MONTE CARLO N PARTICLE EXTENDED (MCNPX) RADIATION SHIELD MODELLING ON BORON NEUTRON CAPTURE THERAPY FACILITY USING D-D NEUTRON GENERATOR 2.4 MeV

Yohannes Sardjono

doi:10.24246/ijpna.v4i2.58-65

Yohannes Sardjono Pusat Sains Dan Teknologi Akselerator; Badan Tenaga Nuklir Nasional (PSTA BATAN) / Center of Science and Technology of Accelerator; National Nuclear Energy Agency

DOI: https://doi.org/10.24246/ijpna.v4i2.58-65

Keywords: Internal Dose, Radiation Worker, BNCT, MCNPX, BSA.

Abstract

Based Studies were carried out to analyze the internal dose of radiation for workers at Boron Neutron Capture Therapy (BNCT) facility base on Cyclotron 30 MeV with BSA and a room that was actually designed before. This internal dose analyzation included interaction between neutrons and air. The air contained N2 (72%), O₂(20%), Ar (0.93%), CO₂, Neon, Kripton, Xenon, Helium and Methane. That internal dose to the worker should be below the dose limit for radiation workers which is an amount of 20 mSv/years. From the particles that are present in the air, only Nitrogen and Argon can change into radioactive element. Nitrogen-14 activated to Carbon-14, Nitrogen-15 activated to Nitrogen-16, and Argon-40 activated to Argon-41. Calculation using tally facility in Monte Carlo N Particle version Extended (MCNPX) program for calculated Neutron flux in the air 3.16x10⁷ Neutron/cm²s. The room design in the cancer facility has a measurement of 200 cm in length, 200 cm in width, and 166.40 cm in height. Neutron flux can be used to calculate the reaction rate which is 80.1x10^-2 reaction/cm³s for carbon-14 and 8.75x10^-5 reaction/cm³s. The internal dose exposed to the radiation worker is 9.08E-9 µSv.

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