16 results on '"accelerator based neutron source"'
Search Results
2. Experimental test of neutron intensity monitor with isomer production reaction for p-Li neutron source for boron neutron capture therapy
- Author
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Shingo Tamaki, Yuuki Ohtani, Sachie Kusaka, Fuminobu Sato, and Isao Murata
- Subjects
boron neutron capture therapy (BNCT) ,neutron intensity monitor ,accelerator based neutron source ,p-Li reaction ,isomer/isomerization ,Plasma physics. Ionized gases ,QC717.6-718.8 ,Nuclear and particle physics. Atomic energy. Radioactivity ,QC770-798 - Abstract
IntroductionBoron Neutron Capture Therapy (BNCT) is a promising cancer therapy. At present, development of accelerator based neutron source (ABNS) is underway to be utilized as a neutron source instead of nuclear reactor. However, it is known that the neutron field formed with accelerators have different characteristics depending on kinds of accelerators. We thus have to characterize the field before practical use.MethodIn the authors’ group, various neutronics characterization devices have been developed for our p-Li based BNCT machine named CSePT. In this paper, three neutron intensity monitor foils with an isomer production reaction for several tens to 800 keV of the p-Li neutrons were proposed, i.e., 107Ag, 115In and 189Os.Result and DiscussionFrom the experimental test results, two activation foils of 107Ag and 115In were confirmed to be a possible candidate as the monitor. However, the isomer production cross sections of them should be examined for practical use.
- Published
- 2024
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3. EXTENDED MSM METHOD TO ESTIMATE THE REACTIVITY OF A SUB-CRITICAL CORE DRIVEN BY AN ACCELERATOR BASED NEUTRON SOURCE.
- Author
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Billebaud, A., Lecouey, J.-L., Chevret, T., Chabod, S., Doligez, X., Kochetkov, A., Krása, A., Lecolley, F.-R., Lehaut, G., Marie, N., Messaoudi, N., Uyttenhove, W., Vittiglio, G., Wagemans, J., Bécares, V., Villamarin, D., and Mellier, F.
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NUCLEAR reactor reactivity , *NEUTRON transport theory , *NUCLEAR fission , *NUCLEAR reactor cores , *NUCLEAR counters - Abstract
The Modified Source Multiplication method is used to determine an unknown reactivity level of a reactor from a known one if one has access to the detector counting for both levels when the reactor is fed by a constant neutron source like an Am-Be source. When available, an accelerator driven source, in continuous mode, can be useful as its intensity can be tunable and then adapted to the experimental conditions. However, in that case, the MSM technique must be extended to account for an external source whose intensity, energy and angular distributions can vary from one measurement to another. In this paper, this Modified Multi-Source Multiplication (MMSM) method is applied to measurements done during the FREYA project in the GUINEVERE facility, operated with the GENEPI-3C accelerator providing a mixture of (D,T) and (D,D) neutrons. The monitoring of these sources through the detection of the associated charged particles allows the calculation of the MMSM factors and the estimate of the reactivity values. The results are compared in different configurations with the reactivity obtained with an Am-Be source or in dynamic measurements performed with GENEPI-3C. Their excellent agreement shows the possibility of using such accelerator-based neutron sources for MSM measurements when they are correctly monitored. This is of great interest for deep sub-critical level characterization for which detector count rates per source neutrons might be low. [ABSTRACT FROM AUTHOR]
- Published
- 2021
- Full Text
- View/download PDF
4. Maxwell–Boltzmann-like neutron spectrum production for Maxwellian averaged cross sections measurements.
- Author
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Musacchio-González, Elizabeth, Mastinu, Pierfrancesco, Martín-Hernández, Guido, Porras, Ignacio, Centofante, Lisa, Arias de Saavedra, Fernando, Maran, Luca, Ruzzon, Alberto, and Lideo, Daniele
- Subjects
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NEUTRON temperature , *NEUTRONS , *TEMPERATURE of stars , *STELLAR spectra , *NEUTRON beams , *PROTON beams - Abstract
Over the years, Maxwellian Averaged Cross Sections (MACS) have been measured by neutron activation, providing a neutron energy spectrum resembling the one found inside the stars. Recently, a new method has been proposed to produce stellar spectra at different stellar temperatures (a Maxwell–Boltzmann neutron energy distribution), employing the 7 Li(p,n) 7 Be reaction. The method is based on the idea of shaping the proton beam energy to shape the neutron beam spectrum. This method was applied to obtain a well-reproduced Maxwell–Boltzmann neutron spectrum (MBNS) at k T = 28 keV. An initial proton energy of 3170 keV and an aluminum foil as a proton energy shaper were employed. Differential angular neutron energy distributions from 0 to 90 degrees in 10 ∘ steps were measured to obtain the 0 ∘ –90 ∘ integrated neutron spectrum over a neutron flight path of 50 cm. This manuscript reports on the measurement results, confirming the method's capability, and suggests the approach for producing a high-quality MBNS at k T = 28 keV. [ABSTRACT FROM AUTHOR]
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- 2024
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5. RF structure design of the China Material Irradiation Facility RFQ.
- Author
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Li, Chenxing, He, Yuan, Xu, Xianbo, Zhang, Zhouli, Wang, Fengfeng, Dou, Weiping, Wang, Zhijun, and Wang, Tieshan
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QUADRUPOLES , *STRUCTURAL design , *NEUTRON radiography , *FUSION reactors , *NANOFABRICATION - Abstract
The radio frequency structure design of the radio frequency quadrupole (RFQ) for the front end of China Material Irradiation Facility (CMIF), which is an accelerator based neutron irradiation facility for fusion reactor material qualification, has been completed. The RFQ is specified to accelerate 10 mA continuous deuteron beams from the energies of 20 keV/u to 1.5 MeV/u within the vane length of 5250 mm. The working frequency of the RFQ is selected to 162.5 MHz and the inter-vane voltage is set to 65 kV. Four-vane cavity type is selected and the cavity structure is designed drawing on the experience of China Initiative Accelerator Driven System (CIADS) Injector II RFQ. In order to reduce the azimuthal asymmetry of the field caused from errors in fabrication and assembly, a frequency separation between the working mode and its nearest dipole mode is reached to 17.66 MHz by utilizing 20 pairs of π -mode stabilizing loops (PISLs) distributed along the longitudinal direction with equal intervals. For the purpose of tuning, 100 slug tuners were introduced to compensate the errors caused by machining and assembly. In order to obtain a homogeneous electrical field distribution along cavity, vane cutbacks are introduced and output endplate is modified. Multi-physics study of the cavity with radio frequency power and water cooling is performed to obtain the water temperature tuning coefficients. Through comparing to the worldwide CW RFQs, it is indicated that the power density of the designed structure is moderate for operation under continuous wave (CW) mode. [ABSTRACT FROM AUTHOR]
- Published
- 2017
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6. Conceptual design of a target station using a 30-MeV cyclotron accelerator for the basic study of boron neutron capture therapy at KURNS.
- Author
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Nakamura, R., Hino, M., Tanaka, H., Kuriyama, Y., and Iwashita, Y.
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THERMAL neutrons , *BORON-neutron capture therapy , *HEAT flux , *CONCEPTUAL design , *NEUTRON irradiation , *CYCLOTRONS - Abstract
A new target station that generates a thermal neutron field based on a 30-MeV proton accelerator was designed for the basic study of boron neutron capture therapy (BNCT). The calculated thermal neutron fluxes at the sample regions under free air conditions reached 2.84 × 109 [n/cm2/s]. The fast neutron and gamma ray dose rates per thermal neutron flux in several regions were on the order of 10−13 [ Gy ⋅ cm 2 ]. The beam characteristics were found to be closer to those of the heavy-water neutron irradiation facility of Kyoto University Research Reactor, which is an established facility in BNCT research. In addition, the shielding size for the new target station was realistically estimated for long-term beam operation. [ABSTRACT FROM AUTHOR]
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- 2022
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7. Neutron characterization study for D–T, p-7Li neutron sources with new BCA based direct collision coupling method.
- Author
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Wang, Guan-bo, Yang, Xin, Qian, Da-zhi, Li, Run-dong, and Tang, Bin
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NEUTRON sources , *NUCLEAR research , *NUCLEOSYNTHESIS , *ANGULAR distribution (Nuclear physics) , *COLLISIONS (Nuclear physics) , *SCATTERING cross sections (Physics) - Abstract
Abstract: The T(D,n)4He and 7Li(p,n)7Be neutron sources have been used for decades in nuclear physics research, stellar nucleosynthesis research and neutron therapy research. In this work, the neutron characterization including neutron yield, spectra, and angular distribution for D–T and p-7Li sources have been studied with our new binary collision approximation (BCA) based direct collision coupling method. Distinguished from the traditional path integration method for getting the neutron weight, the new model establishes a relationship between the scattering cross section and the impact parameter, which allows the secondary neutron generation carrying out jointly with ions BCA tracking. The experimental measurements of neutron characterizations have been employed for these two reactions, and the new algorithm is validated. [Copyright &y& Elsevier]
- Published
- 2014
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8. Project for the development of the linac based NCT facility in University of Tsukuba.
- Author
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Kumada, H., Matsumura, A., Sakurai, H., Sakae, T., Yoshioka, M., Kobayashi, H., Matsumoto, H., Kiyanagi, Y., Shibata, T., and Nakashima, H.
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LINEAR accelerators , *BORON-neutron capture therapy , *PROTON accelerators , *RADIO frequency , *QUADRUPOLES - Abstract
Abstract: A project team headed by University of Tsukuba launched the development of a new accelerator based BNCT facility. In the project, we have adopted Radio-Frequency Quadrupole (RFQ)+Drift Tube Linac (DTL) type linac as proton accelerators. Proton energy generated from the linac was set to 8MeV and average current was 10mA. The linac tube has been constructed by Mitsubishi Heavy Industry Co. For neutron generator device, beryllium is selected as neutron target material; high intensity neutrons are generated by the reaction with beryllium and the 80kW proton beam. Our team chose beryllium as the neutron target material. At present beryllium target system is being designed with Monte-Carlo estimations and heat analysis with ANSYS. The neutron generator consists of moderator, collimator and shielding. It is being designed together with the beryllium target system. We also acquired a building in Tokai village; the building has been renovated for use as BNCT treatment facility. It is noteworthy that the linac tube had been installed in the facility in September 2012. In BNCT procedure, several medical devices are required for BNCT treatment such as treatment planning system, patient positioning device and radiation monitors. Thus these are being developed together with the linac based neutron source. For treatment planning system, we are now developing a new multi-modal Monte-Carlo treatment planning system based on JCDS. The system allows us to perform dose estimation for BNCT as well as particle radiotherapy and X-ray therapy. And the patient positioning device can navigate a patient to irradiation position quickly and properly. Furthermore the device is able to monitor movement of the patient׳s position during irradiation. [Copyright &y& Elsevier]
- Published
- 2014
- Full Text
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9. Extended MSM method to estimate the reactivity of a sub-critical core driven by an accelerator based neutron source
- Author
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François-René Lecolley, G. Lehaut, G. Vittiglio, Nadia Messaoudi, X. Doligez, N. Marie, A. Krasa, W. Uyttenhove, D. Villamarin, J. Wagemans, T. Chevret, J.L. Lecouey, A. Kochetkov, F. Mellier, V. Bécares, S. Chabod, A. Billebaud, Laboratoire de Physique Subatomique et de Cosmologie (LPSC), Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Grenoble Alpes (UGA)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP ), Université Grenoble Alpes (UGA), Laboratoire de physique corpusculaire de Caen (LPCC), Université de Caen Normandie (UNICAEN), Normandie Université (NU)-Normandie Université (NU)-École Nationale Supérieure d'Ingénieurs de Caen (ENSICAEN), Normandie Université (NU)-Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3), AREVA NP Lyon, Institut de Physique Nucléaire d'Orsay (IPNO), Centre National de la Recherche Scientifique (CNRS)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Université Paris-Sud - Paris 11 (UP11), Centre d'Etude de l'Energie Nucléaire (SCK-CEN), Centro de Investigaciones Energéticas Medioambientales y Tecnológicas [Madrid] (CIEMAT), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Normandie Université (NU)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS), and Université Paris-Sud - Paris 11 (UP11)-Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)
- Subjects
Physics ,ads ,[PHYS.PHYS]Physics [physics]/Physics [physics] ,010308 nuclear & particles physics ,QC1-999 ,Detector ,msm method ,[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex] ,01 natural sciences ,Charged particle ,Computational physics ,Core (optical fiber) ,reactivity monitoring ,0103 physical sciences ,Neutron source ,Neutron ,Multiplication ,010306 general physics ,accelerator based neutron source ,Energy (signal processing) ,Intensity (heat transfer) - Abstract
ISBN 978-1-5272-6447-2; International audience; The Modified Source Multiplication method is used to determine an unknown reactivity level of a reactor from a known one if one has access to the detector counting for both levels when the reactor is fed by a constant neutron source like an Am-Be source. When available, an accelerator driven source, in continuous mode, can be useful as its intensity can be tunable and then adapted to the experimental conditions. However, in that case, the MSM technique must be extended to account for an external source whose intensity, energy and angular distributions can vary from one measurement to another. In this paper, this Modified Multi-Source Multiplication (MMSM) method is applied to measurements done during the FREYA project in the GUINEVERE facility, operated with the GENEPI-3C accelerator providing a mixture of (D,T) and (D,D) neutrons. The monitoring of these sources through the detection of the associated charged particles allows the calculation of the MMSM factors and the estimate of the reactivity values. The results are compared in different configurations with the reactivity obtained with an Am-Be source or in dynamic measurements performed with GENEPI-3C. Their excellent agreement shows the possibility of using such accelerator-based neutron sources for MSM measurements when they are correctly monitored. This is of great interest for deep sub-critical level characterization for which detector count rates per source neutrons might be low.
- Published
- 2020
- Full Text
- View/download PDF
10. A Project of Boron Neutron Capture Therapy System based on a Proton Linac Neutron Source.
- Author
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Kiyanagi, Yoshikai, Asano, Kenji, Arakawa, Akihiro, Fukuchi, Shin, Hiraga, Fujio, Kimura, Kenju, Kobayashi, Hitoshi, Kubota, Michio, Kumada, Hiroaki, Matsumoto, Hiroshi, Matsumoto, Akira, Sakae, Takeji, Saitoh, Kimiaki, Shibata, Tokushi, and Yoshioka, Masakazu
- Subjects
BORON-neutron capture therapy ,NEUTRON sources ,HEAVY ion accelerators ,NEUTRON-proton interactions ,RADIOACTIVITY ,PROTON beams ,REACTOR moderators - Abstract
Abstract: At present, the clinical trials of Boron Neutron Capture Therapy (BNCT) are being performed at research reactor facilities. However, an accelerator based BNCT has a merit that it can be built in a hospital. So, we just launched a development project for the BNCT based on an accelerator in order to establish and to spread the BNCT as an effective therapy in the near future. In the project, a compact proton linac installed in a hospital will be applied as a neutron source, and energy of the proton beam is planned to be less than about 10 MeV to reduce the radioactivity. The BNCT requires epithermal neutron beam with an intensity of around 1x109 (n/cm2/sec) to deliver the therapeutic dose to a deeper region in a body and to complete the irradiation within an hour. From this condition, the current of the proton beam required is estimated to be a few mA on average. Enormous heat deposition in the target is a big issue. We are aiming at total optimization of the accelerator based BNCT from the linac to the irradiation position. Here, the outline of the project is introduced and the moderator design is presented. [Copyright &y& Elsevier]
- Published
- 2012
- Full Text
- View/download PDF
11. Study of the effect of high dose rate on tissue equivalent proportional counter microdosimetric measurements in mixed photon and neutron fields
- Author
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Aslam, Qashua, N., and Waker, A.J.
- Subjects
- *
RADIATION doses , *MICRODOSIMETRY , *PHOTON beams , *NEUTRONS , *FIELD theory (Physics) , *ENERGY transfer , *SPECTRUM analysis - Abstract
Abstract: This study describes the measurement of lineal energy spectra carried out with a 5.1cm (2in.) diameter spherical tissue equivalent proportional counter (TEPC) simulating 2μm tissue equivalent (TE) site diameter in low energy mixed photon–neutron fields with varying dose rates generated by employing the McMaster University 1.25MV double stage Tandetron accelerator. The 7Li (p, n) 7Be reaction was employed to generate a variety of mixed fields of photons and low energy neutrons using proton beam energy ranging 1.89–2.56MeV. The dose rate at a given beam energy was varied by changing the beam current. Dose rates that resulted in dead times as high as 75% were employed to study the effect of dose rate on quality, microdosimetric averages (y¯ F and y¯ D), absorbed dose and dose equivalent. We have observed that high dose rates due to both photons and neutrons in a mixed field of radiation result in pile up of pulses and distort the lineal energy spectrum measured under these conditions. The pile up effect and hence the distortion in the lineal energy spectrum becomes prominent with dose rates, which result in dead times larger than 25% for the high linear energy transfer (LET) radiation component. Intense neutron fields, which may amount to 75% dead time, could result in a 50% or even larger increase in the values of the microsdosimetric averages and the neutron quality factor. This study demonstrates moderate dose rates that do not result in dead times of more than 20–25% due to either of the component radiation or due to both components of mixed field radiation generate results that are acceptable for radiation monitoring. [Copyright &y& Elsevier]
- Published
- 2011
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12. An experimental study of the microdosimetric response of a graphite walled proportional counter in low energy neutron fields
- Author
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Waker, A.J. and Aslam
- Subjects
- *
MICRODOSIMETRY , *GRAPHITE , *NEUTRON beams , *PHYSICS experiments , *NUCLEAR counters , *NEUTRON sources , *MEASUREMENT - Abstract
Abstract: This study describes the measurement of lineal energy spectra carried out with a graphite walled proportional counter (GPC) simulating 1μm tissue equivalent (TE) site diameter in low energy neutron fields generated by employing the McMaster University 1.25MV double stage Tandetron accelerator. Experiments were carried out for neutron beams of mean energies extending from 34 to 354keV in direct neutron beams from the 7Li target using proton beam energies ranging from 1.89 to 2.56MeV. We have observed a continuously increasing trend in microdosimetric averages, and , and the ICRP 60 based quality factor, Q, with an increase in neutron energy. It is interesting to note that standard tissue equivalent proportional counters (TEPCs) give rise to a similar trend for these microdosimetric quantities of interest in the same energy range. Quantitatively, these quantities are also comparable to those obtained with standard TEPCs. This implies that at the microdosimetric level in the neutron energy range we employed in this study, the pattern of average energy deposited by ‘starter’ and ‘insider’ proton recoil events in the gas is similar to those generated cumulatively by ‘crosser’ and ‘stopper’ events originating from the counter wall plus ‘starter’ and ‘insider’ recoil events originating in the sensitive volume of a TEPC. This suggests that the average energy deposition per event in the wall of a TEPC counter is the same as in the counting gas itself, which confirms the similarity of the composition and mass stopping power of two media, i.e., TE wall and TE gas, used in neutron dosimetric measurements. [Copyright &y& Elsevier]
- Published
- 2011
- Full Text
- View/download PDF
13. Liquid Li based neutron source for BNCT and science application.
- Author
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Horiike, H., Murata, I., Iida, T., Yoshihashi, S., Hoashi, E., Kato, I., Hashimoto, N., Kuri, S., and Oshiro, S.
- Subjects
- *
BORON-neutron capture therapy , *LITHIUM , *NEUTRON sources , *HEAT transfer , *RADIATION dosimetry - Abstract
Liquid lithium (Li) is a candidate material for a target of intense neutron source, heat transfer medium in space engines and charges stripper. For a medical application of BNCT, epithermal neutrons with least energetic neutrons and γ-ray are required so as to avoid unnecessary doses to a patient. This is enabled by lithium target irradiated by protons at 2.5 MeV range, with utilizing the threshold reaction of 7 Li(p,n) 7 Be at 1.88 MeV. In the system, protons at 2.5 MeV penetrate into Li layer by 0.25 mm with dissipating heat load near the surface. To handle it, thin film flow of high velocity is important for stable operation. For the proton accelerator, electrostatic type of the Schnkel or the tandem is planned to be employed. Neutrons generated at 0.6 MeV are gently moderated to epithermal energy while suppressing accompanying γ-ray minimum by the dedicated moderator assembly. [ABSTRACT FROM AUTHOR]
- Published
- 2015
- Full Text
- View/download PDF
14. Mock-up experiment at Birmingham University for BNCT project of Osaka University – Neutron flux measurement with gold foil.
- Author
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Tamaki, S., Sakai, M., Yoshihashi, S., Manabe, M., Zushi, N., Murata, I., Hoashi, E., Kato, I., Kuri, S., Oshiro, S., Nagasaki, M., and Horiike, H.
- Subjects
- *
BORON-neutron capture therapy , *NEUTRON flux , *GOLD foil , *NEUTRON sources , *NEUTRON beams - Abstract
Mock-up experiment for development of accelerator based neutron source for Osaka University BNCT project was carried out at Birmingham University, UK. In this paper, spatial distribution of neutron flux intensity was evaluated by foil activation method. Validity of the design code system was confirmed by comparing measured gold foil activities with calculations. As a result, it was found that the epi-thermal neutron beam was well collimated by our neutron moderator assembly. Also, the design accuracy was evaluated to have less than 20% error. [ABSTRACT FROM AUTHOR]
- Published
- 2015
- Full Text
- View/download PDF
15. Neutron spectrometry of a liquid Lithium based (p, n) beam at SARAF facility using the broad-energy range directional spectrometer CYSP
- Author
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Roberto Bedogni, L. Weissman, Marco Costa, A. Kreisel, D. Kijel, Andrea Pola, V. Monti, J.M. Gómez-Ros, and S. Halfon
- Subjects
Nuclear and High Energy Physics ,Physics::Instrumentation and Detectors ,Instrumentation ,Accelerator based neutron source ,01 natural sciences ,030218 nuclear medicine & medical imaging ,Nuclear physics ,03 medical and health sciences ,0302 clinical medicine ,0103 physical sciences ,Neutron ,FRUIT unfolding ,Nuclear Experiment ,CYSP ,Liquid lithium target liLiT ,Neutron spectrometry ,SARAF ,010302 applied physics ,Physics ,Range (particle radiation) ,Spectrometer ,Neutron radiation ,SPHERES ,Accelerator based neutron source, CYSP, FRUIT unfolding, Liquid lithium target liLiT, Neutron spectrometry, SARAF ,Energy (signal processing) ,Beam (structure) - Abstract
An intense neutron beam produced via 7Li(p, n)7 Be reaction on a newly developed high-power liquid Lithium target (LiLiT) is available at SARAF (Soreq Applied Research Accelerator Facility) facility, Israel. Its spectrum was determined using the CYSP (CYlindrical SPectrometer), a new directional neutron spectrometer which incorporates the functionality of the Bonner spheres in a single cylindrical moderator. The advantages of this spectrometer are that the neutron spectrum is derived in only one exposure, and that its directional response is not affected by room- and air-scattered neutrons. The data from the CYSP spectrometer were analysed using the FRUIT unfolding code.
- Published
- 2018
16. A Project of Boron Neutron Capture Therapy System based on a Proton Linac Neutron Source
- Author
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Hiroshi Matsumoto, Hiroaki Kumada, Takeji Sakae, Tokushi Shibata, Kenji Asano, Shin Fukuchi, Fujio Hiraga, Masakazu Yoshioka, Michio Kubota, Hitoshi Kobayashi, Akihiro Arakawa, Y. Kiyanagi, Akira Matsumoto, Kenju Kimura, and Kimiaki Saitoh
- Subjects
Materials science ,Proton ,Accelerator based neutron source ,Nuclear engineering ,chemistry.chemical_element ,Boron Neutron Capture Therapy ,Physics and Astronomy(all) ,Epithermal neutron ,Linear particle accelerator ,Neutron capture ,chemistry ,Proton linac ,Neutron source ,Moderator-reflector systemn ,Research reactor ,Boron ,Beam (structure) - Abstract
At present, the clinical trials of Boron Neutron Capture Therapy (BNCT) are being performed at research reactor facilities. However, an accelerator based BNCT has a merit that it can be built in a hospital. So, we just launched a development project for the BNCT based on an accelerator in order to establish and to spread the BNCT as an effective therapy in the near future. In the project, a compact proton linac installed in a hospital will be applied as a neutron source, and energy of the proton beam is planned to be less than about 10 MeV to reduce the radioactivity. The BNCT requires epithermal neutron beam with an intensity of around 1x109 (n/cm2/sec) to deliver the therapeutic dose to a deeper region in a body and to complete the irradiation within an hour. From this condition, the current of the proton beam required is estimated to be a few mA on average. Enormous heat deposition in the target is a big issue. We are aiming at total optimization of the accelerator based BNCT from the linac to the irradiation position. Here, the outline of the project is introduced and the moderator design is presented.
- Published
- 2012
- Full Text
- View/download PDF
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