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Related Experiment Video

Updated: Oct 29, 2025

Neutron Radiography and Computed Tomography of Biological Systems at the Oak Ridge National Laboratory's High Flux Isotope Reactor

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TENIS - ThErmal Neutron Imaging System for use in BNCT.

H Yazdandoust¹, N Ghal-Eh², M M Firoozabadi¹

¹Department of Physics, Faculty of Sciences, University of Birjand, P.O. Box 97175-615, Birjand, Iran.

Applied Radiation and Isotopes : Including Data, Instrumentation and Methods for Use in Agriculture, Industry and Medicine

|July 9, 2021

Summary

This study enhanced a thermal neutron flux measurement tool using FLUKA simulations. Optimizing system geometry and image reconstruction significantly improved the neutron flux profile.

Keywords:

Boron neutron capture therapy (BNCT)Collimator Cross-talk FLUKA MCNPX Plastic scintillator Thermal neutrons

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Area of Science:

Nuclear instrumentation
Monte Carlo simulations
Neutron detection

Background:

A previous study designed and simulated a thermal neutron flux measurement tool using MCNPX.
The tool aimed to map thermal neutron flux by detecting 2.22 MeV gamma rays from hydrogen capture reactions.
The original design lacked detailed light transport modeling and cross-talk analysis.

Purpose of the Study:

To upgrade a thermal neutron flux measurement system by incorporating light transport modeling in plastic scintillators.
To analyze and mitigate the cross-talk phenomenon between scintillator elements.
To optimize system geometry and develop a novel approach for thermal neutron image reconstruction.

Main Methods:

Utilized the Monte Carlo FLUKA code with its scintillation light transport capabilities.
Modeled light transport within plastic scintillators to accurately simulate detector response.
Performed geometric optimization and developed a new image reconstruction algorithm.

Main Results:

The inclusion of light transport modeling provided a more accurate simulation of scintillator response.
Analysis of the cross-talk phenomenon identified its impact on measurement accuracy.
Optimization of system geometry and the new reconstruction approach significantly improved the longitudinal profile of thermal neutron flux.

Conclusions:

FLUKA simulations with light transport capabilities offer a powerful tool for enhancing neutron detector design.
System geometry optimization and advanced image reconstruction are crucial for accurate thermal neutron flux mapping.
The upgraded system shows improved performance in characterizing neutron flux distributions.