Head and neck (HN) cancer is an endemic disease in Taiwan, China. Locally recurrent HN cancer after full-dose irradiation poses a therapeutic challenge, and boron neutron capture therapy (BNCT) may be a solution that could provide durable local control with tolerable toxicity. The Tsing-Hua Open Pool Reactor (THOR) at National Tsing-Hua University in Hsin-Chu, provides a high-quality epithermal neutron source for basic and clinical BNCT research. Our first clinical trial, entitled "A phase I/II trial of boron neutron capture therapy for recurrent head and neck cancer at THOR", was carried out between 2010 and 2013. A total of 17 patients with 23 recurrent HN tumors who had received high-dose photon irradiation were enrolled in the study. The fructose complex of L-boronophenylalanine was used as a boron carrier, and a two-fraction BNCT treatment regimen at 28-day intervals was used for each patient. Toxicity was acceptable, and although the response rate was high (12/17), re-recurrence within or near the radiation site was common. To obtain better local control, another clinical trial entitled "A phase I/II trial of boron neutron capture therapy combined with image-guided intensity-modulated radiotherapy (IG-IMRT) for locally recurrent HN cancer" was initiated in 2014. The first administration of BNCT was performed according to our previous protocol, and IG-IMRT was initiated 28 days after BNCT. As of May 2017, seven patients have been treated with this combination. The treatment-related toxicity was similar to that previously observed with two BNCT applications. Three patients had a complete response, but locoregional recurrence was the major cause of failure despite initially good responses. Future clinical trials combining BNCT with other local or systemic treatments will be carried out for recurrent HN cancer patients at THOR.
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http://dx.doi.org/10.1186/s40880-018-0295-y | DOI Listing |
Appl Radiat Isot
December 2024
Division of Quantum and Radiation Engineering, Graduate School of Engineering, Osaka Metropolitan University, 1-2 Gakuen-cho, Naka-ku, Sakai, Osaka, 599-8570, Japan.
A novel anticoincidence detector is proposed for the measurement of 478 keV gamma radiation for evaluation of boron neutron capture therapy. The Compton continuum around the target photopeak position is effectively suppressed by measuring only the Compton gamma rays scattered at small angles from the primary detector. A numerical evaluation using Monte Carlo simulations estimated an 80% reduction in counts, and the developed prototype detector showed 4% suppression of the Compton continuum of cobalt-60 gamma rays.
View Article and Find Full Text PDFAppl Radiat Isot
December 2024
Bingöl University, Faculty of Arts and Science, Department of Physics, 12000, Bingöl, Türkiye.
In this study, the gamma radiation shielding properties of concrete samples reinforced with 10%, 20%, 30%, 40% and 50% of the cement weight of brass alloy were investigated. To test gamma shielding performance of the samples, mass and linear attenuation coefficients, half and tenth value layers, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and Monte Carlo simulations (GEANT4 and FLUKA). The studies were performed at 11 different gamma energies that range from 59.
View Article and Find Full Text PDFACS Med Chem Lett
December 2024
School of Pharmacy, University of Eastern Finland, P.O. Box 1627, FI-70211 Kuopio, Finland.
This research investigates boronated tryptophans as potential boron delivery agents for boron neutron capture therapy (BNCT) of cancer. We synthesized both enantiomers of 5- and 6-boronotryptophans ( and ) using simple and inexpensive methods. Their uptake was assessed in two human cancer cell lines, CAL27 (head and neck cancer) and U87-MG (brain cancer), and compared to l--boronophenylalanine (l-BPA) as a reference.
View Article and Find Full Text PDFMed Res Rev
December 2024
Sunshine Lake Pharma Co. Ltd., Dongguan, China.
Targeted charged alpha- and beta-particle therapies are currently being used in clinical radiation treatments as newly developed methods for either killing or controlling tumor cell growth. The alpha particles can be generated either through a nuclear decay reaction or in situ by a nuclear fission reaction such as the boron neutron capture reaction. Different strategies have been employed to improve the selectivity and delivery of radiation dose to tumor cells based on the source of the clinically used alpha particles.
View Article and Find Full Text PDFBiomed Phys Eng Express
December 2024
Shandong Key Laboratory of Neutron Science and Technology, International Academy of Neutron Science, Qingdao 266199, People's Republic of China.
In this paper, we propose the design of extending collimators aimed at reducing the radiation dose received by patients with normal tissues and protecting organs at risk in Boron Neutron Capture Therapy (BNCT). Three types of extended collimators are studied: Type 1, which is a traditional design; Type 2, which is built upon Type 1 by incorporating additional polyethylene material containing lithium fluoride (PE(LiF)); Type 3, which adds lead (Pb) to Type 1. We evaluated the dose distribution characteristics of the above-extended collimators using Monte Carlo methods simulations under different configurations: in air, in a homogeneous phantom, and a humanoid phantom model.
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