Perancangan Kolimator Neutron pada Beam Port Singgung Reaktor Kartini untuk Boron Neutron Capture Theraphy

CYNTHIA MAHARANI, Dwi Satya Palupi, S.Si, M.Si; Prof. Ir. Yohannes Sardjono

2014 | Skripsi | FISIKA

Telah dilakukan perancangan kolimator neutron pada beam port singgung Reaktor Kartini untuk aplikasi Boron Neutron Capture Therapy (BNCT). BNCT merupakan salah satu metode radioterapi untuk penyembuhan kanker yang tengah dikembangkan. BNCT memanfaatkan senyawa boron yang diiradiasi oleh berkas neutron untuk menghancurkan sel kanker. Perancangan kolimator dilakukan dengan simulasi menggunakan program Monte Carlo N-Particle (MCNP5) agar diperoleh berkas neutron keluaran dari beam port singgung yang memenuhi rekomendasi International Atomic Energy Agency (IAEA) untuk aplikasi BNCT. Hasil yang diperoleh berupa rancangan kolimator dengan dinding berbahan timbal (Pb) setebal 4 cm dengan moderator berbahan aluminium (Al) setebal 0,5 cm. Dengan rancangan ini, berkas neutron yang dihasilkan memiliki karakteristik: fluks neutron epitermal 1,25 x 108 n/cm2.s , dosis neutron cepat per neutron epitermal 5,56 x 10-14 Gy.cm2/n, dosis gamma per neutron epitermal 9,71 x 10-13Gy.cm2/n, rasio antara fluks neutron termal dengan neutron epitermal 0,34, dan rasio antara arus neutron dengan fluks neutron total 0,72.

A conceptual design of neutron collimator on tangential beam port in Kartini Research Reactor for Boron Neutron Capture Therapy (BNCT) had been made. BNCT is one of the radiotherapy methods that is being developed in many countries. BNCT utilizing the boron compound irradiated with neutron beam to destroy the cancer cell. In order to fulfill the recommendation made by International Atomic Energy Agency (IAEA) for BNCT application, design of neutron collimator was made using a program named Monte Carlo N-Perticle (MCNP5) through series of simulations. This resulting in a collimator design using lead (Pb) as collimator wall material and Aluminium (Al) as moderator material. The thickness of collimator wall was 4 cm while the moderator was 0,5 cm in its thickness. This collimator design was then simulated and resulting in a neutron beam with following characteristics: 1,25 x 108 n/cm2.s of epitermal neutron flux, 5,56 x 10-14 Gy.cm2/n of fast neutron dose per epitermal neutron, 9,71 x 10-13Gy.cm2/n of gamma dose per epitermal neutron, 0,34 of ratio between termal neutron and epitermal neutron flukx, and also 0,72 of ratio between neutron current and total neutron flux.

Kata Kunci : bnct, cancer, neutron collimator, mcnp