Reference based simulation study of detector comparison for BNCT-SPECT imaging

Moo-Sub Kim; Han-Back Shin; Min-Geon Choi; Hajime Monzen; Jae Goo Shim; Tae Suk Suh; Do-Kun Yoon

Nuclear Engineering and Technology (Jan 2020)

Reference based simulation study of detector comparison for BNCT-SPECT imaging

Moo-Sub Kim,
Han-Back Shin,
Min-Geon Choi,
Hajime Monzen,
Jae Goo Shim,
Tae Suk Suh,
Do-Kun Yoon

Affiliations

Moo-Sub Kim: Department of Biomedical Engineering and Research Institute of Biomedical Engineering, College of Medicine, Catholic University of Korea, Seoul, 06591, South Korea
Han-Back Shin: Department of Radiation Oncology, Yonsei Cancer Center, Yonsei University, College of Medicine, Seoul, 032722, South Korea
Min-Geon Choi: Department of Biomedical Engineering and Research Institute of Biomedical Engineering, College of Medicine, Catholic University of Korea, Seoul, 06591, South Korea
Hajime Monzen: Department of Medical Physics, Graduate School of Medical Science, Kindai University, 377-2, Ohno-Higashi, Osakasayama, Osaka, 589-8511, Japan
Jae Goo Shim: Department of Radiologic Technology Daegu Health College, Daegu, 41453, South Korea
Tae Suk Suh: Department of Biomedical Engineering and Research Institute of Biomedical Engineering, College of Medicine, Catholic University of Korea, Seoul, 06591, South Korea; Corresponding author.
Do-Kun Yoon: Department of Biomedical Engineering and Research Institute of Biomedical Engineering, College of Medicine, Catholic University of Korea, Seoul, 06591, South Korea; Corresponding author.

Journal volume & issue: Vol. 52, no. 1
pp. 155 – 163

Abstract

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To investigate the optimal detector material for prompt gamma imaging during boron neutron capture therapy, in this study, we evaluated the characteristic regarding radiation reaction of available detector materials using a Monte Carlo simulation. Sixteen detector materials used for radiation detection were investigated to assess their advantages and drawbacks. The estimations used previous experimental data to build the simulation codes. The energy resolution and detection efficiency of each material was investigated, and prompt gamma images during BNCT simulation were acquired using only the detectors that showed good performance in our preliminary data. From the simulation, we could evaluate the majority of detector materials in BNCT and also could acquire a prompt gamma image using the six high ranked-detector materials and lutetium yttrium oxyorthosilicate. We provide a strategy to select an optimal detector material for the prompt gamma imaging during BNCT with three conclusions. Keywords: Boron neutron capture therapy (BNCT), Prompt gamma, Detector materials, Monte Carlo simulation

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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