A Design of Boron Neutron Capture Therapy for Cancer Treatment in Indonesia

• DOI: 10.24246/ijpna.v1i1.1-13
• Publication Date: 2017-11-01T02:56:28Z
• Authors: Yohannes Sardjono; Susilo Widodo; Irhas Irhas; Hilmi Tantawy
• Keywords: Neutron capture; Neutron generator

Boron Neutron Capture Therapy (BNCT) is an advanced form of radiotherapy technique that potentially superior to all conventional techniques for cancer treatment, as it targeted at killing individual cancerous cells with minimal damage surrounding healthy cells. After decades development, BNCT has reached clinical-trial stages in several countries, mainly treating challenging cancers such malignant brain tumors. The Indonesian consortium already developed the design many cases type using neutron sources. main objective are development technology package which consists a non nuclear reactor source based on cyclotron and compact generator technique, boron-carrying pharmaceutical, user-friendly treatment platform automatic operation feedback system well commercialization though franchised network clinics worldwide. will offering participate carrier pharmaceuticals testing, generators provision neutrons from 100 kW Kartini Research Reactor guide validate development. Studies were carried out collimator results epithermal beam by means Monte Carlo N-Particle 5 (MCNP5) codes. within output thermal power was used source. criteria IAEA’s recommendation. All materials varied size, according value mean free path each. simulations indicated cm thick Ni wall, 60 Al moderator, 15 60Ni filter, 1,5 Bi "-ray shielding, 3 6Li2CO3-polyethylene delimiter, 3-5 aperture minimum flux 7,8 x 108 n.cm-2.s-1, maximum fast components of, respectively, 1,9 10-13 Gy.cm2.n-1 1,8 Gy.cm2.n-1, per ratio 0,009, directionality 0,72, could be produced. did not fully pass criteria, since still below recommended value, 1,0 109 n.cm-2.s-1. Nonetheless, usable exceeded When this surrounded 8 graphite, characteristics became better passed up 1,7 feasible vivo experiment study i.e.; liver lung curcinoma. In case, produced model Collimated Thermal Column Nuclear Reactor, Yogyakarta. Sodium boroncaptate (BSH) research. BSH had effected radiation quality factor 0.8 health tissue 2.5 tissue. Modelling organ who contain research reactor. Variation boron concentration 20, 25, 30, 35, 40, 45, 47 $g/g cancer. Output MCNP calculation scattering dose, gamma ray dose Given advantages low density owned lungs, hence solid option can utilized eradicate cell lungs. carcinoma Compact Generator (CNG) deuterium-tritium boronophenylalanine (BPA). boron-10 compound study; i.e. variations 20; 25; 30; 35; 40 45 μg.g-1 tissues. Ideally, primary solemnly expected contribute therapy alpha but secondary dose; proton caused due interaction spectra simply omitted. Thus, desired MCNPX; tally, flux, photon dose. variation result rate every were0,042; 0,050; 0,058; 0,067; 0,074; 0,082; 0,085 Gy/sec. Irradiation time need 1194,687 sec (19 min 54 sec);999,645 (16 39 sec); 858,746 (14 19 743,810 (12 24 675,156 (11 608,480 (10 585,807sec (9 sec). resulted each variables respectively 0.003145, 0.003657, 0.00359, 0.00385, 0.00438 0.00476 Gy.sec-1 . irradiated needed 375.34, 357.55, 287.58, 284.95, 237.84 219.84 minutes.