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: Lalleman, Anne-Sophie, Dr. (CEA, GIF SUR YVETTE, France); Joyce, MalcolmJ., Professor (Lancaster University, Department of Engineering, Lancaster, UK)
 
Shortcut: NSS-05
Date: Tuesday, 10 November, 2026, 9:00 - 11:00
Location: FEDERICO GARCÍA LORCA
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.

9:00 NSS-05-01

Time-of-Flight Neutron Imaging With a Segmented Organic Imager Cell (#2120)

W. Heriot1, D. Breitenmoser1, P. Marleu2, K. Vaigneur3, S. Clarke1, S. Pozzi1

1 University of Michigan, Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan, United States of America
2 Sandia National Laboratories, Livermore, California, United States of America
3 Oakridge National Laboratories, Oakridge, Tennessee, United States of America

This work was supported in part by the Consortium for Monitoring, Technology, and Verification under Department of Energy National Nuclear Security Administration, award number DE-NA0003920.

Abstract

Neutron imaging arrays are critical tools in nuclear non-proliferation, with applications in neutron source localization in wide-area source searches and cargo inspections. However, they commonly have large form factors due to needing large data acquisition systems, complicating deployment. A solution with simplified data acquisition is needed to make portable and field-deployable neutron imaging arrays. Organic scintillator-based neutron imaging arrays typically require pulse shape discrimination (PSD) to differentiate between neutron and gamma-ray events. This method requires full waveform data acquisition, which results in a high data throughput, and utilizes expensive analog-to-digital converters. In order to alleviate the need for full waveform acquisition, this work seeks to develop a system that instead leverages time-of-flight particle discrimination. To discriminate neutrons from gamma events using time-of-flight particle discrimination, a Segmented Organic Neutron Imager Cell, SONIC, has been constructed of 64 5x0.6x0.6 cm3 bars of EJ200. 14 of the 16 tested bars show typical pulse-integral spectra for Cs-137. This work details the introductory characterization of this imager array and evaluates its validity for future work in achieving a field-deployable, handheld neutron scatter imager.

AcknowledgmentThe authors would like to acknowledge Keith Vaigneur and Paul Hausladen at Oakridge National Laboratory for supplying our team with our detector volume and Erik Brubaker at Sandia National Laboratories for their input throughout the design process. This work was funded in-part by the Consortium for Monitoring, Technology, and Verification under Department of Energy National Nuclear Security Administration, United States of America award number DE-NA0003920. Sandia National Laboratories is a multimission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell International Inc., for the U.S. Department of Energy’s National Nuclear Security Administration under contract DE-NA0003525. SAND2026- 20469A
Keywords: neutron imaging, particle discrimination, nuclear non-proliferation, organic plastic scintillators, time-of-flight
9:15 NSS-05-02

Development of an omnidirectional neutron imager with fractal geometry (#1531)

N. Matsubayashi1, T. Torii2, M. Sasaki3, S. Kurosawa4

1 Tokyo University of Agriculture and Technology, Tokyo, Japan
2 Fukushima University, Fukushima, Japan
3 Japan Atomic Energy Agency, Minamisoma, Japan
4 Nagoya University, Nagoya, Japan

Abstract

In areas where radiation sources are diffused three-dimensionally, it is important to develop a compact imaging sensor that can detect radiation distributions in the 4π direction. A radiation imager that detects the distribution of radiation sources with a fractal Sierpinski tetrahedron shape was developed before. The imager has 16 sensors arranged in a Sierpinski tetrahedron shape, with the space between the sensors filled with a shielding material. We have been developing a neutron imager to measure radiation distribution within the site of the Fukushima Daiichi Nuclear Power Plant (FDNPP) and in the environment contaminated by the FDNPP accident. The reactor buildings contain large amounts of radiation sources. Since the nuclear fuel and debris contained in the reactor pressure vessel (RPV) will be removed in the future, it is extremely important to identify neutron sources originating from nuclear fuel in high dose rate areas for criticality management and radiation protection of workers. Therefore, we developed a compact omnidirectional neutron imager to locate neutron sources in the reactor building. This sensor consists of thin triangular scintillators (6LiF/ZnS:Ag) for neutron detection attached to a tetrahedral acrylic surface and arranged in a Sierpinski tetrahedron shape, with B4C mixed with resin for neutron shielding filled between the sensors. In this presentation, we report the results of performance evaluations of the imager using a neutron source and research reactor.

AcknowledgmentIn making the detector, we got help from N. Miyazaki and Y. Furuta at Clear Pulse Co., Ltd., and T. Sugita at SSL Inc. for response analysis. In addition, this research was conducted using funds from the JAEA/CLADS project (problem-solving program for decommissioning research, FY2024).
References
[1] T. Torii, M. Sasaki, and Y. Sanada, “Development of an omnidirectional detector for beta and gamma-ray imaging with fractal geometry,” in Proc. IEEE NSS/MIC/RTSD, 2023
[2] M. Sasaki, Y. Abe, Y. Sanada, and T. Torii, “Evaluation of the distribution accuracy of radioactivity from a gamma-ray source using an omnidirectional detector for radiation imaging with fractal geometry,” Nucl. Instrum. Methods Phys. Res., Sect. A, vol. 1072, p. 170207, Mar. 2025.
[3] T. Torii, M. Sasaki, Y. Sanada, N. Matsubayashi and S. Kurosawa, “Development of an omnidirectional detector for neutron imaging with fractal geometry” 2025 IEEE NSS MIC RTSD, N-16-150, November, 2025.
[4] T. Sato et al. Features of Particle and Heavy Ion Transport code System, J. Nucle. Sci. and Tech., 55:6  (2018), 684.
Keywords: Neutron Imaging, Omnidirectional Detector, Sierpinski Tetrahedron, Fractal Geometry
9:30 NSS-05-03

Neutron Spectroscopy Using a Spatially Resolved He-3 Slab Detector (#2047)

M. L. Lockhart1, J. P. Hayward1, A. Youmans2, P. Kerr2

1 University of Tennessee, Department of Nuclear Engineering, Knoxville, Tennessee, United States of America
2 Lawrence Livermore National Laboraatory, Livermore, California, United States of America

Abstract

This work presents a He-3 based slab detector for neutron spectroscopy that leverages spatially resolved detector response to infer incident neutron energy. In moderated detector systems, neutron energy information is typically degraded prior to detection, complicating spectrum unfolding. The proposed detector addresses this limitation through channel-by-channel list-mode acquisition, enabling analysis of spatial response variations correlated with neutron energy. Additional moderating and absorbing configurations are investigated to improve spectral sensitivity. A model of the detector is developed using Monte Carlo simulation and benchmarked against experimental measurements with monoenergetic neutron sources. This model will be used to generate energy-dependent response functions for use in spectral unfolding. Results indicate that combining spatial response information with multiple detector configurations will improve the conditioning of the neutron spectrum unfolding problem and enhance reconstruction accuracy. This approach provides a pathway toward information-optimized neutron spectrometry for nuclear security and safeguards applications.

Acknowledgment

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

This material is based upon work supported by the Department of Energy National Nuclear Security Administration through Defense Nuclear Nonproliferation's Enabling Capabilities in Technology Consortium under Award Number DE-NA0004197.

Keywords: neutron spectroscopy, he-3 detector, detector response function, model validation, nondestructive assay
9:45 NSS-05-04

Residual Interpulse 14-MeV Neutron Emission in Active Interrogation with Neutron Generators (#2076)

V. Fondement1, I. Jovanovic2

1 University Of Michigan, Nuclear Engineering & Radiological Sciences, Ann Arbor, Michigan, United States of America
2 University of California, Berkeley, Nuclear Engineering, Berkeley, California, United States of America

Abstract

We report residual 14 MeV neutron emission between pulses of a Thermo Fisher Scientific P 211 DT neutron generator operated at 100 Hz with a 0.1% duty cycle. Using a liquid organic scintillator with pulse-shape discrimination, we detect a significant population of neutron events with light output consistent with DT neutrons. The interpulse time structure follows a two-component exponential decay with time constants of 0.8 ms and 4.7 ms, inconsistent with 17N β-delayed neutron emission. The interpulse yield represents 0.1% of the total emission (~10-6 of instantaneous pulse intensity). These results demonstrate that the assumption of zero interpulse emission can be violated even when both the ion source and the high voltage are nominally pulsed, with direct implications for low-SNR delayed-signature measurements.

AcknowledgmentThis work has been supported in part by the US Department of Homeland Security, Countering Weapons of Mass Destruction (CWMD) Office, Academic Research Initiative
cooperative agreement number 21CWDARI00040-01-0.
References
[1] Thermo Scientific P 211 Neutron Generator: Product Specifications. URL: https://www.thermofisher.com/order/catalog/product/1512521C
[2] T. A. Laplace et al., “Comparative scintillation performance of EJ-309, EJ-276, and a novel organic glass,” J. Inst., vol. 15, no. 11, pp. P11020–P11020, Nov. 2020, doi: 10.1088/1748-0221/15/11/P11020.
[3] CAEN, DT5730S User Manual Rev. 8, CAEN (2023) URL: https://www.caen.it/products/dt5730
[4] C. Graham, et al., “Improved contraband detection using an experimentally optimized neutron active interrogation pulse structure,” NIM A, vol. 1083, p. 171157, Mar. 2026, doi: 10.1016/j.nima.2025.171157.
[5]  V. Fondement et al., "Electronics and 3He Counter Acquisition Tests During the Pulses of a D-T Neutron Generator," 2022 IEEE NSS/MIC, Italy, 2022, pp. 1-6, doi: 10.1109/NSS/MIC44845.2022.10399200.
[6] V. Fondement et al., “Development of a neutron probe to perform a combined measurement of uranium concentration and hydrogen porosity for mining applications,” NIM A, vol. 1059, p. 168888, Feb. 2024, doi: 10.1016/j.nima.2023.168888.
Keywords: DT neutron generator, EJ309, pulse-shape discrimination, interpulse emission, neutron background
10:00 NSS-05-05

Neutron Flux Monitor (NFM): A Micromegas-Based Beam Monitor for the European Spallation Source (#2999)

I. Katsioulas1, A. Altingün1, A. Gardikiotis3, M. Kebbiri2, C. Lampoudis3, B. A. Moreno2, T. Papaevangelou2, E. Samouilidis3, 1, O. Sidiropoulou1

1 European Spallation Source, Detector Group, Lund, Sweden
2 Université Paris-Saclay, IRFU, CEA, Gif-sur-Yvette, France
3 Aristotle University of Thessaloniki, Physics Department, Thessaloniki, Greece

Abstract

The European Spallation Source (ESS) requires advanced neutron-beam monitors capable of stable operation under high-rate conditions while maintaining low beam attenuation. To address these requirements, a Micromegas-based Neutron Flux Monitor (NFM) has been developed by the ESS Detector Group in collaboration with DEDIP (IRFU) and CEA Saclay. The detector employs a novel bulk Micromegas implementation directly on AlMg3 alloy substrates, minimizing the use of hydrogen-rich materials and therefore reducing neutron attenuation and moderation effects along the beamline. Initial detector characterization using X-ray sources demonstrated good gain uniformity, stable high-gain operation, and good energy resolution. Subsequent neutron measurements performed with different gas mixtures and front-end electronics confirmed stable operation under representative ESS-like conditions. Measurements performed at the EMMA beamline at ISIS investigated detector performance at high neutron rates and provided important input for the optimisation of the final NFM readout architecture for future ESS deployment.

AcknowledgmentWe would like to thank Dr Jochen Stahn (PSI) and Dr Davide Raspino for providing beam time and their support during the measurements at the AMOR and MORPHEUS instruments at the Paul Scherrer Institute (CH) and the EMMA beamline in the ISIS facility at the Rutherford Appleton Laboratory (UK).
References
[1] Andersen, KH, Argyriou, DN, Jackson, AJ, Houston, J, Henry, PF, Deen, PP, et al. 2020, ‘The instrument suite of the European Spallation Source’, Nuclear Instruments and Methods in Physics Research Section A, vol. 957, Art. no. 163402, Amsterdam: Elsevier.
[2] Garoby, R, et al. 2018, ‘The European Spallation Source Design’, Physica Scripta, vol. 93, Art. no. 014001, Bristol: IOP Publishing.
[3] Giomataris, I, Rebourgeard, Ph, Robert, JP, Charpak, G 1996, ‘MICROMEGAS: A high-granularity position-sensitive gaseous detector for high particle-flux environments’, Nuclear Instruments and Methods in Physics Research Section A, vol. 376, pp. 29–35, Amsterdam: Elsevier.
[4] Giomataris, I, et al. 2006, ‘Micromegas in a bulk’, Nuclear Instruments and Methods in Physics Research Section A, vol. 560, pp. 405–408, Amsterdam: Elsevier.
[5] Segui, L, et al. 2023, ‘Detector design and performance tests of the ESS-neutron Beam Loss Monitor detectors’, Journal of Instrumentation, vol. 18, P01013, Bristol: IOP Publishing.
Keywords: Beam diagnostics, European Spallation Source, MPGD, MICROMEGAS, neutron detection
10:15 NSS-05-06

Development of a Handheld Fast Neutron Spectrometer Using Deuterated Scintillators and Spectrum Unfolding (#3014)

A. A. Alcaide1, T. C. Borgwardt2, C. Brune3, L. Fabris4, M. Febbraro1, J. J. Manfredi1, T. Massey3, J. Matta4, D. Matthews4, C. Parker3, D. Rutstrom1, N. Zaitseva5

1 Air Force Institute of Technology, Engineering Physics, Dayton, Ohio, United States of America
2 Los Alamos National Laboratory, Los Alamos, New Mexico, United States of America
3 Ohio University, Athens, Ohio, United States of America
4 Oak Ridge National Laboratory, Oak Ridge, Tennessee, United States of America
5 Lawrence Livermore National Laboratory, Livermore, California, United States of America

Abstract

Fast neutron spectroscopy has the potential to offer critical information for safeguards, nonproliferation, and field radiation detection applications where neutron energy distributions provide source characteristics inaccessible through conventional moderated neutron counters. Traditional portable neutron detection systems primarily rely on moderation and thermal neutron counting, which remove incident neutron energy information and limit spectroscopic capability. In this work, the nSpec system is developed as a handheld fast neutron spectrometer utilizing four novel deuterated polystyrene (dPS) scintillator detectors coupled to photomultiplier tubes in a compact, field-deployable architecture. By leveraging neutron--deuteron elastic scattering interactions, the system preserves energy-dependent neutron response while maintaining portability suitable for operational environments. Pulse shape discrimination is employed to separate neutron and gamma interactions, while detector response matrices (DRMs) derived from high-flux neutron characterization are used to reconstruct incident neutron spectra through maximum likelihood expectation maximization (MLEM) unfolding.  Prototype evaluations using representative neutron sources, including AmBe and Cf-252, demonstrate successful spectral unfolding and source discrimination capability. Ongoing development focuses on onboard electronics integration, firmware implementation, shielding optimization, and validation against simulated and experimental DRMs.  These results establish nSpec as a promising pathway toward practical handheld fast neutron spectroscopy for safeguards and field applications.

Keywords: deuterated polystyrene, spectrum unfolding, MLEM, neutron spectrometry
10:30 NSS-05-07

Innovative neutron counting for high-rate double-differential cross-section in fragmentation events. (#2947)

I. B. Rivas Ortiz1, E. M. Data2, V. Ferrero2, E. Fiorina1, S. Giordanengo1, F. Mas Milian1, 3, A. Mereghetti4, D. M. Montalvan Olivares1, 2, F. Pennazio1, M. Pullia4, S. Ranjbar2, R. Sacchi1, 2, A. Vignati1, 2, P. Cerello1

1 Instituto Nazionale di Fisica Nucleare, Sezione di Torino, Torino, Italy
2 Universita degli Studi di Torino, Torino, Italy
3 Universidade Estadual de Santa Cruz, Bahia, Brazil
4 Fondazione Centro Nazionale di Adronterapia Oncologica, Pavia, Italy

Abstract

Neutron production cross-sections are critical for dose assessment in particle therapy and space radiation protection, yet double-differential data remain scarce. We present a consistent framework for Time-Of-Flight (TOF)-based measurement built around the use of Low Gain Avalanche Detectors (LGADs) segmented into strips on the primary beam, enabling large statistical samples and precise time measurement, and a secondary neutron detector split into layers to accurately reconstruct neutron production as a function of kinetic energy and angular direction. A preliminary beam test was conducted to validate the methodology. The setup comprises an 8-strip beam monitor for primary particle tagging, a LaBr3(Ce) scintillator with Silicon Photomultiplier (SiPM) readout as secondary radiation detector, and a plastic veto for charged-particle rejection. Neutron kinetic energy is reconstructed via relativistic TOF analysis from approximately 16 MeV to several hundred MeV. A novel Beer-Lambert fitting approach enables efficiency-independent neutron flux estimation from the attenuation pattern along the detection depth, overcoming systematic uncertainties of conventional scaling methods. Monte Carlo (MC) simulations validate both TOF distributions and flux reconstruction at the few-percent level, with computed cross-sections in good agreement with MC truth values. Combined with a rotary-translation stage enabling systematic angular scanning for full double-differential cross-section mapping, the proposed approach provides a robust and scalable framework for neutron production measurements in fragmentation events, with direct application to out-of-field dose characterization in particle therapy and astronaut radiation exposure assessment.

Keywords: Beam-target fragmentation, Beer-Lambert flux reconstruction, LGAD segmented strip sensor, Monte Carlo validation, Neutron production double-differential cross-sections
10:45 NSS-05-08

First 3D-PDC Experimental Measurements of Fast Neutrons and PSD Performance (#1598)

A. Steinhebel1, S. Charlebois2, L. Fabris1, P. Hausladen1, G. Lessard2, C. Pepin2, J.-F. Pratte2, T. Rossignol2, N. Roy2, F. Vachon2

1 Oak Ridge National Laboratory, Bldg 3500, MS 6010, Oak Ridge, Tennessee, United States of America
2 Universite de Sherbrooke, Interdisciplinary Institute for Technological Innovation and Department of Electrical and Computer Engineering, Sherbrooke, Québec, Canada

Abstract

Novel Photon-to-Digital Converters (3D-PDCs) are arrays of Single Photon Avalanche Diodes (SPADs) vertically-integrated with low power CMOS digital readouts, offering high timing precision ($<200$ ps FWHM) and individual-pixel control.  As single-photon counters, 3D-PDCs can be coupled to scintillators for radiation detection.  This talk will discuss the first 3D-PDC measurements of fast neutrons.  The 3D-PDCs are used to read out an organic plastic scintillator with Pulse Shape Discrimination (PSD) capabilities, making incident neutrons and gamma rays discernible by the pulse shape of the induced scintillator signal.  First PSD results will be shown and compared to standard commercial silicon photomultipliers.

AcknowledgmentThe present work was supported in part by the United States Department of Energy, Office of Defense Nuclear Nonproliferation Research and Development in the National Nuclear Security Administration and by the United States Department of Energy, Office of High Energy Physics.
References
[1] A. Pietropaolo, et al., “Neutron detection techniques from μeV to GeV,” Phys. Reports, vol. 875, pp. 1-65, Sept, 2020, 10.1016/j.physrep.2020.06.003.
[2] M. L. Roush, M. A. Wilson, and W. F. Hornyak, “Pulse shape discrimination,” Nucl. Instrum. Methods, vol. 31, pp. 112-124, June, 1964.
[3] J.-F. Pratte, et al., “3D Photon-To-Digital Converter for radiation instrumentation: Motivation and future works,” Sensors, vol. 21, no. 2, pp. 598, Jan, 2021, 10.3390/s21020598.
[4] T. Rossignol, et al., “A 3D photon-to-digital converter readout for low-power and large-area applications,” JINST, vol. 19, Sept, 2024, 10.1088/1748-0221/19/09/P09017.
[5] C.M. Pepin, et al.. (2025, Nov.). Performance of 3D Photon-to-Digital Converters. Presented at 2025 IEEE NSS MIC RTSD. [In-person]. Available: https://inspirehep.net/literature/3102109. Accessed on: May 06, 2026.
Keywords: CMOS, neutron detectors, Photon-to-Digital Converter, radiation detection, Single Photon Avalanche Diode


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