IEEE 2026 NSS MIC RTSD

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Neutron and gamma-ray detectors and applications, including security, dosimetry and other related applications

Session chair: LYOUSSI, Abdallah, Professor (CEA / French Atomic Energy and Alternative Energies Commission, CEA/DES/IRESNE/DER, Saint Paul-lez-Durance, France); Jovanovic, Igor, Professor (University of California, Berkeley, Department of Nuclear Engineering, Berkeley, USA)
 
Shortcut: NSS-18
Date: Wednesday, 11 November, 2026, 17:30 - 19:00
Location: MACHADO
Session type: NSS Session

Contents

Click on an contribution to preview the abstract content.

The underlined authors are the presenters. The authors in bold are the main authors.

17:30 NSS-18-01

Fast Neutron Spectrometer for Fusion Diagnostics (#3079)

K. Sharma1, F. Retiere1

1 a. TRIUMF, 4004 Wesbrook Mall, Vancouver, British Columbia V6T 2A3, Canada, Vancouver, British Columbia, Canada

Abstract

Advancements in Silicon Photomultiplier (SiPM) performance in recent years have demonstrated success across a broad range of fields, including particle and nuclear physics, Positron Emission Tomography, Light Detection and Ranging technology, Fusion diagnostics, among others. This work develops a time-of-flight (ToF)–based neutron spectrometer using SiPMs coupled to plastic scintillators as a plasma fusion diagnostic tool. A Deuterium-fueled plasma fusion emits 2.45MeV neutrons with an energy spectrum broadened by ion kinematics. The achievable neutron energy resolution of the spectrometer is correlated to the relative uncertainty on the inferred plasma ion temperature, a critical parameter for evaluating plasma performance and viability of the fusion approach. The target relative uncertainty on temperature is below 20%, therefore constraining the neutron interaction time and position resolution within the spectrometer. A two-layer (L1–L2) detector array is in development at TRIUMF. The detector coupled with fast data acquisition is expected to successfully detect neutrons at GHz rate. Timing-Position resolution of the chosen scintillators (Eljen L1: EJ232Q 0.5% Benzophenone doped; L2: EJ230) paired with Broadcom series AFBR-S4N SiPMs is presented as proof of concept in the neutron energy range of interest. A 511keV-gamma source is used to characterize the timing and position response of a single scintillator–SiPM assembly, incorporating the light yield differences between gamma and neutron interactions accounted for via Birks' law. Techniques and results demonstrating time resolution ranging 60 to 120ps with energy in Layer 1 and preliminary work on Layer 2 will be presented.

AcknowledgmentThis work was supported in part by the Natural Sciences and Engineering Research Council of Canada (NSERC).
Keywords: Neutron Spectrometer, Time of Flight, Fast timing
17:45 NSS-18-02

Pixel Size-Induced Visibility Degradation and Its Mitigation for X-ray Dark-Field Baggage Scanners (#2055)

Z. Wang1, P. Guo1, J. Tian2, L. Men1, X. Li3, C. Wu4, 1, X. Ran1, Z. Deng1, L. Zhang1, Z. Wang1

1 Tsinghua University, Department of Engineering Physics, Beijing, China
2 Science and Technology Research Center of China Customs, Beijing, China
3 Nuctech Company Limited, Beijing, China
4 Technical University of Denmark, Department of Physics, Kongens Lyngby, Denmark

Abstract

X-ray dark-field (DF) imaging enables detection of low-Z scattering materials such as powdered explosives and narcotics, which are indistinguishable in conventional absorption imaging, making it a transformative technology for security screening. However, industrial baggage scanners face an inherent trade-off: high-throughput operation requires large-pixel detectors to capture sufficient photon flux at 160 kV operating voltages, but this causes severe Moiré fringe blurring that fundamentally limits DF sensitivity. In our previous work, we developed a 160 kV dark-field baggage scanner prototype, but found that the 2.7 mm × 3.0 mm large-pixel detectors we used only achieved a fringe visibility of ~7.3% under practical operating conditions, severely limiting DF sensitivity. To address this bottleneck, this study quantitatively investigates pixel size-induced visibility degradation through physics-informed simulations and experimental validation on a benchtop grating interferometry platform. Results confirm the visibility decay trend predicted by the sinc model, and show that a 0.5 mm small-pixel detector achieves ~30% improvement in DF sensitivity for high-energy X-ray dark-field baggage scanners. This work provides critical quantitative guidance for optimizing these systems to improve hazardous material detection.

AcknowledgmentThis work was supported in part by National Key Research and Development Program of China (No. 2023YFC2605802) and National Natural Science Foundation of China (No. 62227804).
References
[1] F. Pfeiffer, M. Bech, O. Bunk, et al., "Hard-X-ray dark-field imaging using a grating interferometer," Nature Materials, vol. 7, pp. 134–137, 2008.
[2] J. H. Hubbell, W. J. Veigele, E. A. Briggs, et al., "Atomic form factors, incoherent scattering functions, and photon scattering cross sections," J. Phys. Chem. Ref. Data, vol. 4, pp. 471–538, 1975.
[3] A. P. Sauter, J. Andrejewski, M. Frank, et al., "Correlation of image quality parameters with tube voltage in X-ray dark-field chest radiography: a phantom study," Scientific Reports, vol. 11, Art. no. 14130, 2021.
[4] X. Ran, Z. Deng, Y. Song, and H. Gao, “Development of a Simultaneous Photon Counting and Energy Integrating Detector for X-Ray Imaging Applications,” IEEE Trans. Nucl. Sci., vol. 73, no. 1, pp. 147–156, Jan. 2026.
[5] C. Wu, “Research on information retrieval theory and performance optimization methods for grating-based X-ray multi-contrast imaging,” Ph.D. dissertation, Dept. Eng. Phys., Tsinghua Univ., Beijing, China, 2022.
Keywords: Dark-field imaging, Security inspection, Dark-field sensitivity, Fringe visibility
18:00 NSS-18-03

Three-Dimensional Isotopic Imaging via Portable Neutron Resonance Transmission Analysis (#2122)

K. Sanchez1, A. Danagoulian1, N. Kowitt1

1 MIT, NSE, Cambridge, Massachusetts, United States of America

Abstract

Nuclear material safeguards demand portable, isotope specific verification methods capable of operating across diverse deployment contexts. Neutron Resonance Transmission Analysis (NRTA) exploits isotope-specific resonances in neutron cross sections to provide definitive material identification, but portable implementations have been constrained to one-dimensional areal density measurements. Here we present a compact pixelated NRTA system that achieves three-dimensional isotopic imaging through a deuterium-tritium neutron generator, a multi-element GS20 $^6$Li scintillator array, and Algebraic Reconstruction Technique (ART) algorithms. Systematic benchmarking establishes operational limits: maximum target dimensions of 17.5 × 17.5 × 17.5 cm, stand-off distances up to 17.5 cm, spatial resolution of 2.5 cm, and complete three-dimensional reconstruction within four hours using eight measurement angles at 30 minutes per angle. Three-dimensional reconstruction of both homogeneous and non-homogeneous tungsten and silver targets is demonstrated experimentally. This system extends portable NRTA beyond one-dimensional assay, enabling field-deployable isotopic imaging previously available only at large centralized neutron facilities.

References
[1] Prasad, S. et al. Nonproliferation improvements and challenges presented by small modular reactors. Prog. Nucl. Energy 80, 102–109 (2015).
[2] Anderson, I. S. et al. Research opportunities with compact accelerator driven neutron sources. Phys. Rep. 654, 1–58 (2016).
[3] Postma, H. & Schillebeeckx, P. Neutron resonance capture and transmission analysis. In Encyclopedia of Analytical Chemistry (Wiley, 2009).
[4] Gozani, T. Active Nondestructive Assay of Nuclear Materials: Principles and Applications. NUREG/CR-0602 (US NRC, 1981).
[5] Klein, E. A. et al. Neutron-resonance transmission analysis with a compact deuterium-tritium neutron generator. Phys. Rev. Appl. 15,054026 (2021).
[6] Rahon, J. M. Compact Capabilities: Developing and Evaluating a Field-Portable Neutron Resonance Capture Analysis System. Thesis, Massachusetts Institute of Technology (2024).
[7] Brown, D. et al. ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data. Nucl. Data Sheets 148, 1–142 (2018).
[8] Gordon, R., Bender, R. & Herman, G. T. Algebraic reconstruction techniques (ART) for three-dimensional electron microscopy and X-ray photography. J. Theor. Biol. 29, 471–481 (1970).
Keywords: Neutron Imaging, Neutron Resonance, Image Reconstruction, Isotopic Imaging
18:15 NSS-18-04

Neutron diffraction-contrast tomography demonstration using event-based Timepix camera (#2157)

A. Khaplanov1, K. An1, S. Kabra1, S. Qian1, G. Nagy1, C. Zhang1

1 Oak Ridge National Laboratory, NScD, Oak Ridge, Tennessee, United States of America

Abstract

Diffraction contrast tomography is used extensively on x-ray scattering instruments, however, its neutron counterpart has up till now been elusive, in part due to detector limitations. Scintillator-coupled Timepix detectors offer high spatial resolution, event-mode readout, and improved rate capability, making them attractive for neutron scattering and imaging applications. Here we evaluate a LumaCam detector equipped with a TPX3Cam and a ZnO:Zn:6LiF scintillator in a near-field diffraction setup. Scintillation light was focused in a lens onto a 25mm-diameter MCP-based image intensifier. Intensified light was refocused onto a 0.3mm-thick Si sensor with a thin window bonded to a Timepix3 ASIC. Hits were collected in and clusterie to increase position resolution beyond the native pixelation of the ASIC. The detector was placed 10 cm from the sample at 90 degrees to the beam and calibrated using a silicon powder sample. A refractory alloy sample with grains up to 1mm was measured over 180 degrees of rotation. Diffraction spots were assigned to reflections from several crystallographic orientations. By correlating angular separations and relative intensities, 75 grains were identified. Results demonstrate the feasibility of compact grain-resolved neutron diffraction using Timepix camera technology. Irregular spot shapes indicate sensitivity to grain morphology, however, resolution is smeared by beam divergence. Thus, to fully exploit available detector resolution, shorter sample-to-detector distances are currently being explored. Ongoing work combines near-field diffraction with simultaneous transmission imaging to achieve neutron diffraction contrast tomography by relating diffraction spots to grain locations.

AcknowledgmentThis research used resources of the Spallation Neutron Source, High-Flux Isotope Reactor at ORNL. ORNL is managed by UT-Battelle LLC for DOE’s Office of Science, the single largest supporter of basic research in the physical sciences in the US.
Keywords: Neutron detection, Time-of-flight neutron diffraction, Timepix3, photon counting detecto
18:30 NSS-18-05

Associated-Particle Neutron Time-of-Flight Measurements of Curium-244 and Californium-252 (#2360)

A. Parker1, M. D. Aspinall3, F. Cave2, S. Croft1, A. Grievson5, B. Swinson4, M. Joyce1, 2

1 Lancaster University (Lancaster), School of Engineering, Lancaster, United Kingdom
2 Hybrid Instruments Ltd, Gillow Avenue, Lancaster, United Kingdom
3 Aspinall Instruments, Lancaster, United Kingdom
4 Alpha Safety PSC, Sante Fe, New Mexico, United States of America
5 Mirion Technologies UK Ltd, Warrington, United Kingdom

Abstract

γ-triggered neutron time-of-flight technique was used to measure fast-neutron spectra from spontaneous fission sources using two EJ-309 liquid scintillator detectors operated in coincidence. Prompt γ-ray detection provided the timing reference for neutron energy reconstruction. Measurements were performed using bare 244Cm and 252Cf sources, together with a moderated 252Cf configuration to investigate scattering effects. Time-of-flight spectra were reconstructed into neutron energy distributions with corrections for detector efficiency and the non-linear time–energy relationship, supported by GEANT4 detector-response simulations. The reconstructed spectra were fitted using Maxwellian and Watt functions. Extracted Maxwellian temperatures were 1.89 MeV for bare 252Cf, 1.41–1.51 MeV for moderated 252Cf, and 1.48 MeV for 244Cm, demonstrating the expected spectral softening caused by moderation. Although systematic deviations from literature values were observed due to detector threshold and efficiency limitations, the method successfully resolved relative differences between source configurations. The results demonstrate the suitability of γ-triggered nToF spectrometry for comparative neutron spectral characterisation.

AcknowledgmentThis work was fund by the UKs Science and Technolgies Funding Council, via the DSI: Late-stage commercialisation for time-of-flight neutron spectrometer grant.
Keywords: Fast neutron spectroscopy, plastic scintillators, neutron temperature, liquid scintillators
18:45 NSS-18-06

Quantitative Contamination Mapping Using an Electron-Tracking Compton Camera for Nuclear Decommissioning (#1819)

D. Satoh1, A. Takada2, Y. Koda1, S. Sonoda3, 2, T. Tanimori4, 3

1 Japan Atomic Energy Agency, Ibaraki, Japan
2 Kyoto University, Kyoto, Japan
3 ERRAI Corporation, Kyoto, Japan
4 Kitasato University, Kanagawa, Japan

Abstract

Quantitative evaluation of radioactive contamination is essential for nuclear decommissioning; however, conventional survey methods provide limited spatial information, and conventional Compton cameras lack quantitative imaging capability due to their non-unique source reconstruction, in which the source position spreads into a cone. In this work, we investigate the applicability of an Electron-Tracking Compton Camera (ETCC) [1] to quantitative gamma-ray imaging in a decommissioning environment. The ETCC consists of a gaseous Time Projection Chamber (TPC) as the scatterer and a pixel scintillator array as the absorber. By reconstructing recoil electron tracks in the TPC, the ETCC uniquely solves the Compton kinematics, enabling a one-to-one correspondence between the source direction and the reconstructed image, in contrast to conventional Compton cameras. Measurements were conducted at the Prototype Advanced Thermal Reactor "FUGEN," currently under decommissioning. A 60Co hot spot with a dose rate of approximately 1 μSv/h was successfully identified and imaged, and the dose rate estimated from the ETCC data was consistent with that obtained from a survey meter. In addition, weak 60Co contamination at approximately 0.08 μSv/h, close to the background level and below the sensitivity limit of conventional survey meters, was visualized through direction-resolved analysis. These results demonstrate that the ETCC enables quantitative and sensitive imaging of radioactive contamination and can complement conventional survey methods, with potential to improve the efficiency of contamination assessment and clearance verification in nuclear decommissioning.

AcknowledgmentThe authors would like to thank the staff of the FUGEN Decommissioning Engineering Center for their dedicated support during the experiments. This work was supported by JSPS KAKENHI Grant Number JP23K26591.
References
[1] Takada, A, Takemura, T, Yoshikawa, K, Mizumura, Y, Ikeda, T, Nakamura, Y, Onozaka, K, Abe, M, Hamaguchi, K, Kubo, H, Kurosawa, S, Miuchi, K, Saito, K, Sawano, T & Tanimori, T 2022, 'First Observation of the MeV Gamma-Ray Universe with Bijective Imaging Spectroscopy Using the Electron-tracking Compton Telescope on Board SMILE-2+', The Astrophysical Journal, vol. 930, no. 1, Art. no. 6, Bristol: IOP Publishing.
Keywords: Decommissioning, Compton Camera, Gamma-ray Imaging, Quantitative Analysis


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