Abstract
Shielding design is necessary for brachytherapy treatment room in order to protect the general public and employees. The main objective of this study was to investigate whether the protective unit of our Brachytherapy Centre provided adequate protection to the health and safety assessment of radiobiological impact. In this study, we estimated the effect of radiobiological protection from a single Ir-192 brachytherapy source in Brachytherapy center by using MCNP5 Monte Carlo measurements. The room was based on the design specifications for the HDR 192 Ir treatment was modeled. The estimated dose rate range for HDR 192 Ir and public buildings is (0.45 - 0.64): (micro sivert) μSv/hour. Dose rates measured data for the current setup Brachytherapy HDR unit was approved and agreed quiet well with recommendation of International Atomic Energy Agency. The measured dose rate for public areas and controlled areas, compared with the reference value of 7.5 μSv/h and 0.5 μSv/h and concluded that we have enough shielding to the source but an over estimate with experimental measurements had been seen.
Highlights
Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes
MCNPX (Monte Carlo N-Particle extended) is developed at Los Alamos National Laboratory, and is capable of simulating particle interactions of 34 different types of particles and 2000+ heavy ions at most energies, including those simulated by MCNP [2]
This code is suitable for such shielding investigation because of an extensive library of cross sections for materials that are use for shielding, and compare the experimental calculations with MCNP5 simulation in occupied areas and verify whether the shielding provides adequate protection for the staff and the public in its current operational state and make appropriate recommendations to address any radiological health and safety hazards identified
Summary
Monte Carlo N-Particle Transport Code (MCNP) is a software package for simulating nuclear processes. It is distributed within the United States by the Radiation Safety Information Computational Center in Oak Ridge, TN and internationally by the Nuclear Energy Agency in Paris, France. It is used primarily for the simulation of nuclear processes, such as fission, but has the capability to simulate particle interactions involving neutrons, photons, and electrons. MCNPX (Monte Carlo N-Particle extended) is developed at Los Alamos National Laboratory, and is capable of simulating particle interactions of 34 different types of particles (nucleons and ions) and 2000+ heavy ions at most energies, including those simulated by MCNP [2] Both codes can be used to judge whether or not nuclear systems are critical and to determine doses from sources, among other things. Mahdieh Brachytherapy had been invented in 2012 and had a treatment in 5 days a week
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