Your browser doesn't support javascript.
loading
Show: 20 | 50 | 100
Results 1 - 10 de 10
Filter
Add more filters










Publication year range
1.
Appl Radiat Isot ; 166: 109315, 2020 Dec.
Article in English | MEDLINE | ID: mdl-32966949

ABSTRACT

Existing and active low-energy Accelerator-Based BNCT programs worldwide will be reviewed and compared. In particular, the program in Argentina will be discussed which consists of the development of an Electro-Static-Quadrupole (ESQ) Accelerator-Based treatment facility. The facility is conceived to operate with the deuteron-induced reactions 9Be(d,n)10B and 13C(d,n)14N at 1.45 MeV deuteron energy, as neutron sources. Neutron production target development status is specified. The present status of the construction of the new accelerator development laboratory and future BNCT centre is shown.

2.
Phys Med ; 33: 106-113, 2017 Jan.
Article in English | MEDLINE | ID: mdl-28049613

ABSTRACT

PURPOSE: Boron Neutron Capture Therapy (BNCT) requires neutron sources suitable for in-hospital siting. Low-energy particle accelerators working in conjunction with a neutron producing reaction are the most appropriate choice for this purpose. One of the possible nuclear reactions is 13C(d,n)14N. The aim of this work is to evaluate the therapeutic capabilities of the neutron beam produced by this reaction, through a 30mA beam of deuterons of 1.45MeV. METHODS: A Beam Shaping Assembly design was computationally optimized. Depth dose profiles in a Snyder head phantom were simulated with the MCNP code for a number of BSA configurations. In order to optimize the treatment capabilities, the BSA configuration was determined as the one that allows maximizing both the tumor dose and the penetration depth while keeping doses to healthy tissues under the tolerance limits. RESULTS: Significant doses to tumor tissues were achieved up to ∼6cm in depth. Peak doses up to 57Gy-Eq can be delivered in a fractionated scheme of 2 irradiations of approximately 1h each. In a single 1h irradiation, lower but still acceptable doses to tumor are also feasible. CONCLUSIONS: Treatment capabilities obtained here are comparable to those achieved with other accelerator-based neutron sources, making of the 13C(d,n)14N reaction a realistic option for producing therapeutic neutron beams through a low-energy particle accelerator.


Subject(s)
Boron Neutron Capture Therapy/methods , Neutrons/therapeutic use , Carbon Isotopes/therapeutic use , Nitrogen , Radiotherapy Dosage , Radiotherapy Planning, Computer-Assisted
3.
Appl Radiat Isot ; 106: 18-21, 2015 Dec.
Article in English | MEDLINE | ID: mdl-26320739

ABSTRACT

In this work we provide some information on the present status of accelerator-based BNCT (AB-BNCT) worldwide and subsequently concentrate on the recent accelerator technology developments in Argentina.


Subject(s)
Boron Neutron Capture Therapy/instrumentation , Argentina
4.
Appl Radiat Isot ; 88: 185-9, 2014 Jun.
Article in English | MEDLINE | ID: mdl-24365468

ABSTRACT

The activity in accelerator development for accelerator-based BNCT (AB-BNCT) both worldwide and in Argentina is described. Projects in Russia, UK, Italy, Japan, Israel, and Argentina to develop AB-BNCT around different types of accelerators are briefly presented. In particular, the present status and recent progress of the Argentine project will be reviewed. The topics will cover: intense ion sources, accelerator tubes, transport of intense beams, beam diagnostics, the (9)Be(d,n) reaction as a possible neutron source, Beam Shaping Assemblies (BSA), a treatment room, and treatment planning in realistic cases.


Subject(s)
Boron Neutron Capture Therapy/instrumentation , Particle Accelerators/instrumentation , Radiometry/instrumentation , Equipment Design , Equipment Failure Analysis , Internationality , Technology Assessment, Biomedical
5.
Appl Radiat Isot ; 88: 190-4, 2014 Jun.
Article in English | MEDLINE | ID: mdl-24332880

ABSTRACT

In the frame of accelerator-based BNCT, the (9)Be(d,n)(10)B reaction was investigated as a possible source of epithermal neutrons. In order to determine the configuration in terms of bombarding energy, target thickness and Beam Shaping Assembly (BSA) design that results in the best possible beam quality, a systematic optimization study was carried out. From this study, the optimal configuration resulted in tumor doses ≥40Gy-Eq, with a maximum value of 51Gy-Eq at a depth of about 2.7cm, in a 60min treatment. The optimal configuration was considered for the treatment planning assessment of a real Glioblastoma Multiforme case. From this, the resulted dose performances were comparable to those obtained with an optimized (7)Li(p,n)-based neutron source, under identical conditions and subjected to the same clinical protocol.


Subject(s)
Boron Neutron Capture Therapy/instrumentation , Boron/therapeutic use , Brain Neoplasms/radiotherapy , Glioblastoma/radiotherapy , Particle Accelerators/instrumentation , Radiometry/instrumentation , Radiotherapy Planning, Computer-Assisted/methods , Equipment Design , Equipment Failure Analysis , Humans , Isotopes/therapeutic use , Materials Testing , Neutrons/therapeutic use , Scattering, Radiation
6.
Phys Med ; 30(2): 133-46, 2014 Mar.
Article in English | MEDLINE | ID: mdl-23880544

ABSTRACT

The 9Be(d,n)10B reaction was studied as an epithermal neutron source for brain tumor treatment through Boron Neutron Capture Therapy (BNCT). In BNCT, neutrons are classified according to their energies as thermal (<0.5 eV), epithermal (from 0.5 eV to 10 keV) or fast (>10 keV). For deep-seated tumors epithermal neutrons are needed. Since a fraction of the neutrons produced by this reaction are quite fast (up to 5-6 MeV, even for low-bombarding energies), an efficient beam shaping design is required. This task was carried out (1) by selecting the combinations of bombarding energy and target thickness that minimize the highest-energy neutron production; and (2) by the appropriate choice of the Beam Shaping Assembly (BSA) geometry, for each of the combinations found in (1). The BSA geometry was determined as the configuration that maximized the dose deliverable to the tumor in a 1 h treatment, within the constraints imposed by the healthy tissue dose adopted tolerance. Doses were calculated through the MCNP code. The highest dose deliverable to the tumor was found for an 8 µm target and a deuteron beam of 1.45 MeV. Tumor weighted doses ≥40 Gy can be delivered up to about 5 cm in depth, with a maximum value of 51 Gy at a depth of about 2 cm. This dose performance can be improved by relaxing the treatment time constraint and splitting the treatment into two 1-h sessions. These good treatment capabilities strengthen the prospects for a potential use of this reaction in BNCT.


Subject(s)
Beryllium/therapeutic use , Boron Neutron Capture Therapy/methods , Boron/therapeutic use , Monte Carlo Method , Neoplasms/radiotherapy , Radioisotopes/therapeutic use , Gamma Rays , Neutrons/therapeutic use , Radiotherapy Dosage
7.
Appl Radiat Isot ; 69(12): 1684-7, 2011 Dec.
Article in English | MEDLINE | ID: mdl-21353576

ABSTRACT

In the range of low bombarding energies (less than about 1.5 MeV) the (9)Be(d,n)(10)B reaction produces neutron spectra that can be moderated depending on the choice of the target thickness and the deuteron bombarding energy. In this work, a Monte Carlo simulation study to determine the capability of this reaction to deliver enough dose to efficiently control both skin and deep seated tumors has been performed by means of MCNP calculations using eight optimized (9)Be targets.


Subject(s)
Beryllium/therapeutic use , Boron Neutron Capture Therapy , Neoplasms/radiotherapy , Radioisotopes/therapeutic use , Skin Neoplasms/radiotherapy , Humans , Monte Carlo Method
8.
Appl Radiat Isot ; 69(12): 1672-5, 2011 Dec.
Article in English | MEDLINE | ID: mdl-21353577

ABSTRACT

We describe the present status of an ongoing project to develop a Tandem-ElectroStatic-Quadrupole (TESQ) accelerator facility for Accelerator-Based (AB)-BNCT. The project final goal is a machine capable of delivering 30 mA of 2.4 MeV protons to be used in conjunction with a neutron production target based on the (7)Li(p,n)(7)Be reaction. The machine currently being constructed is a folded TESQ with a high-voltage terminal at 0.6 MV. We report here on the progress achieved in a number of different areas.


Subject(s)
Boron Neutron Capture Therapy , Boron Neutron Capture Therapy/instrumentation , Static Electricity
9.
Appl Radiat Isot ; 68(7-8): 1358-61, 2010.
Article in English | MEDLINE | ID: mdl-20031433

ABSTRACT

The nuclide (241)Am decays by alpha emission to (237)Np. Most of the decays (84.6%) populate the excited level of (237)Np with energy of 59.54 keV. Digital coincidence counting was applied to standardize a solution of (241)Am by alpha-gamma coincidence counting with efficiency extrapolation. Electronic discrimination was implemented with a pressurized proportional counter and the results were compared with two other independent techniques: Liquid scintillation counting using the logical sum of double coincidences in a TDCR array and defined solid angle counting taking into account activity inhomogeneity in the active deposit. The results show consistency between the three methods within a limit of a 0.3%. An ampoule of this solution will be sent to the International Reference System (SIR) during 2009. Uncertainties were analysed and compared in detail for the three applied methods.


Subject(s)
Americium/standards , Radiometry/methods , Alpha Particles , International Cooperation , Reference Standards , Reproducibility of Results , Scintillation Counting/methods , Uncertainty
10.
Appl Radiat Isot ; 66(6-7): 1049-54, 2008.
Article in English | MEDLINE | ID: mdl-18356062

ABSTRACT

A non-radionuclide-specific computer code to analyze data, calculate detection efficiency and activity in a TDCR system is presented. The program was developed prioritizing flexibility in measuring conditions, parameters and calculation models. It is also intended to be well structured in order to easily replace subroutines which could eventually be improved by the user. It is written in standard FORTRAN language but a graphical interface is also available. Several tests were performed to check the ability of the code to deal with different decay schemes such as H-3, C-14, Fe-55, Mn-54 and Co-60.

SELECTION OF CITATIONS
SEARCH DETAIL
...