DOSIMETRI BORON NEUTRON CAPTURE THERAPY PADA KANKER HATI (HEPATOCELLULAR CARCINOMA) MENGGUNAKAN MCNP-CODE DENGAN SUMBER NEUTRON DARI KOLOM TERMAL REAKTOR KARTINI

• Main Authors: , IRHAS, , Dr. Ir. Andang Widi Harto
• Format: Theses and Dissertations NonPeerReviewed
• Published: [Yogyakarta] : Universitas Gadjah Mada 2014
• Subjects: ETD
• Online Access: https://repository.ugm.ac.id/129946/; http://etd.ugm.ac.id/index.php?mod=penelitian_detail&sub=PenelitianDetail&act=view&typ=html&buku_id=70355
• Institution: Universitas Gadjah Mada

Boron Neutron Capture Therapy (BNCT) using phisycs principle when boron-10 irradiated by low energy neutron (thermal neutron). boron and thermal neutron reaction produced boron-11m (t1/2=10-23 s). Boron-11m decay emited alpha, lithium-7 particle and gamma ray. Irradiated time needed to ensure cancer dose enough. Liver cancer was primary malignant who located in liver (Hepatocellular carsinoma). Malignant in liver were different to metastastic from Breast, Colon Cancer, and the other. This condition was Metastatsic Liver Cancer. Monte Carlo method used by Monte Carlo N-Particle (MCNP) Software. Probabilistic approach used for probability of interaction occurred and record refer to caracteristic of particle and material. In this case, thermal neutron produced by model of Collimated Thermal Column Kartini Research Nuclear Reactor, Yogyakarta. Modelling organ and source used liver organ who contain of cancer tissue and research reactor. Variation of boron concentration was 20, 25, 30, 35, 40, 45, dan 47 μg/g cancer. Output of MCNP calculation were neutron scattering dose, gamma ray dose and neutron flux from reactor. Neutron flux used to calculated alpha, proton and gamma ray dose from interaction of tissue material and thermal neutron. Variation of boron concentration result dose rate to every variation were 0,059