Neutron capture therapy
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IEEE International Conference on Plasma Science (ICOPS) is an annual conference coordinated by the Plasma Science and Application Committee (PSAC) of the IEEE Nuclear & Plasma Sciences Society.
Meeting of academia and research professionals to discuss reliability challenges
All areas of ionizing radiation detection - detectors, signal processing, analysis of results, PET development, PET results, medical imaging using ionizing radiation
Particle accelerator science and technology
EUROCON is a flagship event of the IEEE Region 8 (Europe, Middle East and Africa) held every two years in a different country with participants from all over the world. EUROCON is a major international forum for the exchange of ideas, theory basics, design methodologies, techniques and experimental results between academia, research institutions and practitioners from industry. It has achieved a considerable success during the past 17 editions in all fields of electrical and electronic engineering, ICT and computer science covered by IEEE Societies: Aerospace and Electronic Systems; Antennas and Propagation; Broadcast Technology; Circuits and Systems; Communications; Components, Packaging, and Manufacturing Technology; Computational Intelligence; Computer Engineering; Consumer Electronics; Control Systems; Dielectrics and Electrical Insulation; Education; Electron Devices; Electromagnetic Compatibility; Engineering in Medicine and Biology; Geoscience and Remote Sensing;
Contains articles on the applications and other relevant technology. Electronic applications include analog and digital circuits employing thin films and active devices such as Josephson junctions. Power applications include magnet design as well asmotors, generators, and power transmission
Both general and technical articles on current technologies and methods used in biomedical and clinical engineering; societal implications of medical technologies; current news items; book reviews; patent descriptions; and correspondence. Special interest departments, students, law, clinical engineering, ethics, new products, society news, historical features and government.
Imaging methods applied to living organisms with emphasis on innovative approaches that use emerging technologies supported by rigorous physical and mathematical analysis and quantitative evaluation of performance.
All aspects of the theory and applications of nuclear science and engineering, including instrumentation for the detection and measurement of ionizing radiation; particle accelerators and their controls; nuclear medicine and its application; effects of radiation on materials, components, and systems; reactor instrumentation and controls; and measurement of radiation in space.
2017 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2017
In medical radioisotope (RI) production by accelerator neutron, double- differential thick-target neutron yield (DDTTNY) is necessary to be measured to estimate production amount and its radioactive and isotopic purity. We adopted the multiple-foil activation method for the measurement. The DDTTNY should be derived by an unfolding technique from measured numbers of produced atoms via the activation reactions. We have developed ...
25th International Vacuum Nanoelectronics Conference, 2012
Here we report brush-type carbon nanotubes (BCNT) film, which is combined with graphene and carbon nanotube (CNT) array, as cathode on transparent substrate. Prepared by pyrolysis, vertically aligned CNT (VACNT) arrays are covered by a few layer graphene sheets like thin blankets. There are both good electrical and mechanical connections between VACNT arrays and graphene sheets. Transparent field emission cathode ...
IEEE Nuclear Science Symposuim & Medical Imaging Conference, 2010
For measurement of spatial distribution of epithermal neutron source in BNCT, we propose an epithermal neutron camera based on a gas electron multiplier (GEM) and the filter that has a resonance in epithermal energy region. A prototype detector that consisted of GEM with a neutron to charged particle converter of <sup>10</sup>B and a resonance filter of Ag was constructed. Difference ...
IEEE Transactions on Nuclear Science, 1982
Digest of Technical Papers. 12th IEEE International Pulsed Power Conference. (Cat. No.99CH36358), 1999
In this paper, the authors discuss an epithermal neutron source suitable for the boron neutron capture therapy (BNCT) of tumors based on the /sup 7/Li(p,n)/sup 7/Be reaction. To realize this neutron source, a 5 TW pulse generator, a high power proton diode, and an appropriate target arrangement, all capable to produce up to 500 pulses in a burst mode are ...
Nao Robot Therapy with Mentally Impaired Individuals - Ana Freire, António Valente and Vítor Filipe
EMBC 2011-Course-Virtual Reality and Robotics in Neurorehabilitation-Susan Fasoli
ICRA 2020: Designing personalized interactions of a socially assistive robot for stroke rehabilitation therapy
Perpendicular magnetic anisotropy: From ultralow power spintronics to cancer therapy
EMBC 2011 -Keynote (Women in Engineering Program) Re-engineering the War on Cancer: A Call to Action for Personalized Medicine -Mara G. Aspinall
Real-Time, Triggering, & Signal Capture for Agile and Elusive Signals (2)
A Harmonic-Selective Wireless Full-Band-Capture Receiver with Digital Harmonic Rejection Calibration: RFIC INteractive Forum 2017
Applying Control Theory to the Design of Cancer Therapy
Micro-Apps 2013: Real-Time, Triggering, & Signal Capture for Agile and Elusive Signals
EPICS In IEEE Spotlight - NJIT 2016 Project
Analog to Digital Traits
The Use of Robotic and Advanced Technology in Neurorehabilitation
Capture, Recognition, and Imitation of Anthropomorphic Motion
Comparing Modern Multiport VNA vs. Conventional Switch-based VNA: MicroApps 2015 - Keysight Technologies
Sean Sliger of Neuropace accepts the IEEE Spectrum Technology in the Service of Society Award - Honors Ceremony 2016
The New Gene Therapy: CRISPR CAS-9 and the Future of Medicine: IEEE VICS 2018
Roozbeh Ghaffari of MC10 accepts the IEEE Spectrum Emerging Technology Award - Honors Ceremony 2016
Low Power Image Recognition: The Challenge Continues
IEEE Brain: Working With Darpa
In medical radioisotope (RI) production by accelerator neutron, double- differential thick-target neutron yield (DDTTNY) is necessary to be measured to estimate production amount and its radioactive and isotopic purity. We adopted the multiple-foil activation method for the measurement. The DDTTNY should be derived by an unfolding technique from measured numbers of produced atoms via the activation reactions. We have developed an unfolding code using artificial neural network (ANN) which requires no initial guess spectrum and no human-inducible convergence condition which are required for conventional unfolding methods. To demonstrate the ability to derive DDTTNY by the ANN unfolding code, we input numbers of produced atoms obtained by a multiple-foil activation experiment conducted at Kyushu University Tandem Laboratory. The resultant DDTTNY is compared with that by GRAVEL code, which is one of the conventional codes. Since there is no large discrepancy, we found that the ANN unfolding code has same ability to GRAVEL code even no initial guess spectrum was used.
Here we report brush-type carbon nanotubes (BCNT) film, which is combined with graphene and carbon nanotube (CNT) array, as cathode on transparent substrate. Prepared by pyrolysis, vertically aligned CNT (VACNT) arrays are covered by a few layer graphene sheets like thin blankets. There are both good electrical and mechanical connections between VACNT arrays and graphene sheets. Transparent field emission cathode is built by transferring the BCNT film upside down to glass substrate. Taking BCNT roots as field emitters, we found that they have lower threshold field, higher emission current and better luminescence uniformity than that of as-grown VACNT emitters. BCNT film could improve electron transport properties from CNT emitters to substrate with the help of a few layer graphene sheets. BCNT films have a promising future in flexible devices.
For measurement of spatial distribution of epithermal neutron source in BNCT, we propose an epithermal neutron camera based on a gas electron multiplier (GEM) and the filter that has a resonance in epithermal energy region. A prototype detector that consisted of GEM with a neutron to charged particle converter of <sup>10</sup>B and a resonance filter of Ag was constructed. Difference in the response function between with and without the resonance filter was found in the epithermal region as a clear resonance dip, therefore the epithermal neutron detection with the prototype detector was successfully demonstrated.
In this paper, the authors discuss an epithermal neutron source suitable for the boron neutron capture therapy (BNCT) of tumors based on the /sup 7/Li(p,n)/sup 7/Be reaction. To realize this neutron source, a 5 TW pulse generator, a high power proton diode, and an appropriate target arrangement, all capable to produce up to 500 pulses in a burst mode are required. Unless a very accurate control of the proton energy can be achieved, operation close to the reaction threshold, although leading to a higher useful neutron flux, is not practicable. It is therefore proposed to use a 2.5 MeV proton beam. A new target needs to be injected after every pulse. With a repetition rate of 1 pulse per second, a treatment time of less than 10 minutes can be achieved.
At Kyoto University Research Reactor Institute(KURRI), we installed a Cyclotron-Based Epithermal Neutron Source(C-BENS) for Boron Neutron Capture Therapy(BNCT). C-BENS consists of a cyclotron accelerator that can provide a ~ 1000 μA, 30 MeV proton beam, a neutron production beryllium target and the moderator that can reduce the energy of fast neutrons to an effective energy range. C-BENS can provide epithermal neutron flux of 1.2 × 109(cm-2s-1) larger than that of conventional reactor-based neutron sources which have been using for clinical trials of BNCT. During irradiation of BNCT, it is important to detect neutron flux up to 109(cm-2s-1). Now we have been developing the real- time neutron flux monitor with the characteristics such as the resistance of radiation damage and low attenuation rate in optical fiber. To evaluate detection system, the thermal neutron irradiation field using C-BENS in water phantom with the thermal neutron flux from 108to 109was used. The good linearity between the detector counts and thermal neutron flux was obtained.
We have been developed an epithermal neutron source for boron neutron capture therapy(BNCT), consisting of a cyclotron accelerator that can provide a ~ 1 mA, 30 MeV proton beam, a neutron production beryllium target and the moderator that can reduce the energy of fast neutrons to an effective energy range. In order to validate the simulations, we measured the depth distribution of the thermal neutron flux in water phantom located at the treatment position. The measured results were compared with the simulations using the MCNPX Monte Carlo code. The good agreement between the simulations and measurements was shown. The thermal neutron flux with the proton current of 430 ¿A was 7.4 × 10<sup>8</sup> (neutrons cm<sup>-2</sup> s<sup>-1</sup>) at the depth of around 20 mm in the water phantom. This intensity corresponds to the neutron source of Kyoto University Research Reactor (KUR), at which 275 clinical trials of BNCT have been performed. We experimentally confirmed that our cyclotron based neutron source can use for clinical trials of BNCT.
In the present work, an in-depth study of methane adsorption on bamboo-like carbon nanotubes (BCNTs) has been accomplished. The structures of (12,0) and (5,5) BCNTs have been designed and optimized using Quantumwise Atomistix Toolkit software package. The main reason behind employing BCNTs is their unique geometry i.e. the presence of hollow compartments due to which more number of CH4 molecules get adsorbed. The methane molecule adsorption on the various sites of BCNTs have been considered in order to observe and compare the modified structural and electronic properties of the two BCNTs. The comparative analysis depicts that CH4 molecule gets adsorbed suffer with higher adsorption energy to (12,0) BCNT surface than that of (5,0) BCNT surface.
Boron neutron capture therapy (BNCT) is a cancer treatment still in development that is considered with increasing interest. It consists in irradiating with thermal or epithermal neutrons patients to whom a specific tumor-seeking Boron carrier has been administrated. The high cross section of the 10B(n, α)7Li reaction for thermal neutrons and the high radiobiological effectiveness are exploited in order to damage the tumour cells without afflicting the surrounding healthy tissues.
The Plasma and Ion Source Technology Group at Lawrence Berkeley National Laboratory has developed various types of advanced D-D (neutron energy 2.5 MeV), D-T (14 MeV) and T-T (0 – 9 MeV) neutron generators for wide range of applications. These applications include medical (Boron Neutron Capture Therapy), homeland security (Prompt Gamma Activation Analysis, Fast Neutron Activation Analysis and Pulsed Fast Neutron Transmission Spectroscopy) and planetary exploration with a sub-surface material characterization on Mars. These neutron generators utilize RF induction discharge to ionize the deuterium/tritium gas. This discharge method provides high plasma density for high output current, high atomic species from molecular gases, long life operation and versatility for various discharge chamber geometries. Four main neutron generator developments are discussed here: high neutron output co- axial neutron generator for BNCT applications, point neutron generator for security applications, compact and sub-compact axial neutron generator for elemental analysis applications. Current status of the neutron generator development with experimental data will be presented.
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