scholarly journals A Conceptual Design Optimization of Collimator With 181Ta as Neutron Source for Boron Neutron Capture Therapy Based Cyclotron Using Computer Simulation Program Monte Carlo N Particle Extended

2017 ◽  
Vol 2 (2) ◽  
pp. 83
Author(s):  
Jans P B Siburian ◽  
Andang Widi Harto ◽  
Yohannes Sardjono

The optimization of collimator with 30 MeV cyclotron as neutron source and <sup>181</sup>Ta as its proton target. cyclotron assumed work at 30 MeV power with 1 mA and 30 kW operation condition. Criteria of design based on IAEA’s recommendation. Using MCNPX as simulator, the result indicated that with using <sup>181</sup>Ta as target material with 0.55 cm thickness and 19 cm diameter, 25 cm and 45 cm PbF<sub>2</sub> as reflector and back reflector, 30 cm <sup>32</sup>S as a moderator, 20 cm <sup>60</sup>Ni as fast neutron filter, 2 cm <sup>209</sup>Bi as gamma filter, 1 cm <sup>6</sup>Li<sub>2 </sub>CO<sub>3-</sub> polyethylenes as thermal neutron filter, and 23 cm diameter of aperture, an epithermal neutron beam with intensity 4.37 x 10<sup>9</sup> n.cm<sup>-2</sup>.s<sup>-1</sup>, fast neutron and gamma doses per epithermal neutron of 1.86 x 10<sup>-16 </sup>Gy.cm<sup>2</sup>.n<sup>-1 </sup>and 1.93 x 10<sup>-13</sup>Gy.cm<sup>2</sup>.n<sup>-1</sup>, minimum thermal neutron per epithermal neutron ratio of 0.003, and maximum directionality 0,728, respectively could be produced. The results have passed all the IAEA’s criteria.

2018 ◽  
Vol 35 (3) ◽  
pp. 183-186
Author(s):  
Arief Fauzi ◽  
Afifah Hana Tsurayya ◽  
Ahmad Faisal Harish ◽  
Gede Sutresna Wijaya

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.


2017 ◽  
Vol 2 (3) ◽  
pp. 124
Author(s):  
Bilalodin Bilalodin ◽  
Kusminarto Kusminarto ◽  
Arief Hermanto ◽  
Yohannes Sardjono ◽  
Sunardi Sunardi

<span>A research of design of double layer collimator using </span><sup>9</sup><span>Be(p,n) neutron source has been conducted. The research objective is to design a double layer collimator to obtain neutron sources that are compliant with the IAEA standards. The approach to the design of double layer collimator used the MCNPX code. From the research, it was found that the optimum dimensions of a beryllium target are 0.01 mm in length and 9.5 cm in radius. Collimator consists of a D</span><sub>2</sub><span>O and Al moderator, Pb and Ni as a reflector, and Cd and Fe as a thermal and fast neutron filter. The gamma filter used Bi and Pb. The quality neutron beams emitted from the double layer collimator is specified by five parameters: epithermal neutron flux 1 ×10</span><sup>9</sup><span> n/cm</span><sup>2</sup><span>s; fast neutron dose per epithermal neutron flux 5 ×10</span><sup>13</sup><span> Gy cm</span><sup>2</sup><span>s; gamma dose per epithermal neutron flux 1×10</span><sup>13</sup><span> Gy cm</span><sup>2</sup><span>s; ratio of the thermal neutron flux of epithermal neutron flux 0; and the ratio of epithermal neutron current to total epithermal neutron 0.54.</span>


2018 ◽  
Vol 52 (2) ◽  
pp. 73-76 ◽  
Author(s):  
S. Yu. Taskaev ◽  
V. V. Kanygin ◽  
V. A. Byvaltsev ◽  
A. A. Zaboronok ◽  
O. Yu. Volkova ◽  
...  

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