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http://dx.doi.org/10.1016/j.net.2020.12.006

Optimization of target, moderator, and collimator in the accelerator-based boron neutron capture therapy system: A Monte Carlo study  

Cheon, Bo-Wi (Department of Radiation Convergence Engineering, Yonsei University)
Yoo, Dohyeon (Department of Radiation Oncology, Massachusetts General Hospital and Harvard Medical School)
Park, Hyojun (Department of Radiation Convergence Engineering, Yonsei University)
Lee, Hyun Cheol (Department of Radiation Convergence Engineering, Yonsei University)
Shin, Wook-Geun (Department of Radiation Convergence Engineering, Yonsei University)
Choi, Hyun Joon (Department of Radiation Oncology, Wonju Severance Christian Hospital)
Hong, Bong Hwan (Korea Institute of Radiological and Medical Science)
Chung, Heejun (The Korea Institute of Nuclear Nonproliferation and Control)
Min, Chul Hee (Department of Radiation Convergence Engineering, Yonsei University)
Publication Information
Nuclear Engineering and Technology / v.53, no.6, 2021 , pp. 1970-1978 More about this Journal
Abstract
The aim of this study was to optimize the target, moderator, and collimator (TMC) in a neutron beam generator for the accelerator-based BNCT (A-BNCT) system. The optimization employed the Monte Carlo Neutron and Photon (MCNP) simulation. The optimal geometry for the target was decided as the one with the highest neutron flux among nominates, which were called as angled, rib, and tube in this study. The moderator was optimized in terms of consisting material to produce appropriate neutron energy distribution for the treatment. The optimization of the collimator, which wrapped around the target, was carried out by deciding the material to effectively prevent the leakage radiations. As results, characteristic of the neutron beam from the optimized TMC was compared to the recommendation by the International Atomic Energy Agent (IAEA). The tube type target showed the highest neutron flux among nominates. The optimal material for the moderator and collimator were combination of Fluental (Al203+AlF3) with 60Ni filter and lead, respectively. The optimized TMC satisfied the IAEA recommendations such as the minimum production rate of epithermal neutrons from thermal neutrons: that was 2.5 times higher. The results can be used as source terms for shielding designs of treatment rooms.
Keywords
Boron Neutron Capture Therapy; TMC; Monte Carlo; MCNP; Optimization;
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  • Reference
1 J. Mokhtari, Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux, Prog. Nucl. Energy 95 (2017) 70-77.   DOI
2 A. Miller, Californium-252 as a Neutron Source for BNCT, 2012, pp. 69-74. Neutron Capture Therapy, Springer.
3 E. Bavarnegin, Y. Kasesaz, F.M. Wagner, Neutron beams implemented at nuclear research reactors for BNCT, J. Instrum. 12 (5) (2017), P05005, https://doi.org/10.1016/j.ijrobp.2007.02.002. URL.   DOI
4 J.A. Coderre, G.M. Morris, The Radiation Biology of Boron Neutron Capture Therapy, 1999, https://doi.org/10.2307/3579742. URL.
5 H. Koivunoro, E. Hippelainen, I. Auterinen, L. Kankaanranta, M. Kulvik, J. Laakso, T. Seppala, S. Savolainen, H. Joensuu, Biokinetic analysis of tis- sue boron (10B) concentrations of glioma patients treated with BNCT in Finland, Appl. Radiat. Isot. 106 (2015) 189-194, https://doi.org/10.1016/j.apradiso.2015.08.014.   DOI
6 T. Watanabe, Comparison of the pharmacokinetics between l-BPA and l-FBPA using the same adminis- tration dose and protocol: a validation study for the theranostic approach using [18 F]-l-FBPA positron emission tomography in boron neutron capture ther- apy, BMC Canc. 16 (2016), 859.   DOI
7 M. Monshizadeh, MCNP design of thermal and ep- ithermal neutron beam for BNCT at the Isfahan MNSR, Prog. Nucl. Energy 83 (2015) 427-432.   DOI
8 J. Esposito, et al., Be target development for the accelerator-based SPES-BNCT facility at INFN Legnaro, Appl. Radiat. Isot. 67 (2009) 7-8. S270-S273.   DOI
9 A. Kreiner, Juan, Present status of accelerator-based BNCT, Rep. Practical Oncol. Radiother. 21 (2016) 95-101.   DOI
10 J.-K. Kim, K.-O. Kim, Current research on accelerator-based boron neutron capture therapy in Korea, Nuclear Engi- neering and Technology 41 (4) (2009) 531-544, https://doi.org/10.5516/net.2009.41.4.531. URL.   DOI
11 H, et al., Characteristics comparison between a cyclotron-based neutron source and KUR-HWNIF for boron neutron capture therapy, Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. Atoms 267 (11) (2009), 1970-1977, https://doi.org/10.1016/j.nima.2004.05.084. URL.   DOI
12 M. Han, Cheol, TET2MCNP: A conversion program to implement tetrahedralmesh models in MCNP, Journal of Radiation Protection and Research 41 (2016) 389-394.   DOI
13 H. Kumada, Development of beryllium-based neu- tron target system with three-layer structure for accelerator-based neutron source for boron neutron capture therapy, Appl. Radiat. Isot. 106 (2015) 78-83.   DOI
14 E. Bavarnegin, Y. Kasesaz, F.M. Wagner, Neutron beams implemented at nuclear research reactors for BNCT, J. Instrum. 12 (5) (2017), P05005, https://doi.org/10.1088/1748-0221/12/05/p05005. URL.   DOI
15 Coderre, J. "IAEA-TECDOC-1223." (2001)..
16 J.C. Yanch, X.L. Zhou, G.L. Brownell, A Monte Carlo investigation of the dosimetric properties of monoenergetic neutron beams for neutron capture therapy, Radiat. Res. 126 (1) (1991) 1-20.   DOI
17 Martz, Roger Lee, The MCNP6 Book on Unstructured Mesh Geometry: User's Guide for MCNP 6.2. 1. No. LA-UR-18-27630, Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2018.
18 H. Kumada, Project for the development of the linac based NCT facility in University of Tsukuba, Appl. Radiat. Isot. 88 (2014) 211-215.   DOI
19 H. Tanaka, Experimental verification of beam char- acteristics for cyclotronbased epithermal neutron source (C-BENS), Appl. Radiat. Isot. 69 (2011) 1642-1645.   DOI