The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library

Pankin, A.Y.; McCune, D.; André, R.; Bateman, G.; Kritz, A.H.

doi:10.1016/j.cpc.2003.11.002

Cited by 699 publications

(705 citation statements)

References 30 publications

Supporting

Mentioning

663

Contrasting

Unclassified

Order By: Relevance

“…From figure 20 it can be seen that the locations where the mode exchanges energy with the RSAE coincide very well with the resonances as calculated from equation (23). A good coupling between the particle and the mode occurs for resonances with a pitch between −0.25 and 0.05 and 0.25 and 0.75.…”

Section: Single Partice Resonancessupporting

confidence: 62%

See 1 more Smart Citation

A description of the full-particle-orbit-following SPIRAL code for simulating fast-ion experiments in tokamaks

Kramer

Budny

Bortolon

et al. 2013

Plasma Phys. Control. Fusion

View full text Add to dashboard Cite

The numerical methods used in the full particle-orbit following SPIRAL code are described and a number of physics studies performed with the code are presented to illustrate its capabilities. The SPIRAL code is a test-particle code and is a powerful numerical tool to interpret and plan fast-ion experiments in tokamaks. Gyro-orbit effects are important for fast ions in low-field machines such as NSTX and to a lesser extent in DIII-D. A number of physics studies are interlaced between the description of the code to illustrate its capabilities. Results on heat loads generated by a localized error-field on the DIII-D wall are compared with measurements. The enhanced Triton losses caused by the same localized error-field are calculated and compared with measured neutron signals. Magnetohydrodynamic (MHD) activity such as tearing modes and toroidicity-induced Alfvén eigenmodes (TAEs) have a profound effect on the fast-ion content of tokamak plasmas and SPIRAL can calculate the effects of MHD activity on the confined and lost fast-ion population as illustrated for a burst of TAE activity in NSTX. The interaction between ion cyclotron range of frequency (ICRF) heating and fast ions depends solely on the gyro-motion of the fast ions and is captured exactly in the SPIRAL code. A calculation of ICRF absorption on beam ions in ITER is presented. The effects of high harmonic fast wave heating on the beam-ion slowing-down distribution in NSTX is also studied.

show abstract

Section: Single Partice Resonancessupporting

confidence: 62%

“…to obtain only the linear resonances as given by equation (23). From figure 20 it can be seen that the locations where the mode exchanges energy with the RSAE coincide very well with the resonances as calculated from equation (23).…”

Section: Single Partice Resonancesmentioning

confidence: 53%

A description of the full-particle-orbit-following SPIRAL code for simulating fast-ion experiments in tokamaks

Kramer

Budny

Bortolon

et al. 2013

Plasma Phys. Control. Fusion

View full text Add to dashboard Cite

show abstract

“…The recent introduction of the Motional Stark Effect (MSE) diagnostic on NSTX gives considerably greater confidence in this constraint. The neutral beam injection (NBI) properties in the plasma are calculated with NUBEAM [5,6], a Monte Carlo orbit following algorithm. TRANSP contains several peripheral physics models, fast particle physics, and neutral particle effects.…”

Section: Computational Approachmentioning

confidence: 99%

Long pulse high performance plasma scenario development for the National Spherical Torus Experiment

Kessel

Bell

et al. 2006

Physics of Plasmas

View full text Add to dashboard Cite

Abstract.The National Spherical Torus Experiment (NSTX) [Ono, M., et al., Nucl. Fusion, 44, (2004), 452.] is targeting long pulse high performance, non-inductive sustained operations at low aspect ratio, and the demonstration of non-solenoidal startup and current rampup. The modeling of these plasmas provides a framework for experimental planning and identifies the tools to access these regimes. Simulations based on NBI (Neutral Beam Injection)-heated plasmas are made to understand the impact of various modifications and identify the requirements for 1) high elongation and triangularity, 2) density control to optimize the current drive, 3) plasma rotation and/or feedback stabilization to operate above the no-wall β limit, and 4) Electron Bernstein Waves (EBW) for off-axis heating/current drive (H/CD). Integrated scenarios are constructed to provide the transport evolution and H/CD source modeling, supported by rf and stability analyses. Important factors include the energy confinement, Z eff , early heating/H-mode, broadening of the NBI-driven current profile, and maintaining q(0) and q min >1.0. Simulations show that non-inductive sustained plasmas can be reached at I P =800 kA, B T =0.5 T, κ≈2.5, β N ≤5, β≤15%, f NI =92%, and q(0)>1.0 with NBI H/CD, density control, and similar global energy confinement to experiments. The non-inductive sustained high β plasmas can be reached at I P =1.0 MA, B T =0.35 T, κ≈2.5, β N ≤9, β≤43%, f NI =100%, and q(0)>1.5 with NBI H/CD and 3.0 2 MW of EBW H/CD, density control, and 25% higher global energy confinement than experiments. A scenario for non-solenoidal plasma current rampup is developed using High Harmonic Fast Wave (HHFW) H/CD in the early low I P and low T e phase, followed by NBI H/CD to continue the current ramp, reaching a maximum of 480 kA after 3.4 s.

show abstract

“…The pellet system at AUG was recently upgraded and is now capable of delivering pellets with different sizes, speeds and repetitions rates up to 70 Hz. More details can be found in [16]. An example where the full fuelling capability of the new system has been exploited is shown in Fig.…”

Section: High Density Plasmas With Pelletsmentioning

confidence: 99%

“…The aim of this work is to gain a better understanding of the heat transport under such conditions. For this purpose transport analyses taking into account the spatial distribution of the radiated power have been performed with the TRANSP code [16]. The inputs are the 01007-p.5 experimental kinetic profiles and the modelled radiation distribution described in the previous section using the measured impurity concentrations.…”

Section: Transport Analysis Of Radiative Cooling Experimentsmentioning

confidence: 99%

Transport analysis of high radiation and high density plasmas in the ASDEX Upgrade tokamak

Casali

Bernert

Dux

et al. 2014

EPJ Web of Conferences

View full text Add to dashboard Cite

Abstract. Future fusion reactors, foreseen in the "European road map" such as DEMO, will operate under more demanding conditions compared to present devices. They will require high divertor and core radiation by impurity seeding to reduce heat loads on divertor target plates. In addition, DEMO will have to work at high core densities to reach adequate fusion performance. The performance of fusion reactors depends on three essential parameters: temperature, density and energy confinement time. The latter characterizes the loss rate due to both radiation and transport processes. The DEMO foreseen scenarios described above were not investigated so far, but are now addressed at the ASDEX Upgrade tokamak. In this work we present the transport analysis of such scenarios. Plasma with high radiation by impurity seeding: transport analysis taking into account the radiation distribution shows no change in transport during impurity seeding. The observed confinement improvement is an effect of higher pedestal temperatures which extend to the core via stiffness. A non coronal radiation model was developed and compared to the bolometric measurements in order to provide a reliable radiation profile for transport calculations. High density plasmas with pellets: the analysis of kinetic profiles reveals a transient phase at the start of the pellet fuelling due to a slower density build up compared to the temperature decrease. The low particle diffusion can explain the confinement behaviour.

show abstract

The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library

Cited by 699 publications

References 30 publications

A description of the full-particle-orbit-following SPIRAL code for simulating fast-ion experiments in tokamaks

A description of the full-particle-orbit-following SPIRAL code for simulating fast-ion experiments in tokamaks

Long pulse high performance plasma scenario development for the National Spherical Torus Experiment

Transport analysis of high radiation and high density plasmas in the ASDEX Upgrade tokamak

Contact Info

Product

Resources

About