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Journal articles on the topic 'Beam shaping assembly'

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Author: Grafiati

Published: 10 December 2022

Last updated: 28 January 2023

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1

Bilalodin, Bilalodin, Aris Haryadi, Kartika Sari, and Wihantoro Wihantoro. "OPTIMIZATION AND VERIFICATION OF DOUBLE LAYER BEAM SHAPING ASSEMBLY (DLBSA) FOR EPITHERMAL NEUTRON GENERATION." Jurnal Teknologi 84, no. 4 (May 30, 2022): 103–12. http://dx.doi.org/10.11113/jurnalteknologi.v84.18047.

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The designs of Beam Shaping Assembly (BSA) for moderating fast neutron into epithermal neutron have been conducted. Some BSA models that are previously developed are still having problems in generating epithermal neutron. Instead, we propose designs of double layer beam shaping assembly (DLBSA) to produce epithermal neutron. Optimization of the Double Layer Beam Shaping Assembly (DLBSA) design was carried out using the genetic algorithm (AG) method using MCNPX and verified using the Particle and Heavy Ion Transport code System (PHITS). The optimization resulted in four configurations up to the 21st generation capable of producing epithermal neutron beams that comply with the IAEA standards. The best four configurations are obtained by combining: (1) Al with one of the CaF2, BiF3 or PbF2 materials as moderator, (2) Pb with Pb, Ni, or Bi as a reflector, (3) Ni with FeC, or C as collimator, (4) (FeC + LiF) as fast neutron filter, Cd or B4C as thermal neutron filter. Verification of the four optimum configurations of the DLBSA model using PHITS code shows that the epithermal neutron beam produced by DLBSA has met the IAEA standards.

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2

Suparta, Gede Bayu, Arief Hermanto, Dwi Satya Palupi, and Yohannes Sardjono. "Optimization of double layered beam shaping assembly using genetic algorithm." Polish Journal of Medical Physics and Engineering 24, no. 4 (December 1, 2018): 157–64. http://dx.doi.org/10.2478/pjmpe-2018-0022.

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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.

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3

Zaidi, L., E. A. Kashaeva, S. I. Lezhnin, G. N. Malyshkin, S. I. Samarin, T. V. Sycheva, S. Yu Taskaev, and S. A. Frolov. "Neutron-beam-shaping assembly for boron neutron-capture therapy." Physics of Atomic Nuclei 80, no. 1 (January 2017): 60–66. http://dx.doi.org/10.1134/s106377881701015x.

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4

Burlon, A. A., A. J. Kreiner, A. A. Valda, and D. M. Minsky. "An optimized neutron-beam shaping assembly for accelerator-based BNCT." Applied Radiation and Isotopes 61, no. 5 (November 2004): 811–15. http://dx.doi.org/10.1016/j.apradiso.2004.05.063.

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5

Bilalodin, Bilalodin, Gede Bayu Suparta, Arief Hermanto, Dwi Satya Palupi, and Yohannes Sardjono. "Characteristics in Water Phantom of Epithermal Neutron Beam Produced by Double Layer Beam Shaping Assembly." ASEAN Journal on Science and Technology for Development 36, no. 1 (April 27, 2019): 9–12. http://dx.doi.org/10.29037/ajstd.519.

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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.

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6

Minsky, D. M., and A. J. Kreiner. "Beam shaping assembly optimization for 7Li(p,n)7Be accelerator based BNCT." Applied Radiation and Isotopes 88 (June 2014): 233–37. http://dx.doi.org/10.1016/j.apradiso.2013.11.088.

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7

Bilalodin, A. Haryadi, Kartika Sari, Y. Sardjono, and RasitoTursinah. "Design development of double-layer beam shaping assembly using extension nozzle to increase the quality of epithermal neutron beam as a boron neutron capture therapy neutron source." Nuclear Physics and Atomic Energy 22, no. 4 (December 25, 2021): 415–21. http://dx.doi.org/10.15407/jnpae2021.04.415.

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Double layer beam shaping assembly (DLBSA) is a system that moderates fast neutrons into epithermal neutrons. The epithermal neutrons that leave the aperture in the DLBSA system are broadened in the space, thereby reducing the intensity and homogeneity of the epithermal neutron beams. Therefore, it is necessary to improve the design. The development of the DLBSA design was carried out using an extension nozzle. The nozzles are designed using materials made in three configurations, namely Ni+LiF load polyethylene, Pb+LiF load polyethylene, and Bi+LiF load polyethylene. The simulation results show that the addition of a nozzle at the tip of the DLBSA can channel the beam more directionally with high intensity. The addition of nozzles with Ni+LiF load PE material produces an epithermal neutron beam that meets the IAEA standards.

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8

Odin, Bilal, Gede Bayu Suparta, Arief Hermanto, Dwi Satya Palupi, Yohannes Sardjono, and Rasito A. "Characteristics of Thermal Neutron Flux Distribution in a Phantom Irradiated by Epithermal Neutron Beam from Double Layer Beam Shaping Assembly (DBSA)." Pakistan Journal of Scientific & Industrial Research Series A: Physical Sciences 62, no. 3 (November 28, 2019): 167–73. http://dx.doi.org/10.52763/pjsir.phys.sci.62.3.2019.167.173.

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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.

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9

Minsky, D. M., A. J. Kreiner, and A. A. Valda. "AB-BNCT beam shaping assembly based on 7Li(p,n)7Be reaction optimization." Applied Radiation and Isotopes 69, no. 12 (December 2011): 1668–71. http://dx.doi.org/10.1016/j.apradiso.2011.02.047.

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10

Herrera, M. S., S. J. González, A. A. Burlon, D. M. Minsky, and A. J. Kreiner. "Treatment planning capability assessment of a beam shaping assembly for accelerator-based BNCT." Applied Radiation and Isotopes 69, no. 12 (December 2011): 1870–73. http://dx.doi.org/10.1016/j.apradiso.2011.03.029.

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11

Lee, Pei-Yi, Xiaobin Tang, Changran Geng, and Yuan-Hao Liu. "A bi-tapered and air-gapped beam shaping assembly used for AB-BNCT." Applied Radiation and Isotopes 167 (January 2021): 109392. http://dx.doi.org/10.1016/j.apradiso.2020.109392.

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12

Nadazdy, Peter, Jakub Hagara, Petr Mikulik, Zdenko Zaprazny, Dusan Korytar, Eva Majkova, Matej Jergel, and Peter Siffalovic. "A high-throughput assembly of beam-shaping channel-cut monochromators for laboratory high-resolution X-ray diffraction and small-angle X-ray scattering experiments." Journal of Applied Crystallography 54, no. 3 (April 16, 2021): 730–38. http://dx.doi.org/10.1107/s1600576721002338.

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A four-bounce monochromator assembly composed of Ge(111) and Ge(220) monolithic channel-cut monochromators with V-shaped channels in a quasi-dispersive configuration is presented. The assembly provides an optimal design in terms of the highest transmittance and photon flux density per detector pixel while maintaining high beam collimation. A monochromator assembly optimized for the highest recorded intensity per detector pixel of a linear detector placed 2.5 m behind the assembly was realized and tested by high-resolution X-ray diffraction and small-angle X-ray scattering measurements using a microfocus X-ray source. Conventional symmetric and asymmetric Ge(220) Bartels monochromators were similarly tested and the results were compared. The new assembly provides a transmittance that is an order of magnitude higher and 2.5 times higher than those provided by the symmetric and asymmetric Bartels monochromators, respectively, while the output beam divergence is twice that of the asymmetric Bartels monochromator. These results demonstrate the advantage of the proposed monochromator assembly in cases where the resolution can be partially sacrificed in favour of higher transmittance while still maintaining high beam collimation. Weakly scattering samples such as nanostructures are an example. A general advantage of the new monochromator is a significant reduction in the exposure time required to collect usable experimental data. A comparison of the theoretical and experimental results also reveals the current limitations of the technology of polishing hard-to-reach surfaces in X-ray crystal optics.

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13

Ardana, I. Made, and Yohannes Sardjono. "OPTIMIZATION OF A NEUTRON BEAM SHAPING ASSEMBLY DESIGN FOR BNCT AND ITS DOSIMETRY SIMULATION BASED ON MCNPX." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 19, no. 3 (October 10, 2017): 121. http://dx.doi.org/10.17146/tdm.2017.19.3.3582.

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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

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14

Avagyan, R., R. Avetisyan, V. Ivanyan, and I. Kerobyan. "Geant4 Simulations of a Beam Shaping Assembly Design and Optimization for Thermal/Epithermal Neutrons." Acta Physica Polonica B 48, no. 10 (2017): 1693. http://dx.doi.org/10.5506/aphyspolb.48.1693.

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15

Fauzi, Arief, Afifah Hana Tsurayya, Ahmad Faisal Harish, and Gede Sutresna Wijaya. "Beam Shaping Assembly Optimization for Boron Neutron Capture Therapy Facility Based on Cyclotron 30 MeV as Neutron Source." ASEAN Journal on Science and Technology for Development 35, no. 3 (December 24, 2018): 183–86. http://dx.doi.org/10.29037/ajstd.536.

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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.

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16

Ardana, I. Made, Kusminarto Kusminarto, and Yohannes Sardjono. "Optimization of a Beam Shaping Assembly Design for Boron Neutron Capture Cancer Therapy Facility Based on 30 MeV Cyclotron." Indonesian Journal of Physics and Nuclear Applications 1, no. 3 (October 31, 2016): 128. http://dx.doi.org/10.24246/ijpna.v1i3.128-137.

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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.

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17

Kasesaz, Yaser, and Marjan Karimi. "A novel design of beam shaping assembly to use D-T neutron generator for BNCT." Applied Radiation and Isotopes 118 (December 2016): 317–25. http://dx.doi.org/10.1016/j.apradiso.2016.09.029.

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18

Naeem, Hamza, Chaobin Chen, Huaqing Zheng, and Jing Song. "Optimization of beam shaping assembly based on D-T neutron generator and dose evaluation for BNCT." Journal of the Korean Physical Society 70, no. 8 (April 2017): 816–21. http://dx.doi.org/10.3938/jkps.70.816.

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19

Gulo, Desman P., Suryasatriya T., Slamet Santosa, and Y. Sardjono. "Desain Beam Shaping Assembly (BSA) berbasis D-D Neutron Generator 2,45 MeV untuk Uji Fasilitas BNCT." INDONESIAN JOURNAL OF APPLIED PHYSICS 5, no. 02 (December 20, 2015): 25. http://dx.doi.org/10.13057/ijap.v5i02.280.

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<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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20

Bilalodin, G. B. Suparta, A. Hermanto, D. S. Palupi, Y. Sardjono, and Rasito. "Optimization and analysis of neutron distribution on 30 MeV cyclotron-based double layer beam shaping assembly (DLBSA)." Nuclear Physics and Atomic Energy 20, no. 1 (March 25, 2019): 70–75. http://dx.doi.org/10.15407/jnpae2019.01.070.

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21

Ganda, Francesco, Jasmina Vujic, Ehud Greenspan, and Ka-Ngo Leung. "Compact D-D Neutron Source-Driven Subcritical Multiplier and Beam-Shaping Assembly for Boron Neutron Capture Therapy." Nuclear Technology 172, no. 3 (December 2010): 302–24. http://dx.doi.org/10.13182/nt10-a10939.

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22

Fantidis, Jacob G., and G. Nicolaou. "Optimization of Beam Shaping Assembly design for Boron Neutron Capture Therapy based on a transportable proton accelerator." Alexandria Engineering Journal 57, no. 4 (December 2018): 2333–42. http://dx.doi.org/10.1016/j.aej.2017.08.004.

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23

Asnal, M., T. Liamsuwan, and T. Onjun. "An evaluation on the design of beam shaping assembly based on the D-T reaction for BNCT." Journal of Physics: Conference Series 611 (May 7, 2015): 012031. http://dx.doi.org/10.1088/1742-6596/611/1/012031.

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24

Fantidis, J. G. "Beam shaping assembly study for BNCT facility based on a 2.5 MeV proton accelerator on Li target." Journal of Theoretical and Applied Physics 12, no. 4 (December 2018): 249–56. http://dx.doi.org/10.1007/s40094-018-0312-1.

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25

Nishitani, Takeo, Sachiko Yoshihashi, Yuuki Tanagami, Kazuki Tsuchida, Shogo Honda, Atsushi Yamazaki, Kenichi Watanabe, Yoshiaki Kiyanagi, and Akira Uritani. "Neutronics Analyses of the Radiation Field at the Accelerator-Based Neutron Source of Nagoya University for the BNCT Study." Journal of Nuclear Engineering 3, no. 3 (July 13, 2022): 222–32. http://dx.doi.org/10.3390/jne3030012.

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The Nagoya University Accelerator-driven Neutron Source (NUANS) is an accelerator-based neutron source by 7Li(p,n)7Be reaction with a 2.8 MeV proton beam up to 15 mA. The fast neutrons are moderated and shaped to beam with a Beam Shaping Assembly (BSA). NUANS is aiming at the basic study of the Boron Neutron Capture Therapy (BNCT) such as an in vitro cell-based irradiation experiment using a water phantom. Moreover, the BSA is developed as a prototype of one for human treatment. We have evaluated the radiation field of NUANS by a Monte Carlo code PHITS. It is confirmed that the radiation characteristics at the BNCT outlet meet the requirement of IAEA TECDOC-1223. Additionally, the radiation field in the water phantom located just in front of the BSA outlet is calculated. In the in vitro irradiation experiment, the boron dose of 30 Gy-eq, which is the dose to kill tumor cells, is expected for 20 min of irradiation at the beam current of 15 mA.

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26

Taskaev, Sergey, Evgenii Berendeev, Marina Bikchurina, Timofey Bykov, Dmitrii Kasatov, Iaroslav Kolesnikov, Alexey Koshkarev, et al. "Neutron Source Based on Vacuum Insulated Tandem Accelerator and Lithium Target." Biology 10, no. 5 (April 21, 2021): 350. http://dx.doi.org/10.3390/biology10050350.

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A compact accelerator-based neutron source has been proposed and created at the Budker Institute of Nuclear Physics in Novosibirsk, Russia. An original design tandem accelerator is used to provide a proton beam. The proton beam energy can be varied within a range of 0.6–2.3 MeV, keeping a high-energy stability of 0.1%. The beam current can also be varied in a wide range (from 0.3 mA to 10 mA) with high current stability (0.4%). In the device, neutron flux is generated as a result of the 7Li(p,n)7Be threshold reaction. A beam-shaping assembly is applied to convert this flux into a beam of epithermal neutrons with characteristics suitable for BNCT. A lot of scientific research has been carried out at the facility, including the study of blistering and its effect on the neutron yield. The BNCT technique is being tested in in vitro and in vivo studies, and the methods of dosimetry are being developed. It is planned to certify the neutron source next year and conduct clinical trials on it. The neutron source served as a prototype for a facility created for a clinic in Xiamen (China).

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27

Liu, Zheng, Gang Li, and Linmao Liu. "Feasibility of sealed D–T neutron generator as neutron source for liver BNCT and its beam shaping assembly." Applied Radiation and Isotopes 86 (April 2014): 1–6. http://dx.doi.org/10.1016/j.apradiso.2013.12.031.

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28

Rahmani, Faezeh, and Majid Shahriari. "Beam shaping assembly optimization of Linac based BNCT and in-phantom depth dose distribution analysis of brain tumors for verification of a beam model." Annals of Nuclear Energy 38, no. 2-3 (February 2011): 404–9. http://dx.doi.org/10.1016/j.anucene.2010.10.001.

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29

Tian Yong-Shun, Hu Zhi-Liang, Tong Jian-Fei, Chen Jun-Yang, Peng Xiang-Yang, and Liang Tian-Jiao. "Design of beam shaping assembly based on 3.5 MeV radio-frequency quadrupole proton accelerator for boron neutron capture therapy." Acta Physica Sinica 67, no. 14 (2018): 142801. http://dx.doi.org/10.7498/aps.67.20180380.

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30

Martı́n, Guido, and Arian Abrahantes. "A conceptual design of a beam-shaping assembly for boron neutron capture therapy based on deuterium-tritium neutron generators." Medical Physics 31, no. 5 (April 15, 2004): 1116–22. http://dx.doi.org/10.1118/1.1702308.

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31

Faghihi, F., and S. Khalili. "Beam shaping assembly of a D–T neutron source for BNCT and its dosimetry simulation in deeply-seated tumor." Radiation Physics and Chemistry 89 (August 2013): 1–13. http://dx.doi.org/10.1016/j.radphyschem.2013.02.003.

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32

Burlon, A. A., S. Girola, A. A. Valda, D. M. Minsky, A. J. Kreiner, and G. Sánchez. "Design of a beam shaping assembly and preliminary modelling of a treatment room for accelerator-based BNCT at CNEA." Applied Radiation and Isotopes 69, no. 12 (December 2011): 1688–91. http://dx.doi.org/10.1016/j.apradiso.2011.05.003.

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33

Kasesaz, Y., H. Khalafi, and F. Rahmani. "Optimization of the beam shaping assembly in the D–D neutron generators-based BNCT using the response matrix method." Applied Radiation and Isotopes 82 (December 2013): 55–59. http://dx.doi.org/10.1016/j.apradiso.2013.07.008.

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Sahoo, G. S., S. D. Sharma, S. P. Tripathy, and T. Bandyopadhyay. "Design and dosimetric evaluation of beam shaping assembly for BNCT of compact D–T neutron generator by Monte Carlo simulation." Biomedical Physics & Engineering Express 4, no. 1 (December 22, 2017): 015018. http://dx.doi.org/10.1088/2057-1976/aa96e0.

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Hsieh, M., Y. Liu, and L. Nie. "SU-F-T-183: Design of a Beam Shaping Assembly of a Compact DD-Based Boron Neutron Capture Therapy System." Medical Physics 43, no. 6Part15 (June 2016): 3503–4. http://dx.doi.org/10.1118/1.4956320.

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Kim, Kyung-O., Sang Hoon Jung, Soon Young Kim, Gi-Dong Kim, and Jong Kyung Kim. "Performance Evaluation of a Beam-shaping Assembly for Accelerated-BNCT Using the Neutron Generation Experiment of7Li(p,n)7Be Reaction." Journal of Nuclear Science and Technology 45, sup5 (June 2008): 143–46. http://dx.doi.org/10.1080/00223131.2008.10875807.

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Zaidi, L., M. Belgaid, S. Taskaev, and R. Khelifi. "Beam shaping assembly design of 7Li(p,n)7Be neutron source for boron neutron capture therapy of deep-seated tumor." Applied Radiation and Isotopes 139 (September 2018): 316–24. http://dx.doi.org/10.1016/j.apradiso.2018.05.029.

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Burlon, A. A., A. J. Kreiner, A. A. Valda, D. M. Minsky, H. R. Somacal, M. E. Debray, and P. Stoliar. "Optimization of a neutron production target and a beam shaping assembly based on the 7Li(p,n)7Be reaction for BNCT." Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 229, no. 1 (February 2005): 144–56. http://dx.doi.org/10.1016/j.nimb.2004.10.090.

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39

Bikchurina, Marina, Timofey Bykov, Dmitrii Kasatov, Iaroslav Kolesnikov, Aleksandr Makarov, Ivan Shchudlo, Evgeniia Sokolova, and Sergey Taskaev. "The Measurement of the Neutron Yield of the 7Li(p,n)7Be Reaction in Lithium Targets." Biology 10, no. 9 (August 24, 2021): 824. http://dx.doi.org/10.3390/biology10090824.

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A compact accelerator-based neutron source has been proposed and created at the Budker Institute of Nuclear Physics in Novosibirsk, Russia. An original design tandem accelerator is used to provide a proton beam. The neutron flux is generated as a result of the 7Li(p,n)7Be threshold reaction using the solid lithium target. A beam shaping assembly is applied to convert this flux into a beam of epithermal neutrons with characteristics suitable for BNCT. The BNCT technique is being tested in in vitro and in vivo studies, and dosimetry methods are being developed. Currently, the BNCT technique has entered into clinical practice in the world: after successful clinical trials, two clinics in Japan began treating patients, and four more BNCT clinics are ready to start operating. The neutron source proposed at the Budker Institute of Nuclear Physics served as a prototype for a facility created for a clinic in Xiamen (China). It is planned to equip the National Medical Research Center of Oncology (Moscow, Russia) and National Oncological Hadron Therapy Center (Pavia, Italy) with the same neutron sources. Due to the impending use of an accelerator neutron source for treating patients, the validation of the neutron yield of the 7Li(p,n)7Be reaction in lithium metal targets is required. The theoretical neutron yield has not been evaluated experimentally so far.

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Hiraga, F. "Optimum design and criticality safety of a beam-shaping assembly with an accelerator-driven subcritical neutron multiplier for boron neutron capture therapies." Applied Radiation and Isotopes 106 (December 2015): 84–87. http://dx.doi.org/10.1016/j.apradiso.2015.07.029.

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Hang, Shuang, Xiaobin Tang, Diyun Shu, Yuanhao Liu, Changran Geng, Chunhui Gong, Haiyan Yu, and Da Chen. "Monte Carlo study of the beam shaping assembly optimization for providing high epithermal neutron flux for BNCT based on D–T neutron generator." Journal of Radioanalytical and Nuclear Chemistry 310, no. 3 (August 29, 2016): 1289–98. http://dx.doi.org/10.1007/s10967-016-5001-4.

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Cerullo, N., J. Esposito, and K. N. Leung. "Irradiation facility for boron neutron capture therapy application based on a rf-driven D–T neutron source and a new beam shaping assembly (abstract)." Review of Scientific Instruments 73, no. 2 (February 2002): 938. http://dx.doi.org/10.1063/1.1433920.

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Rasouli, Fatemeh S., and S. Farhad Masoudi. "Design and optimization of a beam shaping assembly for BNCT based on D–T neutron generator and dose evaluation using a simulated head phantom." Applied Radiation and Isotopes 70, no. 12 (December 2012): 2755–62. http://dx.doi.org/10.1016/j.apradiso.2012.08.008.

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Cerullo, Nicola, Juan Esposito, Ka Ngo Leung, and Salvatore Custodero. "An irradiation facility for Boron Neutron Capture Therapy application based on a radio frequency driven D–T neutron source and a new beam shaping assembly." Review of Scientific Instruments 73, no. 10 (October 2002): 3614–18. http://dx.doi.org/10.1063/1.1505128.

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Mu’Alim, Muhammad, and Yohannes Sardjono. "MODELING THE RADIATION SHIELDING OF BORON NEUTRON CAPTURE THERAPY BASED ON 2.4 MEV D-D NEUTRON GENERATOR FACILITY." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 20, no. 1 (January 25, 2018): 13. http://dx.doi.org/10.17146/tdm.2018.20.1.3633.

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Radiation shield at Boron Neutron Capture Therapy (BNCT) facility based on D-D Neutron Generator 2.4 MeV has been modified with pre-designed beam shaping assembly (BSA). Modeling includes the material and thickness used in the radiation shield. This radiation shield is expected to protect workers from radiation doses rate that is not exceed 20 mSv·year-1 of dose limit values. The selected materials are barite, paraffin, polyethylene and lead. Calculations were performed using the MCNPX program with tally F4 to determine the dose rate coming out of the radiation shield not exceeding the radiation dose rate of 10 μSv·hr-1. Design 3 was chosen as the recommended model of the four models that have been made. The 3rd shield design uses a 100 cm thickness of barite concrete as primamary layer to surrounding 100 cm x 100 cm x 166.4 cm room, and a 40 cm borated polyethylene surrounding the barite concrete material. Then 10 cm barite concrete and 10 cm of borated polyethylene are added to reduce the primary radiation straight from the BSA after leaving the main layer. The largest dose rate was 4.58 μSv·h-1 on cell 227 and average radiation dose rate 0.65 μSv·hr-1. The dose rates are lower than the lethal dose that is allowed by BAPETEN for radiation worker lethal dose.Keywords: Radiation shield, tally, radiation dose rate, BSA, BNCT PEMODELAN PERISAI RADIASI PADA FASILITAS BORON NEUTRON CAPTURE THERAPY BERBASIS GENERATOR NEUTRON D-D 2,4 MeV. Telah dimodelkan perisai radiasi pada fasilitas Boron Neutron Capture Therapy (BNCT) berbasis reaksi D-D pada Neutron Generator 2,4 MeV dengan Beam Shaping Assembly (BSA) yang telah didesain sebelumnya. Pemodelan ini dilakukan untuk memperoleh suatu desain perisai radiasi untuk fasilitas BNCT berbasis generator neutron 2,4 MeV. Pemodelan dilakukan dengan cara memvariasikan bahan dan ketebalan perisasi radiasi. Bahan yang dipilih adalah beton barit, parafin, polietilen terborasi dan timbal. Perhitungan dilakukan menggunakan program MCNPX dengan tally F4 untuk menentukan laju dosis yang keluar dari perisai radiasi. Desain periasi radiasi dinyatakan optimal jika radiasi yang dihasilkan diluar perisai radiasi tidak melebihi Nilai Batas Dosis (NBD) yang telah ditentukan oleh BAPETEN. Hasilnya, diperoleh suatu desain perisai radiasi menggunakan lapisan utama beton barit setebal 100 cm yang mengelilingi ruangan 100 cm x 100 cm x 166,4 cm dan polietilen terborasi 40 cm yang mengelilingi bahan beton barit. Kemudian ditambahkan beton barit 10 cm dan polietilen terborasi 10 cm untuk mengurangi radiasi primer yang lurus dari BSA setelah keluar dari lapisan utama. Laju dosis terbesar adalah 4,58 μSv·jam-1 pada sel 227 dan laju dosis rata-rata yang dihasilkan adalah sebesar 0,65 µSv·jam-1. Nilai laju dosis tersebut masih dibawah ambang batas NBD yang diperbolehkan oleh BAPETEN untuk pekerja radiasi.Kata kunci: Perisai radiasi, tally, laju dosis radiasi, BSA, BNCT

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Pan, C. T., and H. Hocheng. "Prediction of Extent of Heat Affected Zone in Laser Grooving of Unidirectional Fiber-Reinforced Plastics." Journal of Engineering Materials and Technology 120, no. 4 (October 1, 1998): 321–27. http://dx.doi.org/10.1115/1.2807021.

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Laser has been widely used in various industrial applications including machining. However, in shaping operation of composite material after curing, thermal damage associated with laser energy can be produced. It leads to poor assembly tolerance and long-term performance deterioration. The current research investigates the anisotropic formation of the heat affected zone (HAZ) in unidirectional fiber-reinforced plastics induced by laser grooving. Preliminary analytical and experimental analysis reveal that the laser energy per unit length and fiber orientation-dependent thermal conductivity primarliy determine the induced thermal damage. The extent of HAZ is estimated by the isotherm of the matrix char temperature. Heat conduction is maximum along the fibers, and the HAZ shape is thus affected by the beam scanning direction relative to fiber orientation. The study investigates the grooving of laminated unidirectional carbon/epoxy, which demonstrates clear thermal damage in 90 degree (i.e., perpendicular grooving), 60 degree, 30 degree, and 0 degree (i.e., parallel grooving) relative to the fiber axis. A theoretical analysis based on moving point heat source is adopted to determine the extent of thermal damage in correlation with process parameters and material properties. Mirror Image Method is used for specimen of finite thickness. Considerations of temperature-dependence of thermal conductivity and the emmerged heat source further improve the prediction of HAZ. While HAZ in grooving along the principal material axes can be solved analytically, conductivity ellipsoid and finite difference can calculate the extent of HAZ induced by grooving in any direction relative to fiber axis.

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Tsai, Min-An, Peichen Yu, C. H. Chiu, H. C. Kuo, T. C. Lu, and S. H. Lin. "Self-Assembled Two-Dimensional Surface Structures for Beam Shaping of GaN-Based Vertical-Injection Light-Emitting Diodes." IEEE Photonics Technology Letters 22, no. 1 (January 2010): 12–14. http://dx.doi.org/10.1109/lpt.2009.2034470.

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Teng, Shuqing N., Chi Xu, Licheng Teng, and Jens-Christian Svenning. "Long-term effects of cultural filtering on megafauna species distributions across China." Proceedings of the National Academy of Sciences 117, no. 1 (December 23, 2019): 486–93. http://dx.doi.org/10.1073/pnas.1909896116.

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Human activities currently play a dominant role in shaping and eroding Earth’s biodiversity, but the historical dynamics leading to this situation are poorly understood and contentious. Importantly, these dynamics are often studied and discussed without an emphasis on cultural evolution, despite its potential importance for past and present biodiversity dynamics. Here, we investigate whether cultural filtering, defined as the impact of cultural evolution on species presence, has driven the range dynamics of five historically widespread megafauna taxa (Asiatic elephant, rhinoceroses, tiger, Asiatic black bear, and brown bear) across China over the past 2 millennia. Data on megafauna and sociocultural history were compiled from Chinese administrative records. While faunal dynamics in China are often linked to climate change at these time scales, our results reveal cultural filtering as the dominant driver of range contractions in all five taxa. This finding suggests that the millennia-long spread of agricultural land and agricultural intensification, often accompanied by expansion of the Han culture, has been responsible for the extirpation of these megafauna species from much of China. Our results suggest that cultural filtering is important for understanding society’s role in the assembly of contemporary communities from historical regional species pools. Our study provides direct evidence that cultural evolution since ancient times has overshadowed climate change in shaping broadscale megafauna biodiversity patterns, reflecting the strong and increasing importance of sociocultural processes in the biosphere.

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Piekarski, Maciej. "Floor Slabs Made from Topologically Interlocking Prefabs of Small Size." Buildings 10, no. 4 (April 15, 2020): 76. http://dx.doi.org/10.3390/buildings10040076.

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In this article, the issue of constructing slabs from unified small elements, which are connected together into a stable structure by topological interlocking, is considered. The state-of-the-art methods in this topic are presented, as well as the results of the author’s original research. The author has expanded the well-known concept of shaping square slabs from square prefabs by the aggregation of triangular and hexagonal slabs from prefabs in the shape of equilateral triangles, regular hexagons, and rhombuses. Each of the slabs can be modelled with upper and bottom surfaces, either both relief, both smooth, or one relief and the other smooth. The slabs can be modelled in different ways, and each one results in intriguing floor and ceiling patterns. All of the slabs can co-operate with grillages made of steel beams, which can be constructed before filling with the prefabricated slab, which is a novel idea. Reversing the assembly order, as compared to that used in the literature, is made possible thanks to division of these elements into parts, to form a keystone which is inserted into the slab as a final step.

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Guðmundsdóttir, R., AK Kreiling, BK Kristjánsson, VÞ Marteinsson, and S. Pálsson. "Ciliate diversity in cold water spring sources in Iceland." Aquatic Microbial Ecology 84 (June 18, 2020): 191–203. http://dx.doi.org/10.3354/ame01936.

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Cold groundwater springs at the edges of lava fields along the volcanic active zone in Iceland are an interesting habitat, presenting an ecotone between groundwater, surface water and the terrestrial ecosystems. They are categorized as fennoscandian mineral-rich springs according to the European Nature Information System (EUNIS) classification (C2.111 European Environmental Agency) and have a high conservation value. They are also an island-like phenomena in the landscape and, together with the stable chemical and physical properties of the groundwater, make excellent study sites for testing questions regarding community assembly theory. To explore the biota of these systems, we applied environmental metabarcoding to assess ciliate diversity in this habitat. DNA was extracted and metabarcoding based on the 18S rRNA gene was conducted for (1) water samples and (2) glass beads as support for biomass development. Alpha diversity for ciliate communities in the spring sources increased with temperature, and limnocrene springs had fewer, more abundant taxa than rheocrene springs. Differences were observed between the water samples and the glass bead samples, mainly in terms of abundance. When considering only the water samples, no variation was found among spring source communities, indicating that stochastic processes such as dispersal and ecological drift might be important in shaping the community composition.

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