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.

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 A NEUTRON BEAM SHAPING ASSEMBLY DESIGN FOR BNCT AND ITS DOSIMETRY SIMULATION BASED ON MCNPX

2017 ◽  
Vol 19 (3) ◽  
pp. 121
Author(s):  
I Made Ardana ◽  
Yohannes Sardjono
Keyword(s):  
Soft Tissue ◽  
Soft Tissue Sarcoma ◽  
Neutron Flux ◽  
Head And Neck ◽  
Fast Neutron ◽  
Irradiation Time ◽  
Beam Shaping ◽  
Assembly Design ◽  
Neutron Filter ◽  
Beam Shaping Assembly

This article involves two main objectives of BNCT system. The first goal includes optimization of 30 MeV Cyclotron-based Boron Neutron Capture Therapy (BNCT) beam shaping assembly. The second goal is to calculate the neutron flux and dosimetry system of BNCT in the head and neck soft tissue sarcoma. A series of simulations has been carried out using a Monte Carlo N Particle X program to find out the final composition and configuration of a beam shaping assembly design to moderate the fast neutron flux, which is generated from the thick beryllium target. The final configuration of the beam shaping assembly design includes a 39 cm aluminum moderator, 8.2 cm of lithium fluoride as a fast neutron filter and a 0.5 cm boron carbide as a thermal neutron filter. Bismuth, lead fluoride, and lead were chosen as the aperture, reflector, and gamma shielding, respectively. Epithermal neutron fluxes in the suggested design were 2.83 x 109 n/s cm-2, while other IAEA parameters for BNCT beam shaping assembly design have been satisfied. In the next step, its dosimetry for head and neck soft tissue sarcoma is simulated by varying the concentration of boron compounds in ORNL neck phantom model to obtain the optimal dosimetry results. MCNPX calculation showed that the optimal depth for thermal neutrons was 4.8 cm in tissue phantom with the maximum dose rate found in the GTV on each boron concentration variation. The irradiation time needed for this therapy were less than an hour for each level of boron concentration.Keywords: Optimization, Beam Shaping Assembly, BNCT, Dosimetry, 30 MeV Cyclotron, MCNPX. OPTIMASI DESAIN KOLIMATOR NEUTRON UNTUK SISTEM BNCT DAN UJI DOSIMETRINYA MENGGUNAKAN PROGRAM MCNPX. Telah dilakukan penelitian tentang sistem BNCT yang meliputi dua tahapan simulasi dengan menggunakan program MCNPX yaitu uji simulasi untuk optimasi desain kolimator neutron untuk sistem BNCT berbasis Siklotron 30 MeV dan uji simulasi untuk menghitung fluks neutron dan dosimetri radiasi pada kanker sarkoma jaringan lunak pada leher dan kepala. Tujuan simulasi untuk mendapatkan desain kolimator yang paling optimal dalam memoderasi fluks neutron cepat yang dihasilkan dari sistem target berilium sehingga dapat dihasilkan fluks neutron yang sesuai untuk sistem BNCT. Uji optimasi dilakukan dengan cara memvariasikan bahan dan ketebalan masing-masing komponen dalam kolimator seperi reflektor, moderator, filter neutron cepat, filter neutron thermal, filter radiasi gamma dan lubang keluaran. Desain kolimator yang diperoleh dari hasil optimasi tersusun atas moderator berbahan Al dengan ketebalan 39 cm, filter neutron cepat berbahan LiF2 setebal 8,2 cm, dan filter neutron thermal berbahan B4C setebal 0,5 cm. Untuk reflektor, filter radiasi gamma dan lubang keluaran masing-masing menggunakan bahan PbF2, Pb dan Bi. Fluks neutron epithermal yang dihasilkan dari kolimator yang didesain adalah sebesar 2,83 x 109 n/s cm-2 dan telah memenuhi seluruh parameter fluks neutron yang sesuai untuk sistem BNCT. Selanjutnya uji simulasi dosimetri pada kanker sarkoma jaringan lunak pada leher dan kepala dilakukan dengan cara memvariasikan konsentrasi senyawa boron pada model phantom leher manusia (ORNL). Selanjutnya model phantom tersebut diiradiasi dengan fluks neutron yang berasal dari kolimator yang telah didesain sebelumnya. Hasilnya, fluks neutron thermal mencapai nilai tertinggi pada kedalaman 4,8 cm di dalam model phantom leher ORNL dengan laju dosis tertinggi terletak pada area jaringan kanker. Untuk masing-masing variasi konsentrasi senyawa boron pada model phantom leher ORNL supaya dapat mematikan jaringan kanker, membutukan waktu iradiasi neutron kurang dari satu jam.Kata kunci: Optimasi, Kolimator, BNCT, Dosimetri, Siklotron 30 MeV, MCNPX

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 of a Beam Shaping Assembly Design for Boron Neutron Capture Cancer Therapy Facility Based on 30 MeV Cyclotron

2016 ◽  
Vol 1 (3) ◽  
pp. 128
Author(s):  
I Made Ardana ◽  
Kusminarto Kusminarto ◽  
Yohannes Sardjono
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Target Material ◽  
Beam Shaping ◽  
Copper Plate ◽  
Ansys Fluent ◽  
Beryllium Target ◽  
Neutron Filter ◽  
Beam Shaping Assembly ◽  
Almost All

A series of simulations has been carried out using a Monte Carlo N Particle X code to find out the final composition and configuration of a neutron Beam Shaping Assembly (BSA)  to moderate the fast neutron flux which is generated from the thick disk-type beryllium target. The final configuration for neutron BSA design included 35 cm lead as reflector, 39 cm alumina as moderator, 8.2 cm lithium fluoride as fast neutron filter and 0.5 cm boron carbide as thermal neutron filter. Bismuth, lead fluoride, and lead were chosen as the aperture, reflector, and gamma shielding, respectively. The disk-type of beryllium target is 19 cm in diameter with 0.5 cm thickness which is covered by copper plate to hold the water pressured coolant. A higher yield of neutron production requires a higher intensity of proton beams, which generate much heats and causes the target material to melt. Therefore, it is useful to consider the temperature distribution on the target material with flowing water coolant by means of computer modeling while designing the target. ANSYS-Fluent code will be used to estimate the thermal transfer and heat calculation in a solid target during beam irradiation. Epithermal neutron flux in the suggested design were 1,03x10<sup>9</sup> n/cm<sup>2</sup> s, with almost all IAEA parameters for BNCT BSA design has been satisfied.

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.  

Sign in / Sign up

Export Citation Format

Share Document