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Torres-Sánchez P, Porras I, Ramos-Chernenko N, Arias de Saavedra F, Praena J. Optimized beam shaping assembly for a 2.1-MeV proton-accelerator-based neutron source for boron neutron capture therapy. Sci Rep 2021; 11:7576. [PMID: 33828211 DOI: 10.1038/s41598-021-87305-9] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 11/02/2020] [Accepted: 03/25/2021] [Indexed: 02/06/2023] Open
Abstract
Boron Neutron Capture Therapy (BNCT) is facing a new era where different projects based on accelerators instead of reactors are under development. The new facilities can be placed at hospitals and will increase the number of clinical trials. The therapeutic effect of BNCT can be improved if a optimized epithermal neutron spectrum is obtained, for which the beam shape assembly is a key ingredient. In this paper we propose an optimal beam shaping assembly suited for an affordable low energy accelerator. The beam obtained with the device proposed accomplishes all the IAEA recommendations for proton energies between 2.0 and 2.1 MeV. In addition, there is an overall improvement of the figures of merit with respect to BNCT facilities and previous proposals of new accelerator-based facilities.
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Kellert M, Friedrichs JSJ, Ullrich NA, Feinhals A, Tepper J, Lönnecke P, Hey-Hawkins E. Modular Synthetic Approach to Carboranyl‒Biomolecules Conjugates. Molecules 2021; 26:2057. [PMID: 33916755 PMCID: PMC8038343 DOI: 10.3390/molecules26072057] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [MESH Headings] [Grants] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/15/2021] [Revised: 03/27/2021] [Accepted: 03/30/2021] [Indexed: 12/16/2022] Open
Abstract
The development of novel, tumor-selective and boron-rich compounds as potential agents for use in boron neutron capture therapy (BNCT) represents a very important field in cancer treatment by radiation therapy. Here, we report the design and synthesis of two promising compounds that combine meta-carborane, a water-soluble monosaccharide and a linking unit, namely glycine or ethylenediamine, for facile coupling with various tumor-selective biomolecules bearing a free amino or carboxylic acid group. In this work, coupling experiments with two selected biomolecules, a coumarin derivative and folic acid, were included. The task of every component in this approach was carefully chosen: the carborane moiety supplies ten boron atoms, which is a tenfold increase in boron content compared to the l-boronophenylalanine (l-BPA) presently used in BNCT; the sugar moiety compensates for the hydrophobic character of the carborane; the linking unit, depending on the chosen biomolecule, acts as the connection between the tumor-selective component and the boron-rich moiety; and the respective tumor-selective biomolecule provides the necessary selectivity. This approach makes it possible to develop a modular and feasible strategy for the synthesis of readily obtainable boron-rich agents with optimized properties for potential applications in BNCT.
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Affiliation(s)
| | | | | | | | | | | | - Evamarie Hey-Hawkins
- Institute of Inorganic Chemistry, Faculty of Chemistry and Mineralogy, Leipzig University, Johannisallee 29, 04103 Leipzig, Germany; (M.K.); (J.-S.J.F.); (N.A.U.); (A.F.); (J.T.); (P.L.)
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Torres-sánchez P, Porras I, de Saavedra FA, Sabariego M, Praena J. On the upper limit for the energy of epithermal neutrons for Boron Neutron Capture Therapy. Radiat Phys Chem Oxf Engl 1993 2019; 156:240-4. [DOI: 10.1016/j.radphyschem.2018.11.015] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Hiraga F, Ooie T. Synergistic effects of fast-neutron dose per epithermal neutron and 10B concentration on relative-biological-effectiveness dose for accelerator-based boron neutron capture therapy. Appl Radiat Isot 2019; 144:1-4. [PMID: 30465991 DOI: 10.1016/j.apradiso.2018.11.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 06/15/2017] [Revised: 02/06/2018] [Accepted: 11/10/2018] [Indexed: 11/25/2022]
Abstract
The efficacy of accelerator-based boron neutron capture therapy was examined through relative-biological-effectiveness dose calculations with the fast-neutron dose per epithermal neutron (FNR) and the 10B concentration as parameters. In the case of a tumor 10B concentration of 65 ppm, the treatment efficacy depended more strongly on the FNR when the normal-tissue 10B concentration was 0.65 ppm, which would be brought about by the administration of an advanced chemical compound, than when the 10B concentration was 18 ppm, which is attainable by the use of boronophenylalanine.
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Affiliation(s)
- F Hiraga
- Faculty of Engineering, Hokkaido University, Sapporo, Hokkaido 060-8628, Japan.
| | - T Ooie
- Graduate school of Engineering, Hokkaido University, Sapporo, Hokkaido 060-8628, Japan.
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Ahmadi Ganjeh Z, Eslami-kalantari M. A study of the simulation of the influence on formed neutron spectrum when Li target was covered with polyimide protective film. J Radioanal Nucl Chem 2018; 318:1025-1031. [DOI: 10.1007/s10967-018-6161-1] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Sahoo GS, Sharma SD, Tripathy SP, Bandyopadhyay T. Design and dosimetric evaluation of beam shaping assembly for BNCT of compact D–T neutron generator by Monte Carlo simulation. Biomed Phys Eng Express 2017. [DOI: 10.1088/2057-1976/aa96e0] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/11/2022]
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Verbeke JM, Vujic JL, Leung KN. Neutron Beam Optimization for Boron Neutron Capture Therapy Using the D-D and D-T High-Energy Neutron Sources. NUCL TECHNOL 2017. [DOI: 10.13182/nt00-a3061] [Citation(s) in RCA: 31] [Impact Index Per Article: 4.4] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Jérôme M. Verbeke
- University of California, Berkeley Nuclear Engineering Department, Berkeley, California 94720 and Ernest Orlando Lawrence Berkeley National Laboratory 1 Cyclotron Road, Berkeley, California 94720
| | - Jasmina L. Vujic
- University of California, Berkeley Nuclear Engineering Department, Berkeley, California 94720
| | - Ka-Ngo Leung
- Ernest Orlando Lawrence Berkeley National Laboratory 1 Cyclotron Road, Berkeley, California 94720
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Darvish-Molla S, Prestwich WV, Byun SH. COMPREHENSIVE RADIATION DOSE MEASUREMENTS AND MONTE CARLO SIMULATION FOR THE 7Li(p,n) ACCELERATOR NEUTRON FIELD. Radiat Prot Dosimetry 2016; 171:421-430. [PMID: 26464524 DOI: 10.1093/rpd/ncv428] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/25/2015] [Revised: 08/13/2015] [Accepted: 09/11/2015] [Indexed: 06/05/2023]
Abstract
In order to investigate the radiation dose dependence on the incident proton energy, neutron and gamma-ray doses were measured using a tissue-equivalent proportional counter in the proton energy range of 1.95-2.50 MeV for the McMaster 7Li(p,n) neutron facility. Microdosimetric spectra were collected, and absorbed doses were determined at various positions inside the irradiation cavity, along the lateral axis and outside the shield to find out the spatial distributions of neutron and gamma-ray doses for each proton energy. In parallel with the absorbed dose measurements, MCNP Monte Carlo simulations were carried out and neutron fluence spectra were computed at various positions, which enabled determination of the neutron weighting factors. It was found that neutrons make a substantially dominant contribution to the total equivalent dose for most proton energies and positions. The effective dose for a human subject increased from 0.058 to 1.306 μSv μA-1 min-1 with the increase of proton energy from 1.95 to 2.5 MeV. It is expected that the reported data will be useful for 7Li(p,n) accelerator neutron users.
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Affiliation(s)
- S Darvish-Molla
- Department of Medical Physics and Applied Radiation Sciences, McMaster University, Hamilton, ON, Canada L8S 4K1
| | - W V Prestwich
- Department of Medical Physics and Applied Radiation Sciences, McMaster University, Hamilton, ON, Canada L8S 4K1
| | - S H Byun
- Department of Medical Physics and Applied Radiation Sciences, McMaster University, Hamilton, ON, Canada L8S 4K1
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Elshahat B, Naqvi A, Maalej N. Boron neutron capture therapy design calculation of a 3H(p,n) reaction based BSA for brain cancer setup. Int J Cancer Ther Oncol 2015. [DOI: 10.14319/ijcto.33.10] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/05/2022] Open
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Rasouli FS, Masoudi SF. A study on the optimum fast neutron flux for boron neutron capture therapy of deep-seated tumors. Appl Radiat Isot 2014; 96:45-51. [PMID: 25479433 DOI: 10.1016/j.apradiso.2014.11.016] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/09/2014] [Revised: 10/21/2014] [Accepted: 11/14/2014] [Indexed: 11/28/2022]
Abstract
High-energy neutrons, named fast neutrons which have a number of undesirable biological effects on tissue, are a challenging problem in beam designing for Boron Neutron Capture Therapy, BNCT. In spite of this fact, there is not a widely accepted criterion to guide the beam designer to determine the appropriate contribution of fast neutrons in the spectrum. Although a number of researchers have proposed a target value for the ratio of fast neutron flux to epithermal neutron flux, it can be shown that this criterion may not provide the optimum treatment condition. This simulation study deals with the determination of the optimum contribution of fast neutron flux in the beam for BNCT of deep-seated tumors. Since the dose due to these high-energy neutrons damages shallow tissues, delivered dose to skin is considered as a measure for determining the acceptability of the designed beam. To serve this purpose, various beam shaping assemblies that result in different contribution of fast neutron flux are designed. The performances of the neutron beams corresponding to such configurations are assessed in a simulated head phantom. It is shown that the previously used criterion, which suggests a limit value for the contribution of fast neutrons in beam, does not necessarily provide the optimum condition. Accordingly, it is important to specify other complementary limits considering the energy of fast neutrons. By analyzing various neutron spectra, two limits on fast neutron flux are proposed and their validity is investigated. The results show that considering these limits together with the widely accepted IAEA criteria makes it possible to have a more realistic assessment of sufficiency of the designed beam. Satisfying these criteria not only leads to reduction of delivered dose to skin, but also increases the advantage depth in tissue and delivered dose to tumor during the treatment time. The Monte Carlo Code, MCNP-X, is used to perform these simulations.
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Affiliation(s)
- Fatemeh S Rasouli
- Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416 Tehran, Iran.
| | - S Farhad Masoudi
- Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416 Tehran, Iran
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Inoue R, Hiraga F, Kiyanagi Y. Optimum design of a moderator system based on dose calculation for an accelerator driven Boron Neutron Capture Therapy. Appl Radiat Isot 2014; 88:225-8. [DOI: 10.1016/j.apradiso.2013.12.017] [Citation(s) in RCA: 16] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 12/14/2012] [Revised: 12/16/2013] [Accepted: 12/17/2013] [Indexed: 11/17/2022]
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Torabi F, Farhad Masoudi S, Rahmani F, Rasouli FS. BSA optimization and dosimetric assessment for an electron linac based BNCT of deep‐seated brain tumors. J Radioanal Nucl Chem 2014; 300:1167-74. [DOI: 10.1007/s10967-014-3087-0] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Tanaka K, Endo S, Yonai S, Baba M, Hoshi M. A TPD and AR based comparison of accelerator neutron irradiation fields between (7)Li and W targets for BNCT. Appl Radiat Isot 2013; 88:229-32. [PMID: 24359788 DOI: 10.1016/j.apradiso.2013.11.098] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/22/2013] [Revised: 11/22/2013] [Accepted: 11/23/2013] [Indexed: 11/28/2022]
Abstract
The characteristics of moderator assembly dimension was investigated for the usage of (7)Li(p,n) neutrons by 2.3-2.8MeV protons and W(p,n) neutrons by 50MeV protons. The indexes were the treatable protocol depth (TPD) and advantage depth (AD). Consequently, a configuration for W target with the Fe filter, Fluental moderator, Pb reflector showed the TPD of 5.8cm and AD of 9.3cm. Comparable indexes were found for the Li target in a geometry with the MgF2 moderator and Teflon reflector.
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Affiliation(s)
- Kenichi Tanaka
- Center of Medical Education, Sapporo Medical University, Sapporo, Japan.
| | - Satoru Endo
- Graduate School of Engineering, Hiroshima University, Higashi-Hiroshima, Japan
| | - Shunsuke Yonai
- Research Center for Charged Particle Therapy, National Institute of Radiological Sciences, Chiba, Japan
| | - Mamoru Baba
- Cyclotron Radioisotope Center, Tohoku University, Miyagi, Japan
| | - Masaharu Hoshi
- Research Institute for Radiation Biology and Medicine, Hiroshima University, Hiroshima 734-8553, Japan
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Rasouli FS, Masoudi SF. Design and optimization of a beam shaping assembly for BNCT based on D–T neutron generator and dose evaluation using a simulated head phantom. Appl Radiat Isot 2012; 70:2755-62. [DOI: 10.1016/j.apradiso.2012.08.008] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 06/11/2012] [Revised: 08/01/2012] [Accepted: 08/13/2012] [Indexed: 10/28/2022]
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16
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Matysiak W, Prestwich W, Byun S. Measurements of the neutron spectra from the 7Li(p,n) accelerator based neutron source: Position and angular dependences. Radiat Phys Chem Oxf Engl 1993 2012; 81:1673-82. [DOI: 10.1016/j.radphyschem.2012.06.003] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Rasouli FS, Farhad Masoudi S, Kasesaz Y. Design of a model for BSA to meet free beam parameters for BNCT based on multiplier system for D–T neutron source. ANN NUCL ENERGY 2012. [DOI: 10.1016/j.anucene.2011.08.025] [Citation(s) in RCA: 19] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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TAKATA T, TANAKA H, SAKURAI Y, MARUHASHI A. Increase in Irradiation Beam Intensity by Using a Hybrid Target System in Cyclotron-Based Neutron Capture Therapy. J NUCL SCI TECHNOL 2010. [DOI: 10.1080/18811248.2010.9720954] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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20
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Solberg T, DeMarco J, Chetty I, Mesa A, Cagnon C, Li A, Mather K, Medin P, Arellano A, Smathers J. A review of radiation dosimetry applications using the MCNP Monte Carlo code. RADIOCHIM ACTA 2009. [DOI: 10.1524/ract.2001.89.4-5.337] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
Abstract
The Monte Carlo code MCNP (Monte Carlo N-Particle) has a significant history dating to the early years of the Manhattan Project. More recently, MCNP has been used successfully to solve many problems in the field of medical physics. In radiotherapy applications MCNP has been used successfully to calculate the bremsstrahlung spectra from medical linear accelerators, for modeling the dose distributions around high dose rate brachytherapy sources, and for evaluating the dosimetric properties of new radioactive sources used in intravascular irradiation for prevention of restenosis following angioplasty. MCNP has also been used for radioimmunotherapy and boron neutron capture therapy applications. It has been used to predict fast neutron activation of shielding and biological materials. One area that holds tremendous clinical promise is that of radiotherapy treatment planning. In diagnostic applications, MCNP has been used to model X-ray computed tomography and positron emission tomography scanners, to compute the dose delivered from CT procedures, and to determine detector characteristics of nuclear medicine devices. MCNP has been used to determine particle fluxes around radiotherapy treatment devices and to perform shielding calculations in radiotherapy treatment rooms. This manuscript is intended to provide to the reader a comprehensive summary of medical physics applications of the MCNP code.
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Ceballos C, Esposito J. The BSA modeling for the accelerator-based BNCT facility at INFN LNL for treating shallow skin melanoma. Appl Radiat Isot 2009; 67:S274-7. [DOI: 10.1016/j.apradiso.2009.03.074] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Kim JK, Kim KO. CURRENT RESEARCH ON ACCELERATOR-BASED BORON NEUTRON CAPTURE THERAPY IN KOREA. Nuclear Engineering and Technology 2009. [DOI: 10.5516/net.2009.41.4.531] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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YONAI S, BABA M, NAKAMURA T, YOKOBORI H, TAHARA Y. Extension of Spallation-Based BNCT Concept to Medium- to High-Energy Accelerators. J NUCL SCI TECHNOL 2008. [DOI: 10.1080/18811248.2008.9711447] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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YONAI S, BABA M, ITOGA T, NAKAMURA T, YOKOBORI H, TAHARA Y. Influences of Neutron Source Spectrum and Thermal Neutron Scattering Law Data on the MCNPX Simulation of a Cyclotron-Based Neutron Field for Boron Neutron Capture Therapy. J NUCL SCI TECHNOL 2007. [DOI: 10.1080/18811248.2007.9711383] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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TAHARA Y, ODA Y, SHIRAKI T, TSUTSUI T, YOKOBORI H, YONAI S, BABA M, NAKAMURA T. Engineering Design of a Spallation Reaction-Based Neutron Generator for Boron Neutron Capture Therapy. J NUCL SCI TECHNOL 2006. [DOI: 10.1080/18811248.2006.9711063] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Kononov OE, Kononov VN, Bokhovko MV, Korobeynikov VV, Soloviev AN, Sysoev AS, Gulidov IA, Chu WT, Nigg DW. Optimization of an accelerator-based epithermal neutron source for neutron capture therapy. Appl Radiat Isot 2004; 61:1009-13. [PMID: 15308184 DOI: 10.1016/j.apradiso.2004.05.028] [Citation(s) in RCA: 34] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Abstract
A modeling investigation was performed to choose moderator material and size for creating optimal epithermal neutron beams for BNCT based on a proton accelerator and the (7)Li(p,n)(7)Be reaction as a neutrons source. An optimal configuration is suggested for the beam shaping assembly made from polytetrafluoroethylene and magnesium fluorine to be placed on high current IPPE proton accelerator KG-2.5. Results of calculation were experimentally tested and are in good agreement with measurements.
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Affiliation(s)
- O E Kononov
- State Scientific Center of Russian Federation, Institute for Physics and Power Engineering, Bondarenko sq. 1, 249033 Obninsk, Kaluga, Russia.
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Borisov NM, Kochetkov OA, Yatsenko VN, Franck D, de Carlan L, Tsèdish ST. Modern internal-irradiation dosimetry. ATOM ENERGY+ 2004; 97:713-9. [DOI: 10.1007/s10512-005-0007-y] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Kononov OE, Kononov VN, Solov’ev AN, Bokhovko MV. Accelerator-based source of epithermal neutrons for neutron capture therapy. ATOM ENERGY+ 2004; 97:626-31. [DOI: 10.1007/pl00021744] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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31
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Kononov OE, Kononov VN, Solov’ev AN, Bokhovko MV. Accelerator-based source of epithermal neutrons for neutron capture therapy. ATOM ENERGY+ 2004. [DOI: 10.1007/s10512-005-0043-7] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Abstract
This paper discusses the use of a General Electric PETtrace cyclotron as a neutron source for boron neutron capture therapy. In particular, the standard PETtrace (18)O target is considered. The resulting dose from the neutrons emitted from the target is evaluated using the Monte Carlo radiation transport code MCNP at different depths in a brain phantom. MCNP-simulated results are presented at 1, 2, 3, 4, 5, 6, 7, and 8 cm depth inside this brain phantom. Results showed that using a PETtrace cyclotron in the current configuration allows treating tumors at a depth of up to 4 cm with reasonable treatment times. Further increase of a beam current should significantly improve the treatment time and allow treating tumors at greater depths.
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Affiliation(s)
- A Bosko
- Department of Nuclear Engineering, Texas A&M University, College Station, USA.
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Yonai S, Aoki T, Nakamura T, Yashima H, Baba M, Yokobori H, Tahara Y. Feasibility study on epithermal neutron field for cyclotron-based boron neutron capture therapy. Med Phys 2003; 30:2021-30. [PMID: 12945968 DOI: 10.1118/1.1587431] [Citation(s) in RCA: 16] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
To realize the accelerator-based boron neutron capture therapy (BNCT) at the Cyclotron and Radioisotope Center of Tohoku University, the feasibility of a cyclotron-based BNCT was evaluated. This study focuses on optimizing the epithermal neutron field with an energy spectrum and intensity suitable for BNCT for various combinations of neutron-producing reactions and moderator materials. Neutrons emitted at 90 degrees from a thick (stopping-length) Ta target, bombarded by 50 MeV protons of 300 microA beam current, were selected as a neutron source, based on the measurement of angular distributions and neutron energy spectra. As assembly composed of iron, AlF3/Al/6LiF, and lead was chosen as moderators, based on the simulation trials using the MCNPX code. The depth dose distributions in a cylindrical phantom, calculated with the MCNPX code, showed that, within 1 h of therapeutic time, the best moderator assembly, which is 30-cm-thick iron, 39-cm-thick AlF3/Al/6LiF, and 1-cm-thick lead, provides an epithermal neutron flux of 0.7 x 10(9) [n cm(-2) s(-1)]. This results in a tumor dose of 20.9 Gy-eq at a depth of 8 cm in the phantom, which is 6.4 Gy-eq higher than that of the Brookhaven Medical Research Reactor at the equivalent condition of maximum normal tissue tolerance. The beam power of the cyclotron is 15 kW, which is much lower than other accelerator-based BNCT proposals.
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Affiliation(s)
- Shunsuke Yonai
- Department of Quantum Science and Energy Engineering, Tohoku University, Aoba Aramaki Aoba-ku, Sendai, Japan
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Abstract
This paper reviews the development of low-energy light ion accelerator-based neutron sources (ABNSs) for the treatment of brain tumors through an intact scalp and skull using boron neutron capture therapy (BNCT). A major advantage of an ABNS for BNCT over reactor-based neutron sources is the potential for siting within a hospital. Consequently, light-ion accelerators that are injectors to larger machines in high-energy physics facilities are not considered. An ABNS for BNCT is composed of: (1) the accelerator hardware for producing a high current charged particle beam, (2) an appropriate neutron-producing target and target heat removal system (HRS), and (3) a moderator/reflector assembly to render the flux energy spectrum of neutrons produced in the target suitable for patient irradiation. As a consequence of the efforts of researchers throughout the world, progress has been made on the design, manufacture, and testing of these three major components. Although an ABNS facility has not yet been built that has optimally assembled these three components, the feasibility of clinically useful ABNSs has been clearly established. Both electrostatic and radio frequency linear accelerators of reasonable cost (approximately 1.5 M dollars) appear to be capable of producing charged particle beams, with combinations of accelerated particle energy (a few MeV) and beam currents (approximately 10 mA) that are suitable for a hospital-based ABNS for BNCT. The specific accelerator performance requirements depend upon the charged particle reaction by which neutrons are produced in the target and the clinical requirements for neutron field quality and intensity. The accelerator performance requirements are more demanding for beryllium than for lithium as a target. However, beryllium targets are more easily cooled. The accelerator performance requirements are also more demanding for greater neutron field quality and intensity. Target HRSs that are based on submerged-jet impingement and the use of microchannels have emerged as viable target cooling options. Neutron fields for reactor-based neutron sources provide an obvious basis of comparison for ABNS field quality. This paper compares Monte Carlo calculations of neutron field quality for an ABNS and an idealized standard reactor neutron field (ISRNF). The comparison shows that with lithium as a target, an ABNS can create a neutron field with a field quality that is significantly better (by a factor of approximately 1.2, as judged by the relative biological effectiveness (RBE)-dose that can be delivered to a tumor at a depth of 6cm) than that for the ISRNF. Also, for a beam current of 10 mA, the treatment time is calculated to be reasonable (approximately 30 min) for the boron concentrations that have been assumed.
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Affiliation(s)
- Thomas E Blue
- Nuclear Engineering Program, Mechanical Engineering Department, The Ohio State University, Columbus, OH 43210, USA.
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35
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Abstract
In this paper a fast method to evaluate neutron spectra for brain BNCT is developed. The method is based on an algorithm to calculate dose distribution in the brain, for which a data matrix has been taken into account, containing weighted biological doses per position per incident energy and the incident neutron spectrum to be evaluated. To build the matrix, using the MCNP 4C code, nearly monoenergetic neutrons were transported into a head model. The doses were scored and an energy-dependent function to biologically weight the doses was used. To find the beam quality, dose distribution along the beam centerline was calculated. A neutron importance function for this therapy to bilaterally treat deep-seated tumors was constructed in terms of neutron energy. Neutrons in the energy range of a few tens of kilo-electron-volts were found to produce the best dose gain, defined as dose to tumor divided by maximum dose to healthy tissue. Various neutron spectra were evaluated through this method. An accelerator-based neutron source was found to be more reliable for this therapy in terms of therapeutic gain than reactors.
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Affiliation(s)
- Guido Martín
- Centro de Aplicaciones Tecnológicas y Desarrollo Nuclear, 5ta y 30, Miramar, Playa, PO Box 6122, Ciudad Habana, Cuba.
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Tanaka K, Kobayashi T, Sakurai Y, Nakagawa Y, Endo S, Hoshi M. Dose distributions in a human head phantom for neutron capture therapy using moderated neutrons from the 2.5 meV proton-7Li reaction or from fission of 235U. Phys Med Biol 2001; 46:2681-95. [PMID: 11686282 DOI: 10.1088/0031-9155/46/10/311] [Citation(s) in RCA: 15] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Abstract
The feasibility of neutron capture therapy (NCT) using an accelerator-based neutron source of the 7Li(p,n) reaction produced by 2.5 MeV protons was investigated by comparing the neutron beam tailored by both the Hiroshima University radiological research accelerator (HIRRAC) and the heavy water neutron irradiation facility in the Kyoto University reactor (KUR-HWNIF) from the viewpoint of the contamination dose ratios of the fast neutrons and the gamma rays. These contamination ratios to the boron dose were estimated in a water phantom of 20 cm diameter and 20 cm length to simulate a human head, with experiments by the same techniques for NCT in KUR-HWNIF and/or the simulation calculations by the Monte Carlo N-particle transport code system version 4B (MCNP-4B). It was found that the 7Li(p,n) neutrons produced by 2.5 MeV protons combined with 20, 25 or 30 cm thick D20 moderators of 20 cm diameter could make irradiation fields for NCT with depth-dose characteristics similar to those from the epithermal neutron beam at the KUR-HWNIF.
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Affiliation(s)
- K Tanaka
- Department of Nuclear Engineering, Kyoto University, Japan
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Burlon AA, Kreiner AJ, White SM, Blackburn BW, Gierga DP, Yanch JC. In-phantom dosimetry for the 13C(d,n)14N reaction as a source for accelerator-based BNCT. Med Phys 2001; 28:796-803. [PMID: 11393475 DOI: 10.1118/1.1368879] [Citation(s) in RCA: 17] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
The use of the 13C(d,n) 14N reaction at Ed=1.5 MeV for accelerator-based boron neutron capture therapy (AB-BNCT) is investigated. Among the deuteron-induced reactions at low incident energy, the 3C(d,n)14N reaction turns out to be one of the best for AB-BNCT because of beneficial materials properties inherent to carbon and its relatively large neutron production cross section. The deuteron beam was produced by a tandem accelerator at MIT's Laboratory for Accelerator Beam Applications (LABA) and the neutron beam shaping assembly included a heavy water moderator and a lead reflector. The resulting neutron spectrum was dosimetrically evaluated at different depths inside a water-filled brain phantom using the dual ionization chamber technique for fast neutrons and photons and bare and cadmium-covered gold foils for the thermal neutron flux. The RBE doses in tumor and healthy tissue were calculated from experimental data assuming a tumor 10B concentration of 40 ppm and a healthy tissue 10B concentration of 11.4 ppm (corresponding to a reported ratio of 3.5:1). All results were simulated using the code MCNP, a general Monte Carlo radiation transport code capable of simulating electron, photon, and neutron transport. Experimental and simulated results are presented at 1, 2, 3, 4, 6, 8, and 10 cm depths along the brain phantom centerline. An advantage depth of 5.6 cm was obtained for a treatment time of 56 min assuming a 4 mA deuteron current and a maximum healthy tissue dose of 12.5 RBE Gy.
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Affiliation(s)
- A A Burlon
- Departamento de Física, Comision Nacional de Energía Atómica, San Martin, Argentina.
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38
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Abstract
With a growing interest in the use of accelerator-based epithermal neutron sources for BNCT programs, in particular those based upon the 7Li(p,n)7Be reaction, there is a need to address the question of "what is the best proton energy to use?" This paper considers this question by using radiation transport calculations to investigate a range of proton energies from 2.15 to 3.5 MeV and a range of moderator sizes. This study has moved away completely from the use of empty therapy beam parameters and instead defines the beam quality and optimizes the moderator design using widely accepted in-phantom treatment planning figures of merit. It is concluded that up to a proton energy of about 2.8 MeV there is no observed variation in the achievable therapy beam quality, but a price is paid in terms of treatment time for not choosing the upper limit of this range. For higher proton energies, the beam quality falls, but with no improvement in treatment time for optimum configurations.
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Affiliation(s)
- D A Allen
- School of Physics and Astronomy, University of Birmingham, Edgbaston, United Kingdom
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39
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Abstract
The optimal neutron energy for the treatment of deep-seated tumours using boron neutron capture therapy is studied by analysing various figures of merit. In particular, analysis of the therapeutic gain as a function of the neutron energy indicates that, with the currently available 10B carriers, the most useful neutrons for the treatment of deep-seated tumours, in particular glioblastoma multiforme, are those with an energy of a few keV. Based on the results of the simulations, a method is presented which allows us to evaluate the quality of epithermal neutron beams of known energy spectrum, thus allowing us to compare different neutron-producing reactions and beam-shaping assembly configurations used for accelerator-based neutron sources.
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Affiliation(s)
- E Biscegliet
- Istituto Nazionale di Fisica Nucleare, Sezione di Bari, Italy
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40
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Colonna N, Beaulieu L, Phair L, Wozniak GJ, Moretto LG, Chu WT, Ludewigt BA. Measurements of low-energy (d,n) reactions for BNCT. Boron Neutron Capture Therapy. Med Phys 1999; 26:793-8. [PMID: 10360544 DOI: 10.1118/1.598599] [Citation(s) in RCA: 25] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
Neutron yields and energy spectra have been measured for various deuteron-induced reactions at low energy. Neutrons of energy > 100 keV emitted in the 9Be(d,n)10B, 12C(d,n)13N, and 13C(d,n)14N reactions at Ed= 1.5 MeV were detected at five angles by means of liquid scintillator detectors. While low-energy neutrons were observed in all studied reactions, only 13C(d,n)14N is characterized by a relatively large yield with spectral features potentially interesting for an accelerator-based neutron source for BNCT.
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Affiliation(s)
- N Colonna
- Istituto Nazionale Fisica Nucleare, Bari, Italy
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Nigg DW. Some recent trends and progress in the physics and biophysics of neutron capture therapy. Progress in Nuclear Energy 1999; 35:79-127. [DOI: 10.1016/s0149-1970(99)00004-9] [Citation(s) in RCA: 16] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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