Ion Temperature Inference from Neutron Counting in Maxwellian Deuterium Plasmas

A method is presented for inferring the deuterium fuel ion temperature from neutron counts measured with fast liquid scintillators in conditions where the ion velocity distribution is Maxwellian. Local neutron count rates at each scintillator position are combined to estimate total neutron yield from the plasma, where absolute detection efficiency is determined via MCNP neutron scattering simulation based on a 3D model of the experiment structure. This method is particularly advantageous for Magnetized Target Fusion applications as it yields a time-resolved diagnostic and does not require direct line-of-sight to the plasma or collimation of the neutrons. The instrumentation configuration, pulse-shape discrimination and pile-up correction algorithms, detector calibration, and ion temperature calculation method with uncertainty characterization are discussed. An application of the method to General Fusion's Plasma Injector~3 (PI3) spherical tokamak device is demonstrated and the results are compared to an Ion Doppler spectroscopy ion temperature diagnostic.

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Publication Details

Journal
Fusion Science & Technology
Published
2026-02-10
DOI
https://doi.org/10.1080/15361055.2026.2613327
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00
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article

Ion Temperature Inference from Neutron Counting in Maxwellian Deuterium Plasmas

R. Underwood, Myles T. Hildebrand, M. W. Reynolds, A. J. Radich et al.
Fusion Science & Technology
Magnetic confinement fusion research
article

Ion Temperature Inference from Neutron Counting in Maxwellian Deuterium Plasmas

R. Underwood, Myles T. Hildebrand, M. W. Reynolds, A. J. Radich, A. Rohollahi, V.V. Grecu, Stephen Howard, Colin P. McNally, Patrick J. F. Carle, Sara Weinstein
article en

Abstract

A method is presented for inferring the deuterium fuel ion temperature from neutron counts measured with fast liquid scintillators in conditions where the ion velocity distribution is Maxwellian. Local neutron count rates at each scintillator position are combined to estimate total neutron yield from the plasma, where absolute detection efficiency is determined via MCNP neutron scattering simulation based on a 3D model of the experiment structure. This method is particularly advantageous for Magnetized Target Fusion applications as it yields a time-resolved diagnostic and does not require direct line-of-sight to the plasma or collimation of the neutrons. The instrumentation configuration, pulse-shape discrimination and pile-up correction algorithms, detector calibration, and ion temperature calculation method with uncertainty characterization are discussed. An application of the method to General Fusion's Plasma Injector~3 (PI3) spherical tokamak device is demonstrated and the results are compared to an Ion Doppler spectroscopy ion temperature diagnostic.

Fusion Science & Technology
General Fusion (Canada) (CA)
Peace, Justice and strong institutions
Openalex Percentile: Top 93%
Magnetic confinement fusion research
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Ion Temperature Inference from Neutron Counting in Maxwellian Deuterium Plasmas — R. Underwood, Myles T. Hildebrand, et al. · Fusion Science & Technology (2026) | TGRS Research Map | TGRS