B. LaBombard
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View article: Determination of confinement regime boundaries via separatrix parameters on Alcator C-Mod based on a model for interchange-drift-Alfvén turbulence
Determination of confinement regime boundaries via separatrix parameters on Alcator C-Mod based on a model for interchange-drift-Alfvén turbulence Open
The separatrix operational space (SepOS) model (Eich and Manz 2021 Nucl. Fusion 61 086017) is shown to predict the L–H transition, the L-mode density limit, and the ideal magnetohydrodynamic ballooning limit in terms of separatrix paramete…
View article: The low frequency edge oscillation in alcator C-Mod and ASDEX upgrade I-mode
The low frequency edge oscillation in alcator C-Mod and ASDEX upgrade I-mode Open
The low frequency edge oscillation (LFEO) is a low frequency fluctuation in many plasma quantities in the pedestal region of the I-Mode confinement regime. It is observed on Alcator C-Mod between 10–30 kHz and on ASDEX Upgrade between 5–10…
View article: Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a high-power neon-seeded scenario in the DTT
Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a high-power neon-seeded scenario in the DTT Open
In this work, we cross-compare the state-of-the-art edge plasma codes SOLPS-ITER, SOLEDGE2D, and UEDGE in a reactor-relevant neon-seeded Divertor Tokamak Test scenario at nominal power, extending the simplified test-bed of Moscheni et al (…
View article: DEGAS 2 model validation study: comparison of measured and modeled helium and deuterium line emission arising from an external gas puff on Alcator C-Mod
DEGAS 2 model validation study: comparison of measured and modeled helium and deuterium line emission arising from an external gas puff on Alcator C-Mod Open
The ability to accurately model and predict neutral transport in the boundary plasma is important for tokamak operation. Nevertheless, validation of neutral transport models can be challenging due to the difficulty in measuring neutral par…
View article: Comment on ‘Relationship between magnetic field and tokamak size—a system engineering perspective and implications to fusion development’
Comment on ‘Relationship between magnetic field and tokamak size—a system engineering perspective and implications to fusion development’ Open
The recent Federici et al (2024 Nucl. Fusion 64 036025) article makes the argument that higher magnetic fields cannot reduce the size and cost of a tokamak-based fusion power plant due to: structural considerations of the toroidal field (T…
View article: Design, Fabrication, and Assembly of the SPARC Toroidal Field Model Coil
Design, Fabrication, and Assembly of the SPARC Toroidal Field Model Coil Open
The SPARC Toroidal Field Model Coil (TFMC) is the first large-scale (∼3 m), high-field (∼20 T) superconducting fusion magnet based on Rare Earth Yttrium Barium Copper Oxide (REBCO). Its objective was to retire risk for the toroidal field m…
View article: Building the Runway: A New Superconducting Magnet Test Facility Made for the SPARC Toroidal Field Model Coil
Building the Runway: A New Superconducting Magnet Test Facility Made for the SPARC Toroidal Field Model Coil Open
A new superconducting magnet test facility was created at the MIT Plasma Science and Fusion Center (PSFC) for the SPARC Toroidal Field Model Coil (TFMC) program. The facility was designed and constructed in parallel with the TFMC between 2…
View article: The SPARC Toroidal Field Model Coil Program
The SPARC Toroidal Field Model Coil Program Open
The SPARC Toroidal Field Model Coil (TFMC) Program was a three-year effort between 2018 and 2021 that developed novel Rare Earth Barium Copper Oxide (REBCO) superconductor technologies and then successfully utilized these technologies to d…
View article: Performance of demountable solder joints for no-insulation superconducting coils produced by vacuum pressure impregnation
Performance of demountable solder joints for no-insulation superconducting coils produced by vacuum pressure impregnation Open
No-insulation high temperature superconductor (HTS) stack coils show both increased thermal and electrical stability, and present a simplified geometry for the integration of demountable joints. Demountability is a desirable feature for ma…
View article: Strongly intermittent far scrape-off layer fluctuations in Alcator C-Mod plasmas close to the empirical discharge density limit
Strongly intermittent far scrape-off layer fluctuations in Alcator C-Mod plasmas close to the empirical discharge density limit Open
Intermittent plasma fluctuations in the boundary region of the Alcator C-Mod device were comprehensively investigated using data time-series from gas puff imaging and mirror Langmuir probe diagnostics. Fluctuations were sampled during stat…
View article: The SPARC Toroidal Field Model Coil Program
The SPARC Toroidal Field Model Coil Program Open
The SPARC Toroidal Field Model Coil (TFMC) Program was a three-year effort between 2018 and 2021 that developed novel Rare Earth Yttrium Barium Copper Oxide (REBCO) superconductor technologies and then successfully utilized these technolog…
View article: Strongly intermittent far scrape-off layer fluctuations in Alcator C-Mod plasmas close to the empirical discharge density limit
Strongly intermittent far scrape-off layer fluctuations in Alcator C-Mod plasmas close to the empirical discharge density limit Open
Intermittent plasma fluctuations in the boundary region of the Alcator C-Mod device were comprehensively investigated using data time-series from gas puff imaging and mirror Langmuir probe diagnostics. Fluctuations were sampled during stat…
View article: Scalability analysis of direct and iterative solvers used to model charging of superconducting pancake solenoids
Scalability analysis of direct and iterative solvers used to model charging of superconducting pancake solenoids Open
A mathematical model for the charging simulation of non-insulated superconducting pancake solenoids is presented. Numerical solutions are obtained by the simulation model using a variety of solvers. A scalability analysis is performed for …
View article: 10.1063/5.0088216.1
10.1063/5.0088216.1 Open
The role of turbulence in setting boundary plasma conditions is presently a key uncertainty in projecting to fusion energy reactors. To robustly diagnose edge turbulence, we develop and demonstrate a technique to translate brightness measu…
View article: Deep modeling of plasma and neutral fluctuations from gas puff turbulence imaging
Deep modeling of plasma and neutral fluctuations from gas puff turbulence imaging Open
The role of turbulence in setting boundary plasma conditions is presently a key uncertainty in projecting to fusion energy reactors. To robustly diagnose edge turbulence, we develop and demonstrate a technique to translate brightness measu…
View article: Dependence of the boundary heat flux width on core and edge profiles in Alcator C-Mod
Dependence of the boundary heat flux width on core and edge profiles in Alcator C-Mod Open
This work presents new evidence that the heat flux width, λ q , in the Alcator C-Mod tokamak scales with the edge electron pressure, as observed in the ASDEX Upgrade (AUG) tokamak (Silvagni et al 2020 Plasma Phys. Control. Fusion 62 045015…
View article: First application of a digital mirror Langmuir probe for real-time plasma diagnosis
First application of a digital mirror Langmuir probe for real-time plasma diagnosis Open
For the first time, a digital Mirror Langmuir Probe (MLP) has successfully sampled plasma temperature, ion saturation current, and floating potential together on a single probe tip in real time in a radio-frequency driven helicon linear pl…
View article: Simulation of the SPARC plasma boundary with the UEDGE code
Simulation of the SPARC plasma boundary with the UEDGE code Open
Here in this work, the UEDGE edge transport code is used to examine conditions in the SPARC divertor and edge plasma for various levels of carbon impurity and power from the core (PSOL). A double-null magnetic configuration is simulated as…
View article: High Field Side Launch of Lower Hybrid Waves: A Scoping Study for ADX
High Field Side Launch of Lower Hybrid Waves: A Scoping Study for ADX Open
Launching lower hybrid (LH) waves from the high field side (HFS) of a tokamak offers significant advantages over low field side (LFS) launch with respect to both wave physics and plasma material interactions (PMI). The higher magnetic fiel…
View article: Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations
Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations Open
The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well as for the design of the ITER divertor. The numerical scheme of the plasma solver of the code, B2.5, is based on the assumptio…
View article: Impurity screening behavior of the high-field side scrape-off layer in near-double-null configurations: prospect for mitigating plasma-material interactions on RF actuators and first-wall components
Impurity screening behavior of the high-field side scrape-off layer in near-double-null configurations: prospect for mitigating plasma-material interactions on RF actuators and first-wall components Open
The impurity screening response of the high-field side (HFS) scrape-off layer (SOL) to localized nitrogen injection is investigated on Alcator C-Mod for magnetic equilibria spanning lower-single null, double-null and upper single null conf…
View article: Alcator C-Mod: Research in support of ITER and steps beyond
Alcator C-Mod: Research in support of ITER and steps beyond Open
This paper presents an overview of recent highlights from research on Alcator C-Mod. Significant progress has been made across all research areas over the last two years, with particular emphasis on divertor physics and power handling, pla…
View article: Overview of the SPARC tokamak
Overview of the SPARC tokamak Open
The SPARC tokamak is a critical next step towards commercial fusion energy. SPARC is designed as a high-field ( $B_0 = 12.2$ T), compact ( $R_0 = 1.85$ m, $a = 0.57$ m), superconducting, D-T tokamak with the goal of producing fusion gain $…
View article: Divertor heat flux challenge and mitigation in SPARC
Divertor heat flux challenge and mitigation in SPARC Open
Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges …
View article: Scalability Analysis of Direct and Iterative Solvers Used to Model Charging of Non-insulated Superconducting Pancake Solenoids
Scalability Analysis of Direct and Iterative Solvers Used to Model Charging of Non-insulated Superconducting Pancake Solenoids Open
A mathematical model for the charging simulation of non-insulated superconducting pancake solenoids is presented. Numerical solutions are obtained by the simulation model implemented on the Petra-M FEM platform using a variety of solvers. …
View article: Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept
Performance assessment of long-legged tightly-baffled divertor geometries in the ARC reactor concept Open
Extremely intense power exhaust channels are projected for tokamak-based fusion power reactors; a means to handle them remains to be demonstrated. Advanced divertor configurations have been proposed as potential solutions. Recent modelling…
View article: Study of passively stable, fully detached divertor plasma regimes attained in innovative long-legged divertor configurations
Study of passively stable, fully detached divertor plasma regimes attained in innovative long-legged divertor configurations Open
Numerical modeling of divertor configurations with radially or vertically extended, tightly baffled, outer divertor legs has demonstrated the existence of a passively-stable fully detached divertor regime. Here in the simulations, long-leg…