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Image obtained from the infrared camera during the target irradiation by a proton beam with a current of 1.4 mA. The dashed circle denotes the diameter of 30 mm.

Image obtained from the infrared camera during the target irradiation by a proton beam with a current of 1.4 mA. The dashed circle denotes the diameter of 30 mm.

Context in source publication

Context 1
... Fig. 3, the typical image of the FLIR T650SC infrared camera (FLIR, United States) is shown stretched vertically by a factor of . The dotted circle 30 mm in diameter is superimposed on the image. It is shown that the proton beam heats the area inside the diameter of 30 mm. Note that the light dots in the image are heated small metal droplets ...

Citations

... Since the space charge does not affect the transport of the proton beam [11], let us estimate the size of the proton beam on the surface of the lithium target, which is planned to be installed in a neighboring bunker at a distance of 10.7 m from the center of the accelerator. For an upper estimate, consider the most divergent beam obtained at 3 mA. ...
... The details of the studies that made it possible to achieve such parameters are presented in a review article [7] and in recent publications [8][9][10][11]. ...
... The spatial charge does not influence the transport of the proton beam [10], therefore, the proton beam can be transported relatively simply and without loss to a lithium target 10 cm in diameter in whatever position it is installed. So, with the bending magnet turned off, the size of the proton beam on the surface of the lithium target in position C is 20 mm, in position D-28 mm, E-38 mm (here the distance from the center of the accelerator to the target is 10.7 m). ...
Article
Full-text available
A compact accelerator-based neutron source has been proposed and created at the Budker Institute of Nuclear Physics in Novosibirsk, Russia. An original design tandem accelerator is used to provide a proton beam. The proton beam energy can be varied within a range of 0.6–2.3 MeV, keeping a high-energy stability of 0.1%. The beam current can also be varied in a wide range (from 0.3 mA to 10 mA) with high current stability (0.4%). In the device, neutron flux is generated as a result of the 7Li(p,n)7Be threshold reaction. A beam-shaping assembly is applied to convert this flux into a beam of epithermal neutrons with characteristics suitable for BNCT. A lot of scientific research has been carried out at the facility, including the study of blistering and its effect on the neutron yield. The BNCT technique is being tested in in vitro and in vivo studies, and the methods of dosimetry are being developed. It is planned to certify the neutron source next year and conduct clinical trials on it. The neutron source served as a prototype for a facility created for a clinic in Xiamen (China).
Book
Full-text available
Boron neutron capture therapy (BNCT) is a neutron-based technique that allows selective cancer treatment at the tumour cellular level. BNCT is especially suitable for the treatment of brain, head, neck and skin cancers. Using the reaction between a neutron and boron to selectively destroy cancer cells, BNCT is a treatment that differs radically from conventional radiotherapy and promises to become a more widely adopted option for cancer treatment. BNCT is undergoing a major resurgence of interest around the world as some recent progress in accelerator technology allows the procedure to be undertake in clinics. In addition, the approval of BNCT in Japan as a routine clinical treatment for certain tumour types offers valuable insights for other states considering a similar approach. This publication comprehensively reports on the current state of the science as well as the supporting technology. It covers accelerator-based neutron sources, beam design, physical dosimetry, facility design and operation, pharmaceuticals, radiobiology, dose calculation, treatment planning and clinical trials. It has been written to assist in decision making at the national level as well as offering practical guidance for all those involved in implementation and ongoing management of BNCT programmes. Please download a free copy at: https://www.iaea.org/publications/15339/advances-in-boron-neutron-capture-therapy
Preprint
Boron neutron capture therapy (BNCT) is a combination cancer therapy utilizing an external beam of neutrons of appropriate energies and a 10B-containing pharmaceutical that preferentially concentrates in tumour tissues of the patient. The nuclear reaction between the neutron and the boron nucleus generates an alpha particle and recoiling 7Li nucleus that create a high degree of localized damage to the tumour cell. This concept, while simple and first proposed in 1936 by Gordon Locher, has proven challenging to implement, and involves truly multidisciplinary teams. One difficulty in the past was that there were few neutron sources around the world of sufficient intensity and of the required energies for BNCT. The only neutron sources suitable were research reactors, which were distributed at universities and government laboratories around the world. Research reactors are not clinical environments, and, while many clinical trials were conducted and several centres reported encouraging results, the number of patients treated was small, and intercomparison of results from different centres not simple. In 2001, the IAEA issued ‘Current Status of Neutron Capture Therapy’ (TECDOC-1223), which summarized the state of the field based around reactor sources.