Brendan Crowley
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Research Subjects
Brendan Crowley has a total of 58 co-authors. Here are the top co-authors by number of shared publications:
- John T. Scoville
General Atomics, San Diego, CA, USA
8 shared publications - Amanda Marie Lietz
North Carolina State University
3 shared publications - Arthur Mazzeo
North Carolina State University
3 shared publications - Evan Kallenberg
Department of Nuclear Engineering, North Carolina State University, Raleigh, NC, USA
3 shared publications - Florian M. Laggner
North Carolina State University
3 shared publications J.M. Rauch
Gen Atom, POB 85608, San Diego, CA 92186 USA
3 shared publications
Latest Publications
- Open Access
- 1 February 2026
- Published by IOP Publishing in Plasma Sources Science and Technology
- Vol. 35 (2) , 025020
Fluid-kinetic modeling of a high power density radio frequency inductively coupled positive hydrogen ion source
High power density radio-frequency (RF) inductively coupled positive ion sources are attractive candidates for next-generation neutral beam injection (NBI) systems, where higher injected power and longer pulse lengths are desired without sacrificing source reliability. Operating at absorbed power densities of order > 1 W cm − 3 places these sources in a regime with stronger gas heating, higher dissociation, and non-Maxwellian electron energy distributions. The Large Uniform Plasma for Ionizing Neutrals (LUPIN) is an RF inductively coupled plasma source designed to explore this high power density regime and to provide guidance for a positive ion source upgrade for the DIII-D NBI system. LUPIN is designed to operate at up to 20 kW of RF power at 2 MHz, coupling energy through a cylindrical quartz vessel to achieve target ion current densities of 2100 A m − 2 . This paper presents fluid-kinetic modeling of LUPIN using the hybrid plasma equipment model where electrons are treated kinetically, and the simulations reveal that electron energy distribution function transitions from nearly Maxwellian in the core to bi-Maxwellian towards the edge. Parametric simulations investigate the effects of RF power, gas pressure, and frequency on plasma density, ion flux, and uniformity. Parametric sweeps reveal that increasing power shifts the primary ionization channel from molecular to atomic with diminishing flux gains due to skin-depth contraction and gas rarefaction. Higher frequency localizes heating and increases H 2 + and H 3 + delivery to the grid, while elevated pressure boosts ionization yet hinders ion transport due to increase in collisionality.
- 1 February 2026
- Published by IOP Publishing in Plasma Sources Science and Technology
- Vol. 35 (2) , 025020
Open AccessFluid-kinetic modeling of a high power density radio frequency inductively coupled positive hydrogen ion source
High power density radio-frequency (RF) inductively coupled positive ion sources are attractive candidates for next-generation neutral beam injection (NBI) systems, where higher injected power and longer pulse lengths are desired without sacrificing source reliability. Operating at absorbed power densities of order > 1 W cm − 3 places these sources in a regime with stronger gas heating, higher dissociation, and non-Maxwellian electron energy distributions. The Large Uniform Plasma for Ionizing Neutrals (LUPIN) is an RF inductively coupled plasma source designed to explore this high power density regime and to provide guidance for a positive ion source upgrade for the DIII-D NBI system. LUPIN is designed to operate at up to 20 kW of RF power at 2 MHz, coupling energy through a cylindrical quartz vessel to achieve target ion current densities of 2100 A m − 2 . This paper presents fluid-kinetic modeling of LUPIN using the hybrid plasma equipment model where electrons are treated kinetically, and the simulations reveal that electron energy distribution function transitions from nearly Maxwellian in the core to bi-Maxwellian towards the edge. Parametric simulations investigate the effects of RF power, gas pressure, and frequency on plasma density, ion flux, and uniformity. Parametric sweeps reveal that increasing power shifts the primary ionization channel from molecular to atomic with diminishing flux gains due to skin-depth contraction and gas rarefaction. Higher frequency localizes heating and increases H 2 + and H 3 + delivery to the grid, while elevated pressure boosts ionization yet hinders ion transport due to increase in collisionality.
- 4 August 2025
- Published by Taylor & Francis in Fusion Science and Technology
- Vol. 82 (1-2) , 92-105
Design and Study of Inductively Coupled Plasma Chamber Components Using the SupRISE Test Device at DIII-D
- 4 August 2025
- Published by Taylor & Francis in Fusion Science and Technology
- Vol. 82 (1-2) , 92-105
Design and Study of Inductively Coupled Plasma Chamber Components Using the SupRISE Test Device at DIII-D
- 16 June 2025
- Published by Taylor & Francis in Fusion Science and Technology
- Vol. 82 (1-2) , 79-91
Design and Engineering of LUPIN: A Test-Bed Radio-Frequency Ion Source for Enhanced Neutral Beam Injection on DIII-D
- 16 June 2025
- Published by Taylor & Francis in Fusion Science and Technology
- Vol. 82 (1-2) , 79-91
Design and Engineering of LUPIN: A Test-Bed Radio-Frequency Ion Source for Enhanced Neutral Beam Injection on DIII-D
- 1 September 2019
- Published by Elsevier in Fusion Engineering and Design
- Vol. 146, 1605-1609
Experimental studies of the arc chamber short circuit failure mechanism on the DIII-D neutral beam system
- 1 September 2019
- Published by Elsevier in Fusion Engineering and Design
- Vol. 146, 1605-1609
Experimental studies of the arc chamber short circuit failure mechanism on the DIII-D neutral beam system
- 1 September 2019
- Published by Elsevier in Fusion Engineering and Design
- Vol. 146, 6-9
New capabilities and upgrade path for the DIII-D neutral beam heating system
- 1 September 2019
- Published by Elsevier in Fusion Engineering and Design
- Vol. 146, 6-9
New capabilities and upgrade path for the DIII-D neutral beam heating system
- 22 May 2019
- Published by IOP Publishing in Nuclear Fusion
- Vol. 59 (7) , 076004
Feedback control of stored energy and rotation with variable beam energy and perveance on DIII-D
- 22 May 2019
- Published by IOP Publishing in Nuclear Fusion
- Vol. 59 (7) , 076004
Feedback control of stored energy and rotation with variable beam energy and perveance on DIII-D
- 20 April 2018
- Published by AIP Publishing in Physics of Plasmas
- Vol. 25 (5) , 056109
Dynamic neutral beam current and voltage control to improve beam efficacy in tokamaks
An engineering upgrade to the neutral beam system at the DIII-D tokamak [J. L. Luxon, Nucl. Fusion 42, 614 (2002)] enables time-dependent programming of the beam voltage and current. Initial application of this capability involves pre-programmed beam voltage and current injected into plasmas that are known to be susceptible to instabilities that are driven by energetic ( keV) beam ions. These instabilities, here all Alfvén eigenmodes (AEs), increase the transport of the beam ions beyond a classical expectation based on particle drifts and collisions. Injecting neutral beam power, MW, at reduced voltage with increased current reduces the drive for Alfvénic instabilities and results in improved ion confinement. In lower-confinement plasmas, this technique is applied to eliminate the presence of AEs across the mid-radius of the plasmas. Simulations of those plasmas indicate that the mode drive is decreased and the radial extent of the remaining modes is reduced compared to a higher beam voltage case. In higher-confinement plasmas, this technique reduces AE activity in the far edge and results in an interesting scenario of beam current drive improving as the beam voltage reduces from 80 kV to 65 kV.- 20 April 2018
- Published by AIP Publishing in Physics of Plasmas
- Vol. 25 (5) , 056109
Dynamic neutral beam current and voltage control to improve beam efficacy in tokamaks
An engineering upgrade to the neutral beam system at the DIII-D tokamak [J. L. Luxon, Nucl. Fusion 42, 614 (2002)] enables time-dependent programming of the beam voltage and current. Initial application of this capability involves pre-programmed beam voltage and current injected into plasmas that are known to be susceptible to instabilities that are driven by energetic ( keV) beam ions. These instabilities, here all Alfvén eigenmodes (AEs), increase the transport of the beam ions beyond a classical expectation based on particle drifts and collisions. Injecting neutral beam power, MW, at reduced voltage with increased current reduces the drive for Alfvénic instabilities and results in improved ion confinement. In lower-confinement plasmas, this technique is applied to eliminate the presence of AEs across the mid-radius of the plasmas. Simulations of those plasmas indicate that the mode drive is decreased and the radial extent of the remaining modes is reduced compared to a higher beam voltage case. In higher-confinement plasmas, this technique reduces AE activity in the far edge and results in an interesting scenario of beam current drive improving as the beam voltage reduces from 80 kV to 65 kV.- 1 October 2015
- Published by Elsevier in Fusion Engineering and Design
- Vol. 96-97, 443-446
Modeling and experimental studies of the DIII-D neutral beam system
- 1 October 2015
- Published by Elsevier in Fusion Engineering and Design
- Vol. 96-97, 443-446
Modeling and experimental studies of the DIII-D neutral beam system
- 1 August 2015
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 463, 787-791
Thermal behavior and temperature measurements of melting beryllium plasma-facing components exposed to high heat flux
- 1 August 2015
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 463, 787-791
Thermal behavior and temperature measurements of melting beryllium plasma-facing components exposed to high heat flux
- 1 May 2015
- Published by Institute of Electrical and Electronics Engineers (IEEE)
- p. 1-6
Benchmark testing of DIII-D neutral beam modeling with water flow calorimetry
Power loading on beamline components in the DIII-D neutral beam system is measured using water flow calorimetry. The results are used to benchmark beam transport models. Anomalously high heat loads in the magnet region are investigated and a speculative hypothesis as to their origin is presented.
- 1 May 2015
- Published by Institute of Electrical and Electronics Engineers (IEEE)
- p. 1-6
Benchmark testing of DIII-D neutral beam modeling with water flow calorimetry
Power loading on beamline components in the DIII-D neutral beam system is measured using water flow calorimetry. The results are used to benchmark beam transport models. Anomalously high heat loads in the magnet region are investigated and a speculative hypothesis as to their origin is presented.