scholarly journals ANALYSIS OF PARTICLE DISTRIBUTION IN A DOUBLE LAYER BEAM SHAPING ASSEMBLY RESULTED FROM 30 MEV-PROTON REACTIONS WITH BERYLLIUM TARGET USING THE PHITS PROGRAM

2020 ◽  
Vol 82 (3) ◽  
Author(s):  
Bilalodin Bilalodin ◽  
Gede Bayu Suparta ◽  
Arief Hermanto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono ◽  
...  
Keyword(s):  
Double Layer ◽  
Neutron Beam ◽  
Particle Flux ◽  
Epithermal Neutron ◽  
Beam Shaping ◽  
Fast Neutrons ◽  
Hydrogen Atoms ◽  
Epithermal Neutrons ◽  
Beryllium Target ◽  
Beam Shaping Assembly

An analysis on the distribution of particle flux emanating from reactions of 30 MeV-proton with beryllium target in a double layer beam shaping assembly (BSA) has been carried out using the PHITS program.  It studies important parameters relating to the distribution of proton, neutron, and gamma. It is revealed that reactions of proton and beryllium in double layer BSA produce fast neutrons and other protons, resulting from certain reactions, and recoil protons from the interactions of fast neutrons and hydrogen atoms. Fast neutrons are distributed around beryllium target, moderator, reflector, and collimator. They are moderated by Al and LiF material. Epithermal neutrons spread along the moderator, with a distribution that is tapering down as it approaches the end of the collimator (aperture). During its travel along the moderator, an epithermal neutron decreases in energy to become a thermal neutron. The spectrum of neutron beam produced by the double layer BSA is wide, which indicates that the neutron beam exiting the aperture consists of three kinds of neutrons, dominated by epithermal neutronswith energy range 1 eV – 10 keV.  

scholarly journals Characteristics of Thermal Neutron Flux Distribution in a Phantom Irradiated by Epithermal Neutron Beam from Double Layer Beam Shaping Assembly (DBSA)

2019 ◽  
Vol 62 (3) ◽  
pp. 167-173
Author(s):  
Bilal Odin ◽  
Gede Bayu Suparta ◽  
Arief Hermanto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Double Layer ◽  
Neutron Beam ◽  
Epithermal Neutron ◽  
Beam Shaping ◽  
Epithermal Neutron Flux ◽  
Epithermal Neutrons ◽  
Beryllium Target ◽  
Beam Shaping Assembly

A simulation study on the Double-layer Beam Shaping Assembly (DBSA) system has been carried out. This study used fast neutron beam resulting from reactions of 30 MeV protons with beryllium target. The MCNPX code was utilized to design the DBSA and the phantom as well as to calculate neutron flux on the phantom. The distribution of epithermal neutron flux and gamma in the DBSA and phantom were computed using the PHITS code. The spectrum of radiation beams generated by the DBSA shows the characteristics that the typical epithermal neutron flux of 1.0 x109 n/(cm2.s), the ratio of epithermal to the thermal and fast neutron flux of 344 and 85, respectively and the ratio of gamma dose to the epithermal neutron flux of 1.82 x 10-13 Gy.cm2. The test of epithermal neutron beams irradiation on the water phantom shows that epithermal neutrons are thermalized and penetrate the phantom up to 12 cm in depth. The maximum value of neutron flux is 1.1 x 109 n/(cm2.s) at a depth of 2 cm in phantom.  

scholarly journals Characteristics in Water Phantom of Epithermal Neutron Beam Produced by Double Layer Beam Shaping Assembly

2019 ◽  
Vol 36 (1) ◽  
pp. 9-12
Author(s):  
Bilalodin Bilalodin ◽  
Gede Bayu Suparta ◽  
Arief Hermanto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono
Keyword(s):  
Double Layer ◽  
Neutron Beam ◽  
Epithermal Neutron ◽  
Absorbed Dose ◽  
Heavy Ion ◽  
Beam Shaping ◽  
Water Phantom ◽  
Program Testing ◽  
Epithermal Neutrons ◽  
Beam Shaping Assembly

A Double Layer Beam Shaping Assembly (DLBSA) was designed to produce epithermal neutrons for BNCT purposes. The Monte Carlo N-Particle eXtended program was used as the software to design the DLBSA and phantom. Distribution of epithermal neutron and gamma flux in the DLBSA and phantom and absorbed dose in the phantom were computed using the Particle and Heavy Ion Transport code System program. Testing results of epithermal neutron beam irradiation of the water phantom showed that epithermal neutrons were thermalized and penetrated the phantom up to a depth of 12 cm. The maximum value of the absorbed dose was 2 × 10-3 Gy at a depth of 2 cm in the phantom.

scholarly journals Optimization and analysis of neutron distribution on 30 MeV cyclotron-based double layer beam shaping assembly (DLBSA)

2019 ◽  
Vol 20 (1) ◽  
pp. 70-75
Author(s):  
Bilalodin ◽  
◽  
G.B. Suparta ◽  
A. Hermanto ◽  
D.S. Palupi ◽  
...  
Keyword(s):  
Double Layer ◽  
Beam Shaping ◽  
Neutron Distribution ◽  
Beam Shaping Assembly

scholarly journals Optimization of double layered beam shaping assembly using genetic algorithm

2018 ◽  
Vol 24 (4) ◽  
pp. 157-164
Author(s):  
◽  
Gede Bayu Suparta ◽  
Arief Hermanto ◽  
Dwi Satya Palupi ◽  
Yohannes Sardjono ◽  
...  
Keyword(s):  
Genetic Algorithm ◽  
Thermal Neutron ◽  
Double Layer ◽  
Beam Shaping ◽  
New Method ◽  
Neutron Filter ◽  
Genetic Algorithm Method ◽  
Layered Beam ◽  
Beam Shaping Assembly ◽  
Radiation Beams

Abstract The genetic algorithm method is a new method used to obtain radiation beams that meet the IAEA requirements. This method is used in optimization of configurations and compositions of materials that compose double layered Beam Shaping Assembly (BSA). The double layered BSA is modeled as having two layers of material for each of the components, which are the moderator, reflector, collimator, and filter. Up to 21st generation, the optimization results in four (4) individuals having the capacity to generate the most optimum radiation beams. The best configuration, producing the most optimum radiation beams, is attained by using combinations of materials, that is by combining Al with either one of CaF2 and PbF2for moderator; combining Pb material with either Ni or Pb for reflector; combining Ni and either FeC or C for collimator, and FeC+LiF and Cd for fast and thermal neutron filter. The parameters of radiation resulted from the four configurations of double layer BSA adequately satisfy the standard of the IAEA.

Neutron-beam-shaping assembly for boron neutron-capture therapy

2017 ◽  
Vol 80 (1) ◽  
pp. 60-66 ◽  
Author(s):  
L. Zaidi ◽  
E. A. Kashaeva ◽  
S. I. Lezhnin ◽  
G. N. Malyshkin ◽  
S. I. Samarin ◽  
...  
Keyword(s):  
Neutron Beam ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Beam Shaping ◽  
Neutron Capture Therapy ◽  
Boron Neutron Capture ◽  
Beam Shaping Assembly

scholarly journals Evaluating the Therapeutic Potential and the Suitability of Neutron Beams Designed for Clinical BNCT

2020 ◽  
Author(s):  
Ian Postuma ◽  
Sara Gonzalez ◽  
Maria Herrera ◽  
Lucas Provenzano ◽  
Michele Ferrarini ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Neutron Beam ◽  
Clinical Relevance ◽  
Epithermal Neutron ◽  
Therapeutic Potential ◽  
Beam Quality ◽  
Beam Shaping ◽  
Physical Characteristics ◽  
Epithermal Neutron Flux ◽  
Beam Design

Abstract The standard of neutron beam quality for Boron Neutron Capture Therapy (BNCT) of deep-seated tumours is currently defined by its physical characteristics in air: the epithermal neutron flux, the ratio of thermal and epithermal neutron flux, the fast neutron and photon dose contamination, and the beam collimation. Traditionally, the beam design consists in tailoring a Beam Shaping Assembly (BSA) able to deliver a neutron beam with the recommended values of these figures of merit (FOMs). This work investigated the possibility to produce an epithermal neutron beam able to guarantee the best clinical performance for deep-seated tumours, starting from a 5 MeV, 30 mA proton beam coupled to a beryllium target. Different Beam Shaping Assemblies were designed using those physical FOMs which, however, were not enough to establish a clear ranking of the different beams, nor to describe their clinical relevance. To go beyond this traditional approach, beams were then evaluated employing new criteria based on the dose distributions obtained in-phantom and on the calculation of the Uncomplicated Tumour Control Probability (UTCP). Such radiobiological FOM allows establishing the therapeutic potential of the beams. Moreover, we included the concept of suitability as a criterion to select the safest BSA design, calculating the in-patient out-of-beam dosimetry. The clinical relevance of the selected beam was finally tested in the treatment planning of a clinical case treated at the FiR 1 beam in Finland, where several patients have safely and successfully received BNCT in the last years. Despite the selected beam does not comply with all the standard physical recommendations, it shows a therapeutic potential comparable and even better than that of FiR 1. This confirms that establishing the performance of a beam cannot rely only on its physical characteristics, but requires additional criteria able to predict the clinical outcome of a BNCT treatment.

scholarly journals Beam Shaping Assembly Optimization for Boron Neutron Capture Therapy Facility Based on Cyclotron 30 MeV as Neutron Source

2018 ◽  
Vol 35 (3) ◽  
pp. 183-186
Author(s):  
Arief Fauzi ◽  
Afifah Hana Tsurayya ◽  
Ahmad Faisal Harish ◽  
Gede Sutresna Wijaya
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Boron Neutron Capture Therapy ◽  
Neutron Capture ◽  
Epithermal Neutron ◽  
Beam Shaping ◽  
Neutron Capture Therapy ◽  
Epithermal Neutron Flux ◽  
Boron Neutron Capture ◽  
Beam Shaping Assembly

A design of beam shaping assembly (BSA) installed on cyclotron 30 MeV model neutron source for boron neutron capture therapy (BNCT) has been optimized using simulator software of Monte Carlo N-Particle Extended (MCNPX). The Beryllium target with thickness of 0.55 cm is simulated to be bombarded with 30 MeV of proton beam. In this design, the parameter regarding beam characteristics for BNCT treatment has been improved, which is ratio of fast neutron dose and epithermal neutron flux. TiF3 is replaced to 30 cm of 27Al as moderator, and 1.5 cm of 32S is combined with 28 cm of 60Ni as neutron filter. Eventually, this design produces epithermal neutron flux of 2.33 × 109, ratio between fast neutron dose and epithermal neutron flux of 2.12 × 10-13,ratio between gamma dose and epithermal neutron flux of 1.00 × 10-13, ratio between thermal neutron flux and epithermal neutron flux is 0.047, and ration between particle current and total neutron flux is 0.56.

scholarly journals Determination of the Neutron Beam Spatial Profile at n_TOF EAR-2 using the CR-39 Track Detectors

2019 ◽  
Vol 23 ◽  
pp. 28
Author(s):  
Z. Eleme ◽  
M. Alexandropoulou ◽  
A. Georgiadou ◽  
K. G. Ioannides ◽  
M. Kokkoris ◽  
...  
Keyword(s):  
Neutron Beam ◽  
Optical Microscope ◽  
Fast Neutrons ◽  
Hydrogen Atoms ◽  
Spatial Profile ◽  
Naoh Solution ◽  
Sample Position ◽  
Cr 39 Detectors

Within the present work the neutron beam spatial profile was determined at the sample position in EAR-2 at the n_TOF facility at CERN. The CR-39 detectors were coupled with a 2mm PE foil serving as neutron-to-proton converter. Two irradiations were performed in the 10x5 cm surface of CR-39 detectors. Proton tracks were revealed in the CR-39 detectors resulting from the elastic scattering of fast neutrons on the hydrogen atoms in the PE converter. Afterwards, the CR-39 detectors were chemically etched in aqueous NaOH solution and latent tracks were considerably enlarged to become visible under an optical microscope. After the scanning of the detectors surface, the acquired images were analyzed using the ImageJ program. In the present work, the experimental setup and procedure will be presented along with the results concerning the characterization of the neutron beam spatial profile at the sample position in the n_TOF EAR-2.

scholarly journals Desain Beam Shaping Assembly (BSA) berbasis D-D Neutron Generator 2,45 MeV untuk Uji Fasilitas BNCT

2015 ◽  
Vol 5 (02) ◽  
pp. 25 ◽  
Author(s):  
Desman P. Gulo ◽  
Suryasatriya T. ◽  
Slamet Santosa ◽  
Y. Sardjono
Keyword(s):  
Breast Cancer ◽  
Neutron Generator ◽  
Epithermal Neutron ◽  
Beam Shaping ◽  
Neutron Capture Therapy ◽  
Total Production ◽  
Cancer Treatments ◽  
Epithermal Flux ◽  
Boron Neutron Capture ◽  
Beam Shaping Assembly

<p>Boron Neutron Capture Therapy (BNCT) is one of the cancer treatments that are being developed in nowadays. In order to support BNCT treatment for cancer that exists in underneath skin like breast cancer, the facility needs a generator that is able to produce epithermal neutron. One of the generator that is able to produce neutron is D-D neutron generator with 2.45 MeV energy. Based on the calculation of this paper, we found that the total production of neutron per second (neutron yield) from Neutron Generator (NG) by PSTA-BATAN Yogyakarta is 2.55×10<sup>11 </sup>n/s. The energy and flux that we found is in the range of quick neutron. Thus, it needs to be moderated to the level of epithermal neutron which is located in the interval energy of 1 eV to 10 KeV with 10<sup>9</sup> n/cm<sup>2</sup>s flux. This number is the recommendation standard from IAEA. Beam Shaping Assembly (BSA) is needed in order to moderate the quick neutron to the level of epithermal neutron. One part of BSA that has the responsibility in moderating the quick neutron to epithermal neutron is the moderator. The substance of moderator used in this paper is MgF<sub>2</sub> and A1F<sub>3</sub>. The thickness of moderator has been set in in such a way by using MCNPX software in order to fulfill the standard of IAEA. As the result of optimizing BSA moderator, the data obtain epithermal flux with the total number of 4.64×10<sup>8 </sup>n/cm<sup>2</sup>/s for both of moderators with the thickness of moderator up to 15 cm. At the end of this research, the number of epithermal flux does not follow the standard of IAEA. This is because the flux neutron that is being produced by NG is relatively small. In conclusion, the NG from PSTA-BATAN Yogyakarta is not ready to be used for the BNCT treatment facility for the underneath skin cancer like breast cancer.</p>

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