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Qi J, Geng C, Tang X, Tian F, Han Y, Liu H, Liu Y, Bortolussi S, Guan F. Effect of spatial distribution of boron and oxygen concentration on DNA damage induced from boron neutron capture therapy using Monte Carlo simulations. Int J Radiat Biol 2021; 97:986-996. [PMID: 33970761 DOI: 10.1080/09553002.2021.1928785] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 11/20/2020] [Revised: 04/03/2021] [Accepted: 04/19/2021] [Indexed: 10/21/2022]
Abstract
PURPOSE This paper aims to investigate how the spatial distribution of boron in cells and oxygen concentration affect the DNA damage induced by charged particles in boron neutron capture therapy (BNCT) by Monte Carlo simulations, and further to evaluate the relative biological effectiveness (RBE) of DNA double-strand breaks (DSBs) induction. MATERIALS AND METHODS The kinetic energy spectra of α, 7Li particles in BNCT arriving at the nucleus surface were obtained from GEANT4 (Geant4 10.05.p01). The DNA damage caused by BNCT was then evaluated using MCDS (MCDS 3.10A). RESULTS When α or 7Li particles were distributed in the cytomembrane or cytoplasm, the difference in DNA damage of the same types was less than 0.5%. Taking the 137Cs photons as the reference radiation, when the oxygen concentration varied from 0% to 50%, the RBE of 0.54MeV protons and recoil protons varied from 5 to 2, whereas it decreased from 10 to 3 for α or 7Li particles. CONCLUSION The RBE of DSB induction all charged particles in BNCT decreased with the increase of oxygen concentration. This work indicated that the RBE of different radiation particles of BNCT might be affected by many factors, which should be paid attention to in theoretical research or clinical application.
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Affiliation(s)
- Jie Qi
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | - Changran Geng
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
- Key Laboratory of Nuclear Technology Application and Radiation Protection in Astronautics, Ministry of Industry and Information Technology, Nanjing, China
- Joint International Research Laboratory on Advanced Particle Therapy, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | - Xiaobin Tang
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
- Key Laboratory of Nuclear Technology Application and Radiation Protection in Astronautics, Ministry of Industry and Information Technology, Nanjing, China
- Joint International Research Laboratory on Advanced Particle Therapy, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | - Feng Tian
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | - Yang Han
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
- Department of Physics, University of Pavia, Pavia, Italy
| | - Huan Liu
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | - Yuanhao Liu
- Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, China
| | | | - Fada Guan
- Department of Radiation Physics, Division of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, TX, USA
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Wu S, Geng C, Tang X, Bortolussi S, Han Y, Shu D, Gong C, Zhang X, Tian F. Dosimetric impact of respiratory motion during boron neutron capture therapy for lung cancer. Radiat Phys Chem Oxf Engl 1993 2020. [DOI: 10.1016/j.radphyschem.2019.108527] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/31/2022]
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3
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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. [DOI: 10.1007/s10967-018-6161-1] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Farhad Masoudi S, Ghiasi H, Harif M, Rasouli FS. An electron linac-based system for BNCT of shallow tumors. Radiat Phys Chem Oxf Engl 1993 2018. [DOI: 10.1016/j.radphyschem.2018.03.001] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Zaidi L, Belgaid M, Taskaev S, Khelifi R. Beam shaping assembly design of 7Li(p,n) 7Be neutron source for boron neutron capture therapy of deep-seated tumor. Appl Radiat Isot 2018; 139:316-324. [PMID: 29890472 DOI: 10.1016/j.apradiso.2018.05.029] [Citation(s) in RCA: 24] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/17/2017] [Revised: 03/11/2018] [Accepted: 05/29/2018] [Indexed: 11/19/2022]
Abstract
The development of a medical facility for boron neutron capture therapy at Budker Institute of Nuclear Physics is under way. The neutron source is based on a tandem accelerator with vacuum insulation and lithium target. The proposed accelerator is conceived to deliver a proton beam around 10 mA at 2.3 MeV proton beam. To deliver a therapeutic beam for treatment of deep-seated tumors a typical Beam Shaping Assembly (BSA) based on the source specifications has been explored. In this article, an optimized BSA based on the 7Li(p,n)7Be neutron production reaction is proposed. To evaluate the performance of the designed beam in a phantom, the parameters and the dose profiles in tissues due to the irradiation have been considered. In the simulations, we considered a proton energy of 2.3 MeV, a current of 10 mA, and boron concentrations in tumor, healthy tissues and skin of 52.5 ppm, 15 ppm and 22.5 ppm, respectively. It is found that, for a maximum punctual healthy tissue dose seated to 11 RBE-Gy, a mean dose of 56.5 RBE Gy with a minimum of 52.2 RBE Gy can be delivered to a tumor in 40 min, where the therapeutic ratio is estimated to 5.38. All of these calculations were carried out using the Monte Carlo MCNP code.
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Affiliation(s)
- L Zaidi
- University of Science and Technology Houari Boumediene, Faculty of Physics, SNIRM Laboratory, BP 32 El Alia 16111, Bab Ezzouar 16111, Algeria.
| | - M Belgaid
- University of Science and Technology Houari Boumediene, Faculty of Physics, SNIRM Laboratory, BP 32 El Alia 16111, Bab Ezzouar 16111, Algeria
| | - S Taskaev
- Novosibirsk State University, st. Pirogova 2, Novosibirsk 630090, Russia; Budker Institute of Nuclear Physics, Siberian Branch, Russian Academy of Sciences, pr. Akademika Lavrentieva 11, Novosibirsk 630090, Russia
| | - R Khelifi
- Saad Dahlab University, Departement of Physics, LPTHIRM Laboratory, BP 270 Soumaa, Algeria
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Geant4 beam model for boron neutron capture therapy: investigation of neutron dose components. AUSTRALASIAN PHYSICAL & ENGINEERING SCIENCES IN MEDICINE 2018; 41:129-141. [PMID: 29362987 DOI: 10.1007/s13246-018-0617-z] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/25/2017] [Accepted: 01/08/2018] [Indexed: 10/18/2022]
Abstract
Boron neutron capture therapy (BNCT) is a biochemically-targeted type of radiotherapy, selectively delivering localized dose to tumour cells diffused in normal tissue, while minimizing normal tissue toxicity. BNCT is based on thermal neutron capture by stable [Formula: see text]B nuclei resulting in emission of short-ranged alpha particles and recoil [Formula: see text]Li nuclei. The purpose of the current work was to develop and validate a Monte Carlo BNCT beam model and to investigate contribution of individual dose components resulting of neutron interactions. A neutron beam model was developed in Geant4 and validated against published data. The neutron beam spectrum, obtained from literature for a cyclotron-produced beam, was irradiated to a water phantom with boron concentrations of 100 μg/g. The calculated percentage depth dose curves (PDDs) in the phantom were compared with published data to validate the beam model in terms of total and boron depth dose deposition. Subsequently, two sensitivity studies were conducted to quantify the impact of: (1) neutron beam spectrum, and (2) various boron concentrations on the boron dose component. Good agreement was achieved between the calculated and measured neutron beam PDDs (within 1%). The resulting boron depth dose deposition was also in agreement with measured data. The sensitivity study of several boron concentrations showed that the calculated boron dose gradually converged beyond 100 μg/g boron concentration. This results suggest that 100μg/g tumour boron concentration may be optimal and above this value limited increase in boron dose is expected for a given neutron flux.
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Affiliation(s)
- John A. Bernard
- Massachusetts Institute of Technology 138 Albany Street, Cambridge, Massachusetts 02139-4296
| | - Lin-Wen Hu
- Massachusetts Institute of Technology 138 Albany Street, Cambridge, Massachusetts 02139-4296
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Maučec M. Conceptual Design of a Clinical BNCT Beam in an Adjacent Dry Cell of the Jožef Stefan Institute TRIGA Reactor. NUCL TECHNOL 2017. [DOI: 10.13182/nt00-a3137] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Marko Maučec
- Jožef Stefan Institute, Reactor Physics Division Jamova 39, 1000 Ljubljana, Slovenia
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Ronen Y, Aboudy M, Regev D. Homogeneous242mAm-Fueled Reactor for Neutron Capture Therapy. NUCL SCI ENG 2017. [DOI: 10.13182/nse01-a2215] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Y. Ronen
- Ben-Gurion University, Department of Nuclear Engineering, Beer-Sheva, 84105, Israel
| | - M. Aboudy
- Ben-Gurion University, Department of Nuclear Engineering, Beer-Sheva, 84105, Israel
| | - D. Regev
- Ben-Gurion University, Department of Nuclear Engineering, Beer-Sheva, 84105, Israel
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Harling OK, Riley KJ, Newton TH, Wilson BA, Bernard JA, Hu LW, Fonteneau EJ, Menadier PT, Ali SJ, Sutharshan B, Kohse GE, Ostrovsky Y, Stahle PW, Binns PJ, Kiger WS, Busse PM. The Fission Converter-Based Epithermal Neutron Irradiation Facility at the Massachusetts Institute of Technology Reactor. NUCL SCI ENG 2017. [DOI: 10.13182/nse02-a2258] [Citation(s) in RCA: 46] [Impact Index Per Article: 6.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- O. K. Harling
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - K. J. Riley
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - T. H. Newton
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - B. A. Wilson
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - J. A. Bernard
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - L-W. Hu
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - E. J. Fonteneau
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - P. T. Menadier
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - S. J. Ali
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - B. Sutharshan
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - G. E. Kohse
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Y. Ostrovsky
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - P. W. Stahle
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - P. J. Binns
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - W. S. Kiger
- Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - P. M. Busse
- Beth Israel-Deaconess Medical Center, Department of Radiation Oncology 330 Brookline Avenue, Boston, Massachusetts 02215
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12
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Newton TH, Riley KJ, Binns PJ, Kohse GE, Hu LW, Harling OK. Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor. NUCL TECHNOL 2017. [DOI: 10.13182/nt02-a3312] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Thomas H. Newton
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Kent J. Riley
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Peter J. Binns
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Gordon E. Kohse
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Lin-Wen Hu
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
| | - Otto K. Harling
- Massachusetts Institute of Technology, Nuclear Reactor Laboratory 138 Albany Street, Cambridge, Massachusetts 02139
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13
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Ganda F, Vujic J, Greenspan E, Leung KN. Compact D-D Neutron Source-Driven Subcritical Multiplier and Beam-Shaping Assembly for Boron Neutron Capture Therapy. NUCL TECHNOL 2017. [DOI: 10.13182/nt10-a10939] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Francesco Ganda
- University of California at Berkeley, Department of Nuclear EngineeringBerkeley, California
| | - Jasmina Vujic
- University of California at Berkeley, Department of Nuclear EngineeringBerkeley, California
| | - Ehud Greenspan
- University of California at Berkeley, Department of Nuclear EngineeringBerkeley, California
| | - Ka-Ngo Leung
- University of California at Berkeley, Department of Nuclear EngineeringBerkeley, California
- Lawrence Berkeley National Laboratory, Berkeley, California
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14
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Mokhtari J, Faghihi F, Khorsandi J, Hadad K. Conceptual design study of the low power and LEU medical reactor for BNCT using in-tank fission converter to increase epithermal flux. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2016.11.014] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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15
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Zolfaghari M, Sedaghatizadeh M. Design of thermal neutron beam based on an electron linear accelerator for BNCT. Appl Radiat Isot 2016; 118:149-153. [PMID: 27640175 DOI: 10.1016/j.apradiso.2016.08.024] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/03/2015] [Revised: 08/03/2016] [Accepted: 08/30/2016] [Indexed: 11/25/2022]
Abstract
An electron linear accelerator (Linac) can be used for boron neutron capture therapy (BNCT) by producing thermal neutron flux. In this study, we used a Varian 2300 C/D Linac and MCNPX.2.6.0 code to simulate an electron-photoneutron source for use in BNCT. In order to decelerate the produced fast neutrons from the photoneutron source, which optimize the thermal neutron flux, a beam-shaping assembly (BSA) was simulated. After simulations, a thermal neutron flux with sharp peak at the beam exit was obtained in the order of 3.09×108n/cm2 s and 6.19×108n/cm2 s for uranium and enriched uranium (10%) as electron-photoneutron sources respectively. Also, in-phantom dose analysis indicates that the simulated thermal neutron beam can be used for treatment of shallow skin melanoma in time of about 85.4 and 43.6min for uranium and enriched uranium (10%) respectively.
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Affiliation(s)
- Mona Zolfaghari
- Department of Physics, Faculty of Science, K.N. Toosi University of Technology, Tehran, Iran.
| | - Mahmood Sedaghatizadeh
- Department of Physics, Faculty of Science, K.N. Toosi University of Technology, Tehran, Iran
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Hang S, Tang X, Shu D, Liu Y, Geng C, Gong C, Yu H, Chen D. Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator. J Radioanal Nucl Chem 2016. [DOI: 10.1007/s10967-016-5001-4] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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17
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BNCT project at Tehran Research Reactor: Current and prospective plans. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.04.010] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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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] [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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Farías RO, Bortolussi S, Menéndez PR, González SJ. Exploring Boron Neutron Capture Therapy for non-small cell lung cancer. Phys Med 2014; 30:888-97. [PMID: 25176019 DOI: 10.1016/j.ejmp.2014.07.342] [Citation(s) in RCA: 24] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Submit a Manuscript] [Subscribe] [Scholar Register] [Received: 04/16/2014] [Revised: 07/02/2014] [Accepted: 07/30/2014] [Indexed: 12/31/2022] Open
Abstract
Boron Neutron Capture Therapy (BNCT) is a radiotherapy that combines biological targeting and high LET radiation. It consists in the enrichment of tumour with (10)B and in the successive irradiation of the target with low energy neutrons producing charged particles that mainly cause non-repairable damages to the cells. The feasibility to treat Non Small Cells Lung Cancer (NSCLC) with BNCT was explored. This paper proposes a new approach to determine treatment plans, introducing the possibility to choose the irradiation start and duration to maximize the tumour dose. A Tumour Control Probability (TCP) suited for lung BNCT as well as other high dose radiotherapy schemes was also introduced. Treatment plans were evaluated in localized and disseminated lung tumours. Semi-ideal and real energy spectra beams were employed to assess the best energy range and the performance of non-tailored neutron sources for lung tumour treatments. The optimal neutron energy is within [500 eV-3 keV], lower than the 10 keV suggested for the treatment of deep-seated tumours in the brain. TCPs higher than 0.6 and up to 0.95 are obtained for all cases. Conclusions drawn from [Suzuki et al., Int Canc Conf J 1 (4) (2012) 235-238] supporting the feasibility of BNCT for shallow lung tumours are confirmed, however discussions favouring the treatment of deeper lesions and disseminated disease are also opened. Since BNCT gives the possibility to deliver a safe and potentially effective treatment for NSCLC, it can be considered a suitable alternative for patients with few or no treatment options.
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Affiliation(s)
- Rubén O Farías
- Comisión Nacional de Energía Atómica (CNEA), Av. Gral. Paz 1499, Buenos Aires B1650KNA, Argentina; Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET), Av. Rivadavia 1917, Buenos Aires C1033AAJ, Argentina
| | - Silva Bortolussi
- Department of Physics, University of Pavia, via Bassi 6, Pavia 27100, Italy; National Institute of Nuclear Physics (INFN), via Bassi 6, Pavia 27100, Italy
| | - Pablo R Menéndez
- Insituto de Oncología "Angel H. Roffo", Universidad de Buenos Aires, Av. San Martin, n° 5421, Buenos Aires C1417DTB, Argentina
| | - Sara J González
- Comisión Nacional de Energía Atómica (CNEA), Av. Gral. Paz 1499, Buenos Aires B1650KNA, Argentina; Consejo Nacional de Investigaciones Científicas y Técnicas (CONICET), Av. Rivadavia 1917, Buenos Aires C1033AAJ, Argentina.
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BSA optimization and dosimetric assessment for an electron linac based BNCT of deep‐seated brain tumors. J Radioanal Nucl Chem 2014. [DOI: 10.1007/s10967-014-3087-0] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Investigation on F/M material aspects of IRT-Sofia NCT channel. Appl Radiat Isot 2013; 88:180-4. [PMID: 24359789 DOI: 10.1016/j.apradiso.2013.11.112] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 12/13/2012] [Revised: 11/24/2013] [Accepted: 11/26/2013] [Indexed: 11/23/2022]
Abstract
The filter/moderator area of IRT-Sofia BNCT channel was investigated in this study in order to find a higher radiation resistant material as a suitable substitution for the Teflon(®). Two options - Al2O3 and graphite - were investigated. The results show, that both graphite and the Al2O3 can be successfully used as a filter/moderator material at IRT-Sofia. Initial evaluation of the in-phantom performance of the IRT-Sofia BNCT channel was made and merits similar to the best existing ones were found.
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Kasesaz Y, Khalafi H, Rahmani F. Optimization of the beam shaping assembly in the D-D neutron generators-based BNCT using the response matrix method. Appl Radiat Isot 2013; 82:55-9. [PMID: 23954283 DOI: 10.1016/j.apradiso.2013.07.008] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/27/2011] [Revised: 06/19/2013] [Accepted: 07/01/2013] [Indexed: 11/17/2022]
Abstract
Optimization of the Beam Shaping Assembly (BSA) has been performed using the MCNP4C Monte Carlo code to shape the 2.45 MeV neutrons that are produced in the D-D neutron generator. Optimal design of the BSA has been chosen by considering in-air figures of merit (FOM) which consists of 70 cm Fluental as a moderator, 30 cm Pb as a reflector, 2mm (6)Li as a thermal neutron filter and 2mm Pb as a gamma filter. The neutron beam can be evaluated by in-phantom parameters, from which therapeutic gain can be derived. Direct evaluation of both set of FOMs (in-air and in-phantom) is very time consuming. In this paper a Response Matrix (RM) method has been suggested to reduce the computing time. This method is based on considering the neutron spectrum at the beam exit and calculating contribution of various dose components in phantom to calculate the Response Matrix. Results show good agreement between direct calculation and the RM method.
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Affiliation(s)
- Y Kasesaz
- Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), Tehran 14399-51113, Iran
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Torabi F, Masoudi SF, Rahmani F. Photoneutron production by a 25MeV electron linac for BNCT application. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2012.11.001] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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24
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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] [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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25
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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] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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26
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Anghel V. Prediction of the Safety Level to an Installation of the Tritium Process Through Predictive Maintenance. FUSION SCIENCE AND TECHNOLOGY 2008. [DOI: 10.13182/fst08-a1830] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Vasile Anghel
- National Research and Development Institute for Cryogenics and Isotopic Technologies – ICIT Rm.Valcea Uzinei Street no.4, Code: 240050 ROMANIA,
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Binns PJ, Riley KJ, Ostrovsky Y, Gao W, Albritton JR, Kiger WS, Harling OK. Improved Dose Targeting for a Clinical Epithermal Neutron Capture Beam Using Optional 6Li Filtration. Int J Radiat Oncol Biol Phys 2007; 67:1484-91. [PMID: 17394946 DOI: 10.1016/j.ijrobp.2006.11.022] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 09/08/2006] [Revised: 11/07/2006] [Accepted: 11/09/2006] [Indexed: 10/23/2022]
Abstract
PURPOSE The aim of this study was to construct a (6)Li filter and to improve penetration of thermal neutrons produced by the fission converter-based epithermal neutron beam (FCB) for brain irradiation during boron neutron capture therapy (BNCT). METHODS AND MATERIALS Design of the (6)Li filter was evaluated using Monte Carlo simulations of the existing beam line and radiation transport through an ellipsoidal water phantom. Changes in beam performance were determined using three figures of merit: (1) advantage depth (AD), the depth at which the total biologically weighted dose to tumor equals the maximum weighted dose to normal tissue; (2) advantage ratio (AR), the ratio of the integral tumor dose to that of normal tissue averaged from the surface to the AD; and (3) advantage depth dose rate (ADDR), the therapeutic dose rate at the AD. Dosimetry performed with the new filter installed provided calibration data for treatment planning. Past treatment plans were recalculated to illustrate the clinical potential of the filter. RESULTS The 8-mm-thick Li filter is more effective for smaller field sizes, increasing the AD from 9.3 to 9.9 cm, leaving the AR unchanged at 5.7 but decreasing the ADDR from 114 to 55 cGy min(-1) for the 12 cm diameter aperture. Using the filter increases the minimum deliverable dose to deep seated tumors by up to 9% for the same maximum dose to normal tissue. CONCLUSIONS Optional (6)Li filtration provides an incremental improvement in clinical beam performance of the FCB that could help to establish a therapeutic window in the future treatment of deep-seated tumors.
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Affiliation(s)
- Peter J Binns
- Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge, MA 02139, USA.
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Kiger WS, Lu XQ, Harling OK, Riley KJ, Binns PJ, Kaplan J, Patel H, Zamenhof RG, Shibata Y, Kaplan ID, Busse PM, Palmer MR. Preliminary treatment planning and dosimetry for a clinical trial of neutron capture therapy using a fission converter epithermal neutron beam. Appl Radiat Isot 2005; 61:1075-81. [PMID: 15308195 DOI: 10.1016/j.apradiso.2004.05.008] [Citation(s) in RCA: 26] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Abstract] [MESH Headings] [Grants] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
Abstract
A Phase I/II clinical trial of neutron capture therapy (NCT) was conducted at Harvard-MIT using a fission converter epithermal neutron beam. This epithermal neutron beam has nearly ideal performance characteristics (high intensity and purity) and is well-suited for clinical use. Six glioblastoma multiforme (GBM) patients were treated with NCT by infusion of the tumor-selective amino acid boronophenylalanine-fructose (BPA-F) at a dose of 14.0 g/m(2) body surface area over 90 min followed by irradiation with epithermal neutrons. Treatments were planned using NCTPlan and an accelerated version of the Monte Carlo radiation transport code MCNP 4B. Treatments were delivered in two fractions with two or three fields. Field order was reversed between fractions to equalize the average blood boron concentration between fields. The initial dose in the dose escalation study was 7.0 RBEGy, prescribed as the mean dose to the whole brain volume. This prescription dose was increased by 10% to 7.7 RBEGy in the second cohort of patients. A pharmacokinetic model was used to predict the blood boron concentration for determination of the required beam monitor units with good accuracy; differences between prescribed and delivered doses were 1.5% or less. Estimates of average tumor doses ranged from 33.7 to 83.4 RBEGy (median 57.8 RBEGy), a substantial improvement over our previous trial where the median value of the average tumor dose was 25.8 RBEGy.
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Affiliation(s)
- W S Kiger
- Department of Radiation Oncology, Beth Israel Deaconess Medical Center, Harvard Medical School, 330 Brookline Avenue, Boston, MA 02215, USA
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Ye SJ, Pareek PN, Spencer S, Duan J, Brezovich IA. Monte Carlo techniques for scattering foil design and dosimetry in total skin electron irradiations. Med Phys 2005; 32:1460-8. [PMID: 16013701 DOI: 10.1118/1.1924368] [Citation(s) in RCA: 13] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
Total skin electron irradiation (TSEI) with single fields requires large electron beams having good dose uniformity, dmax at the skin surface, and low bremsstrahlung contamination. To satisfy these requirements, energy degraders and scattering foils have to be specially designed for the given accelerator and treatment room. We used Monte Carlo (MC) techniques based on EGS4 user codes (BEAM, DOSXYZ, and DOSRZ) as a guide in the beam modifier design of our TSEI system. The dosimetric characteristics at the treatment distance of 382 cm source-to-surface distance (SSD) were verified experimentally using a linear array of 47 ion chambers, a parallel plate chamber, and radiochromic film. By matching MC simulations to standard beam measurements at 100 cm SSD, the parameters of the electron beam incident on the vacuum window were determined. Best match was achieved assuming that electrons were monoenergetic at 6.72 MeV, parallel, and distributed in a circular pattern having a Gaussian radial distribution with full width at half maximum = 0.13 cm. These parameters were then used to simulate our TSEI unit with various scattering foils. Two of the foils were fabricated and experimentally evaluated by measuring off-axis dose uniformity and depth doses. A scattering foil, consisting of a 12 x 12 cm2 aluminum plate of 0.6 cm thickness and placed at isocenter perpendicular to the beam direction, was considered optimal. It produced a beam that was flat within +/-3% up to 60 cm off-axis distance, dropped by not more than 8% at a distance of 90 cm, and had an x-ray contamination of <3%. For stationary beams, MC-computed dmax, Rp, and R50 agreed with measurements within 0.5 mm. The MC-predicted surface dose of the rotating phantom was 41% of the dose rate at dmax of the stationary phantom, whereas our calculations based on a semiempirical formula in the literature yielded a drop to 42%. The MC simulations provided the guideline of beam modifier design for TSEI and estimated the dosimetric performance for stationary and rotational irradiations.
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Affiliation(s)
- Sung-Joon Ye
- Department of Radiation Oncology, The University of Alabama School of Medicine, 1824 6th Avenue South, Birmingham, Alabama 35294, USA.
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SAKURAI Y. Depth-Dose-Distribution Control for Incident Beam Directionality and Irradiation Field Size in Boron Neutron Capture Therapy. J NUCL SCI TECHNOL 2005. [DOI: 10.1080/18811248.2005.9726358] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Coderre JA, Turcotte JC, Riley KJ, Binns PJ, Harling OK, Kiger WS. Boron neutron capture therapy: cellular targeting of high linear energy transfer radiation. Technol Cancer Res Treat 2004; 2:355-75. [PMID: 14529302 DOI: 10.1177/153303460300200502] [Citation(s) in RCA: 86] [Impact Index Per Article: 4.3] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022] Open
Abstract
Boron neutron capture therapy (BNCT) is based on the preferential targeting of tumor cells with (10)B and subsequent activation with thermal neutrons to produce a highly localized radiation. In theory, it is possible to selectively irradiate a tumor and the associated infiltrating tumor cells with large single doses of high-LET radiation while sparing the adjacent normal tissues. The mixture of high- and low-LET dose components created in tissue during neutron irradiation complicates the radiobiology of BNCT. Much of the complexity has been unravelled through a combination of preclinical experimentation and clinical dose escalation experience. Over 350 patients have been treated in a number of different facilities worldwide. The accumulated clinical experience has demonstrated that BNCT can be delivered safely but is still defining the limits of normal brain tolerance. Several independent BNCT clinical protocols have demonstrated that BNCT can produce median survivals in patients with glioblastoma that appear to be equivalent to conventional photon therapy. This review describes the individual components and methodologies required for effect BNCT: the boron delivery agents; the analytical techniques; the neutron beams; the dosimetry and radiation biology measurements; and how these components have been integrated into a series of clinical studies. The single greatest weakness of BNCT at the present time is non-uniform delivery of boron into all tumor cells. Future improvements in BNCT effectiveness will come from improved boron delivery agents, improved boron administration protocols, or through combination of BNCT with other modalities.
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Affiliation(s)
- Jeffrey A Coderre
- Nuclear Engineering Department, Massachusetts Institute of Technology, Cambridge, MA, USA.
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Riley KJ, Binns PJ, Ali SJ, Harling OK. The design, construction and performance of a variable collimator for epithermal neutron capture therapy beams. Phys Med Biol 2004; 49:2015-28. [PMID: 15214538 DOI: 10.1088/0031-9155/49/10/012] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/11/2022]
Abstract
A patient collimator for the fission converter based epithermal neutron beam (FCB) at the Massachusetts Institute of Technology Research Reactor (MITR-II) was built for clinical trials of boron neutron capture therapy (BNCT). A design was optimized by Monte Carlo simulations of the entire beam line and incorporates a modular construction for easy modifications in the future. The device was formed in-house by casting a mixture of lead spheres (7.6 mm diameter) in epoxy resin loaded with either 140 mg cm(-3) of boron carbide or 210 mg cm(-3) of lithium fluoride (95% enriched in 6Li). The cone shaped collimator allows easy field placement anywhere on the patient and is equipped with a laser indicator of central axis, beam's eye view optics and circular apertures of 80, 100, 120 and 160 mm diameter. Beam profiles and the collateral dose in a half-body phantom were measured for the 160 mm field using fission counters, activation foils as well as tissue equivalent (A-150) and graphite walled ionization chambers. Leakage radiation through the collimator contributes less than 10% to the total collateral dose up to 0.15 m beyond the edge of the aperture and becomes relatively more prominent with lateral displacement. The measured whole body dose equivalent of 24 +/- 2 mSv per Gy of therapeutic dose is comparable to doses received during conventional therapy and is due principally (60-80%) to thermal neutron capture reactions with boron. These findings, together with the dose distributions for the primary beam, demonstrate the suitability of this patient collimator for BNCT.
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Affiliation(s)
- K J Riley
- Nuclear Reactor Laboratory, Massachusetts Institute of Technology, 138 Albany St. Cambridge, MA 02139, USA
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Tracz G, Dabkowski L, Dworak D, Pytel K, Woźnicka U. The filter/moderator arrangement-optimisation for the boron-neutron capture therapy (BNCT). RADIATION PROTECTION DOSIMETRY 2004; 110:827-831. [PMID: 15353754 DOI: 10.1093/rpd/nch145] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/24/2023]
Abstract
The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for the boron neutron capture therapy (BNCT) facility to be located at the Polish research nuclear reactor MARIA at Swierk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised to moderate fission neutrons to epithermal energies and to remove both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both high epithermal neutron flux and suitably low level of beam contamination. Photons originating from the reactor core are almost eliminated what is the exceptional advantage of the proposed design. It yields one order of magnitude lower gamma radiation dose than the maximum allowed dose in such a type of therapeutic facility. The MCNP code has been used for the computations.
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Affiliation(s)
- G Tracz
- The Henryk Niewodniczański Institute of Nuclear Physics of the Polish Academy of Sciences, ul. Radzikowskiego 152, 31-342 Kraków, Poland.
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Giusti V, Munck af Rosenschöld PM, Sköld K, Montagnini B, Capala J. Monte Carlo model of the Studsvik BNCT clinical beam: Description and validation. Med Phys 2003; 30:3107-17. [PMID: 14713077 DOI: 10.1118/1.1626120] [Citation(s) in RCA: 17] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
The neutron beam at the Studsvik facility for boron neutron capture therapy (BNCT) and the validation of the related computational model developed for the MCNP-4B Monte Carlo code are presented. Several measurements performed at the epithermal neutron port used for clinical trials have been made in order to validate the Monte Carlo computational model. The good general agreement between the MCNP calculations and the experimental results has provided an adequate check of the calculation procedure. In particular, at the nominal reactor power of 1 MW, the calculated in-air epithermal neutron flux in the energy interval between 0.4 eV-10 keV is 3.24 x 10(9) n cm(-2) s(-1) (+/- 1.2% 1 std. dev.) while the measured value is 3.30 x 10(9) n cm(-20 s(-1) (+/- 5.0% 1 std. dev.). Furthermore, the calculated in-phantom thermal neutron flux, equal to 6.43 x 10(9) n cm(-2) s(-1) (+/- 1.0% 1 std. dev.), and the corresponding measured value of 6.33 X 10(9) n cm(-2) s(-1) (+/- 5.3% 1 std. dev.) agree within their respective uncertainties. The only statistically significant disagreement is a discrepancy of 39% between the MCNP calculations of the in-air photon kerma and the corresponding experimental value. Despite this, a quite acceptable overall in-phantom beam performance was obtained, with a maximum value of the therapeutic ratio (the ratio between the local tumor dose and the maximum healthy tissue dose) equal to 6.7. The described MCNP model of the Studsvik facility has been deemed adequate to evaluate further improvements in the beam design as well as to plan experimental work.
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Affiliation(s)
- Valerio Giusti
- Department of Mechanical, Nuclear and Production Engineering, Pisa University, Pisa, Italy.
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Riley KJ, Binns PJ, Harling OK. Performance characteristics of the MIT fission converter based epithermal neutron beam. Phys Med Biol 2003; 48:943-58. [PMID: 12701897 DOI: 10.1088/0031-9155/48/7/310] [Citation(s) in RCA: 37] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/11/2022]
Abstract
A pre-clinical characterization of the first fission converter based epithermal neutron beam (FCB) designed for boron neutron capture therapy (BNCT) has been performed. Calculated design parameters describing the physical performance of the aluminium and Teflon filtered beam were confirmed from neutron fluence and absorbed dose rate measurements performed with activation foils and paired ionization chambers. The facility currently provides an epithermal neutron flux of 4.6 x 10(9) n cm(-2) s(-1) in-air at the patient position that makes it the most intense BNCT source in the world. This epithermal neutron flux is accompanied by very low specific photon and fast neutron absorbed doses of 3.5 +/- 0.5 and 1.4 +/- 0.2 x 10(-13) Gy cm2, respectively. A therapeutic dose rate of 1.7 RBE Gy min(-1) is achievable at the advantage depth of 97 mm when boronated phenylalanine (BPA) is used as the delivery agent, giving an average therapeutic ratio of 5.7. In clinical trials of normal tissue tolerance when using the FCB, the effective prescribed dose is due principally to neutron interactions with the nonselectively absorbed BPA present in brain. If an advanced compound is considered, the dose to brain would instead be predominately from the photon kerma induced by thermal neutron capture in hydrogen and advantage parameters of 0.88 Gy min(-1), 121 mm and 10.8 would be realized for the therapeutic dose rate, advantage depth and therapeutic ratio, respectively. This study confirms the success of a new approach to producing a high intensity, high purity epithermal neutron source that attains near optimal physical performance and which is well suited to exploit the next generation of boron delivery agents.
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Affiliation(s)
- K J Riley
- Nuclear Reactor Laboratory and Department of Nuclear Engineering, Massachusetts Institute of Technology, 138 Albany Street, Cambridge, MA 02139. USA.
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Kiger WS, Palmer MR, Riley KJ, Zamenhof RG, Busse PM. Pharamacokinetic modeling for boronophenylalanine-fructose mediated neutron capture therapy: 10B concentration predictions and dosimetric consequences. J Neurooncol 2003; 62:171-86. [PMID: 12749712 DOI: 10.1007/bf02699943] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [MESH Headings] [Grants] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
Abstract
A two-compartment open model has been developed for predicting 10B concentrations in blood following intravenous infusion of the L-p-boronophenylalanine-fructose complex in humans and derived from pharmacokinetic studies of 24 patients in Phase I clinical trials of boron neutron capture therapy. The 10B concentration profile in blood exhibits a characteristic rise during the infusion to a peak of approximately 32 microg/g (for infusion of 350 mg/kg over 90 min) followed by a biexponential disposition profile with harmonic mean half-lives of 0.32 +/- 0.08 and 8.2 +/- 2.7 h, most likely due to redistribution and primarily renal elimination, respectively. The mean model rate constants k12, k21, and k10 are (mean +/- SD) 0.0227 +/- 0.0064 min(-1), 0.0099 +/- 0.0027 min(-1), 0.0052 +/- 0.0016 min(-1), respectively, and the central compartment volume of distribution V1 is 0.235 +/- 0.042 L/kg. In anticipation of the initiation of clinical trials using an intense neutron beam with concomitantly short irradiations, the ability of this model to predict, in advance, the average blood 10B concentration during brief irradiations was simulated in a retrospective analysis of the pharmacokinetic data from these patients. The prediction error for blood boron concentration and its effect on simulated dose delivered for each irradiation field are reported for three different prediction strategies. In this simulation, error in delivered dose (or, equivalently, neutron fluence) for a given single irradiation field resulting from error in predicted blood 10B concentration was limited to less than 10%. In practice, lower dose errors can be achieved by delivering each field in two fractions (on two separate days) and by adjusting the second fraction's dose to offset error in the first.
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Affiliation(s)
- W S Kiger
- Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge, MA, USA.
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37
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Busse PM, Harling OK, Palmer MR, Kiger WS, Kaplan J, Kaplan I, Chuang CF, Goorley JT, Riley KJ, Newton TH, Santa Cruz GA, Lu XQ, Zamenhof RG. A critical examination of the results from the Harvard-MIT NCT program phase I clinical trial of neutron capture therapy for intracranial disease. J Neurooncol 2003; 62:111-21. [PMID: 12749707 DOI: 10.1007/bf02699938] [Citation(s) in RCA: 81] [Impact Index Per Article: 3.9] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
Abstract
A phase I trial was designed to evaluate normal tissue tolerance to neutron capture therapy (NCT); tumor response was also followed as a secondary endpoint. Between July 1996 and May 1999, 24 subjects were entered into a phase I trial evaluating cranial NCT in subjects with primary or metastatic brain tumors. Two subjects were excluded due to a decline in their performance status and 22 subjects were irradiated at the MIT Nuclear Reactor Laboratory. The median age was 56 years (range 24-78). All subjects had a pathologically confirmed diagnosis of either glioblastoma (20) or melanoma (2) and a Karnofsky of 70 or higher. Neutron irradiation was delivered with a 15 cm diameter epithermal beam. Treatment plans varied from 1 to 3 fields depending upon the size and location of the tumor. The 10B carrier, L-p-boronophenylalanine-fructose (BPA-f), was infused through a central venous catheter at doses of 250 mg kg(-1) over 1 h (10 subjects), 300 mg kg(-1) over 1.5 h (two subjects), or 350 mg kg(-1) over 1.5-2 h (10 subjects). The pharmacokinetic profile of 10B in blood was very reproducible and permitted a predictive model to be developed. Cranial NCT can be delivered at doses high enough to exhibit a clinical response with an acceptable level of toxicity. Acute toxicity was primarily associated with increased intracranial pressure; late pulmonary effects were seen in two subjects. Factors such as average brain dose, tumor volume, and skin, mucosa, and lung dose may have a greater impact on tolerance than peak dose alone. Two subjects exhibited a complete radiographic response and 13 of 17 evaluable subjects had a measurable reduction in enhanced tumor volume following NCT.
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Affiliation(s)
- Paul M Busse
- Department of Radiation Oncology, Beth Israel Deaconess Medical Center, Harvard Medical School, Boston, MA 02215, USA.
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Sakurai Y, Kobayashi T. The medical-irradiation characteristics for neutron capture therapy at the Heavy Water Neutron Irradiation Facility of Kyoto University Research Reactor. Med Phys 2002; 29:2328-37. [PMID: 12408307 DOI: 10.1118/1.1509444] [Citation(s) in RCA: 28] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
At the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor, the mix irradiation of thermal and epi-thermal neutrons, and the solo irradiation of epi-thermal neutrons are available additionally to the thermal neutron irradiation, and then the neutron capture therapy (NCT) at this facility became more flexible, after the update in 1996. The estimation of the depth dose distributions in NCT clinical irradiation, were performed for the standard irradiation modes of thermal, mixed and epi-thermal neutrons, from the both sides of experiment and calculation. On the assumption that the 10B concentration in tumor part was 40 ppm and the ratio of tumor to normal tissue was 3.5, the advantage depth were estimated to 5.4, 6.0, and 8.0, for the respective standard irradiation modes. It was confirmed that the various irradiation conditions can be selected according to the target-volume conditions, such as size, depth, etc. Besides, in the viewpoint of the radiation shielding for patient, it was confirmed that the whole-body exposure is effectively reduced by the new clinical collimators, compared with the old one.
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Affiliation(s)
- Yoshinori Sakurai
- Kyoto University Research Reactor Institute, Sennan-gun, Osaka, Japan
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Palmer MR, Goorley JT, Kiger WS, Busse PM, Riley KJ, Harling OK, Zamenhof RG. Treatment planning and dosimetry for the Harvard-MIT Phase I clinical trial of cranial neutron capture therapy. Int J Radiat Oncol Biol Phys 2002; 53:1361-79. [PMID: 12128139 DOI: 10.1016/s0360-3016(02)02862-6] [Citation(s) in RCA: 46] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Abstract
PURPOSE A Phase I trial of cranial neutron capture therapy (NCT) was conducted at Harvard-MIT. The trial was designed to determine maximum tolerated NCT radiation dose to normal brain. METHODS AND MATERIALS Twenty-two patients with brain tumors were treated by infusion of boronophenylalanine-fructose (BPA-f) followed by exposure to epithermal neutrons. The study began with a prescribed biologically weighted dose of 8.8 RBE (relative biologic effectiveness) Gy, escalated in compounding 10% increments, and ended at 14.2 RBE Gy. BPA-f was infused at a dose 250-350 mg/kg body weight. Treatments were planned using MacNCTPlan and MCNP 4B. Irradiations were delivered as one, two, or three fields in one or two fractions. RESULTS Peak biologically weighted normal tissue dose ranged from 8.7 to 16.4 RBE Gy. The average dose to brain ranged from 2.7 to 7.4 RBE Gy. Average tumor dose was estimated to range from 14.5 to 43.9 RBE Gy, with a mean of 25.7 RBE Gy. CONCLUSIONS We have demonstrated that BPA-f-mediated NCT can be precisely planned and delivered in a carefully controlled manner. Subsequent clinical trials of boron neutron capture therapy at Harvard and MIT will be initiated with a new high-intensity, high-quality epithermal neutron beam.
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Affiliation(s)
- Matthew R Palmer
- Department of Radiology, Beth Israel Deaconess Medical Center, Harvard Medical School, Boston, MA 02115, USA.
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Kiger WS, Palmer MR, Riley KJ, Zamenhof RG, Busse PM. A pharmacokinetic model for the concentration of 10B in blood after boronophenylalanine-fructose administration in humans. Radiat Res 2001; 155:611-8. [PMID: 11260663 DOI: 10.1667/0033-7587(2001)155[0611:apmftc]2.0.co;2] [Citation(s) in RCA: 52] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/03/2022]
Abstract
An open two-compartment model has been developed for predicting (10)B concentrations in blood after intravenous infusion of the l-p-boronophenylalanine-fructose complex (BPA-F) in humans and derived from studies of pharmacokinetics in 24 patients in the Harvard-MIT Phase I clinical trials of BNCT. The (10)B concentration profile in blood exhibits a characteristic rise during the infusion to a peak of approximately 32 microg/g (for infusion of 350 mg/kg over 90 min) followed by a biphasic exponential clearance profile with half-lives of 0.34 +/- 0.12 and 9.0 +/- 2.7 h, due to redistribution and primarily renal elimination, respectively. The model rate constants k(1), k(2) and k(3) are 0.0227 +/- 0.0064, 0.0099 +/- 0.0027 and 0.0052 +/- 0.0016 min(-1), respectively, and the central compartment volume of distribution, V(1), is 0.235 +/- 0.042 kg/kg. The validity of this model was demonstrated by successfully predicting the average pharmacokinetic response for a cohort of patients who were administered BPA-F using an infusion schedule different from those used to derive the parameters of the model. Furthermore, the mean parameters of the model do not differ for cohorts of patients infused using different schedules.
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Affiliation(s)
- W S Kiger
- Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge, MA, USA
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Marek M, Flibor S, Burian J, Rataj J, Viererbl L. Optimization of the BNCT Filter. J NUCL SCI TECHNOL 2000. [DOI: 10.1080/00223131.2000.10874910] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Ye SJ. Boron self-shielding effects on dose delivery of neutron capture therapy using epithermal beam and boronophenylalanine. Med Phys 1999; 26:2488-93. [PMID: 10587238 DOI: 10.1118/1.598769] [Citation(s) in RCA: 19] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
Previous dosimetry studies for boron neutron capture therapy have often neglected the thermal neutron self-shielding effects caused by the 10B accumulation in the brain and the tumor. The neglect of thermal neutron flux depression, therefore, results in an overestimation of the actual dose delivery. The relevant errors are expected to be more pronounced when boronophenylalanine is used in conjunction with an epithermal neutron beam. In this paper, the boron self-shielding effects are calculated in terms of the thermal neutron flux depression across the brain and the dose delivered to the tumors. The degree of boron self-shielding is indicated by the difference between the thermal neutron fluxes calculated with and without considering a 10B concentration as part of the head phantom composition. The boron self-shielding effect is found to increase with increasing 10B concentrations and penetration depths from the skin. The calculated differences for 10B concentrations of 7.5-30 ppm are 2.3%-8.3% at 2.3 cm depth (depth of the maximum brain dose) and 4.6%-17% at 7.3 cm depth (the center of the brain). The additional self-shielding effects by the 10B concentration in a bulky tumor are investigated for a 3-cm-diam spherical tumor located either near the surface (3.3 cm depth) or at the center of the brain (7.3 cm depth) along the beam centerline. For 45 ppm of 10B in the tumor and 15 ppm of 10B in the brain, the dose delivered to the tumors is approximately 10% lower at 3.3 cm depth and 20% lower at the center of the brain, compared to the dose neglecting the boron self-shielding in transport calculations.
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Affiliation(s)
- S J Ye
- Department of Medical Physics, Rush University Medical Center, Chicago, Illinois 60612, USA
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Sakamoto S, Kiger WS, Harling OK. Sensitivity studies of beam directionality, beam size, and neutron spectrum for a fission converter-based epithermal neutron beam for boron neutron capture therapy. Med Phys 1999; 26:1979-88. [PMID: 10505888 DOI: 10.1118/1.598784] [Citation(s) in RCA: 30] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022] Open
Abstract
Sensitivity studies of epithermal neutron beam performance in boron neutron capture therapy are presented for realistic neutron beams with varying filter/moderator and collimator/delimiter designs to examine the relative importance of neutron beam spectrum, directionality, and size. Figures of merit for in-air and in-phantom beam performance are calculated via the Monte Carlo technique for different well-optimized designs of a fission converter-based epithermal neutron beam with head phantoms as the irradiation target. It is shown that increasing J/phi, a measure of beam directionality, does not always lead to corresponding monotonic improvements in beam performance. Due to the relatively low significance, for most configurations, of its effect on in-phantom performance and the large intensity losses required to produce beams with very high J/phi, beam directionality should not be considered an important figure of merit in epithermal neutron beam design except in terms of its consequences on patient positioning and collateral dose. Hardening the epithermal beam spectrum, while maintaining the specific fast neutron dose well below the inherent hydrogen capture dose, improves beam penetration and advantage depth and, as a desirable by-product, significantly increases beam intensity. Beam figures of merit are shown to be strongly dependent on beam size relative to target size. Beam designs with J/phi approximately 0.65-0.7, specific fast neutron doses of 2-2.6x10(-13) Gy cm2/n and beam sizes equal to or larger than the size of the head target produced the deepest useful penetration, highest therapeutic ratios, and highest intensities.
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Affiliation(s)
- S Sakamoto
- Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge 02139, USA
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Some recent trends and progress in the physics and biophysics of neutron capture therapy. PROGRESS IN NUCLEAR ENERGY 1999. [DOI: 10.1016/s0149-1970(99)00004-9] [Citation(s) in RCA: 16] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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