machines JET and ITER as well. By driving up the ELM frequency, the ELM size can be reduced and eventually suppressed below a dangerous level. An according pellet injection systems for ..."
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sufficiently small to avoid unbearable side- effects by particle fuelling. An ELM released by the local perturbation imposed by the ablating pellet in the plasma edge region is detected when only a minor fraction (less than 1%) of the fuelling size pellets (containing about 41021D) was ablated and deposited
PRINCETON PLASMA PHYSICS LABORATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY PPPL-3620 PPPL-3620 UC-70 Stiff Temperature Profiles in JT-60U ELMy H-mode Plasmas Availability Stiff Temperature Profiles in JT-60U ELMy H-mode Plasmas
"... Abstract The 'stiffness' of thermal transport in ELMy H-modes is examined in a series of carefully chosen JT-60U plasmas, and measured temperatures are compared with the predictions of several transport models. A heating power scan with constant T ped , a scan of pedestal temperature, T p ..."
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Abstract The 'stiffness' of thermal transport in ELMy H-modes is examined in a series of carefully chosen JT-60U plasmas, and measured temperatures are compared with the predictions of several transport models. A heating power scan with constant T ped , a scan of pedestal temperature
2-D spatial distribution of D-D and D-T neutron emission in JET ELMy H-mode plasmas with Tritium puff
"... JET neutron cameras detect both D-D 2.5 MeV and D-T 14 MeV fusion neutrons along 19 lines of sight (see in figure 1). This instrument, unique among similar diagnostics available at large fusion research facilities has a coarse spatial resolution of 15 cm and a time resolution currently of 10ms. Both ..."
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JET neutron cameras detect both D-D 2.5 MeV and D-T 14 MeV fusion neutrons along 19 lines of sight (see in figure 1). This instrument, unique among similar diagnostics available at large fusion research facilities has a coarse spatial resolution of 15 cm and a time resolution currently of 10ms. Both sets of detectors are absolutely calibrated at 2.5 MeV for D-D and 14
28 th EPS Conf. on Contr. Fusion and Plasma Physics, 2001, P3.11 Energy Confinement in Steady State ELMy H-modes in JET
"... During the last seven years an extensive confinement database has been assembled on JET of steady state ELMy H-mode plasmas. The database was started under the JET Joint Undertaking and has been continued under EFDA with the addition of a further 200 pulses. In this paper the database is used to ass ..."
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During the last seven years an extensive confinement database has been assembled on JET of steady state ELMy H-mode plasmas. The database was started under the JET Joint Undertaking and has been continued under EFDA with the addition of a further 200 pulses. In this paper the database is used
28th EPS Conf. on Contr. Fusion and Plasma Physics, 2001, P3.11 Energy Confinement in Steady State ELMy H-modes in JET
"... During the last seven years an extensive confinement database has been assembled on JET of steady state ELMy H-mode plasmas. The database was started under the JET Joint Undertaking and has been continued under EFDA with the addition of a further 200 pulses. In this paper the database is used to ass ..."
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During the last seven years an extensive confinement database has been assembled on JET of steady state ELMy H-mode plasmas. The database was started under the JET Joint Undertaking and has been continued under EFDA with the addition of a further 200 pulses. In this paper the database is used
Development of ITER 15 MA ELMy H-mode Inductive Scenario
"... Abstract. The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, and current, is a critical element for achieving mission performance. Analysis of PF capabilities has focused on the 15 MA Q = 10 scenario with a 300-500 s flattop b ..."
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burn phase. The operating space available for the 15 MA ELMy H-mode plasma discharges in ITER and upgrades to the PF coils or associated systems to establish confidence that ITER mission objectives can be reached have been identified. Time dependent self-consistent free-boundary calculations were
Results 1 - 10
of
729