DESAIN UJI KLINIS BORON NEUTRON CAPTURE THERAPY (BNCT) PADA KANKER PAYUDARA MENGGUNAKAN SUMBER RADIASI COAXIAL COMPACT NEUTRON GENERATOR D-D DENGAN METODE SIMULASI MONTE CARLO N-PARTICLE EXTENDED (MCNPX); CLINICAL TRIAL DESIGN OF BORON NEUTRON CAPTURE THERAPY ON BREAST CANCER USING D-D COAXIAL COMPACT NEUTRON GENERATOR AS NEUTRON SOURCE BY MONTE CARLO N-PARTICLE EXTENDED (MCNPX) SIMULATION METHOD

Pasaribu, Rosenti, Kusminarto

2015 | Disertasi | FMIPA

A clinical trial simulation of Boron Neutron Capture Therapy (BNCT) for breast cancer was conducted at National Nuclear Energy Agency Yogyakarta, Indonesia. This was motivated by high rate of breast cancer in the world, especially in Indonesia. BNCT is a type of therapy by nuclear reaction 10B(n,?)7Li that produces kinetic energy in the total of 2.79 MeV. High Linear Energy Transfer (LET) radiation of ?-particle and recoil 7Li would locally deposit their energy in a range of 5-9 ?m, which corresponds to the human cell diameter. Fast neutron coming out of Compact Neutron Generator (CNG) was moderated using Fe and MgF2 materials. A collimator, along with breast cancer and the corresponding organ at risk were designed compatible to Monte Carlo N-Particle eXtended (MCNPX). The radiation was simulated by the MCNPX software and the physical quantities were counted by tally MCNPX codes. The highest neutron thermal flux was found at a depth of 1.4 cm on fat tissue. En face and upward intersection radiation techniques were adopted for the breast cancer radiation. The average dose rate of radiation used on breast cancer was found to be 1.72×10-5 Gy/s for the en face method and 8.98×10-6 Gy/s for the upward intersection method. Dose 50±3 Gy was given into cancer cell, (4.18±0.06) ×10-2 Gy into heart and (8.16±0.06) ×10-2 Gy into lung for 806.34 hours irradiation.

Kata Kunci : Boron Neutron Capture Therapy; Compact Neutron Generator; Breast Cancer; Dosimetry