Open AccessThe use of MNCP-5 particle transport program for calculation of flux radiation exposure in object surface
Author(s) -
Tumpal Pandiangan,
Ika Bali,
Alexander R. J. Silalahi
Publication year - 2020
Publication title -
iop conference series. materials science and engineering
Language(s) - English
Resource type - Journals
eISSN - 1757-899X
pISSN - 1757-8981
DOI - 10.1088/1757-899x/852/1/012174
Subject(s) - radiation , particle radiation , radiation flux , physics , particle (ecology) , neutron , radius , flux (metallurgy) , photon , computational physics , neutron flux , optics , nuclear physics , materials science , charged particle , computer science , oceanography , metallurgy , geology , ion , computer security , quantum mechanics
Calculation of particle or photon flux in three dimensions is needed to facilitate the observation and the real approach of radiation to the observed object. Calculation of the flux of radiation received on an object’s surface can be done using the MCNP-5 particle transport program (Monte Carlo N particle-5). In this study, the radiation source is a neutron particle emitted from the center of the ball with a radius of 0.5 cm with 16 MeV of energy on an object’s surface of an iron ball with a radius of 0.5 cm. The source of neutrons and irradiated objects is in a cube vessel, with a side length of 10 cm and 20 cm. This simulation can be useful as a model for calculating the impact of radiation exposure on the surface of objects in human organs. Flux and the magnitude of the radiation particle’s track on the object’s surface are calculated based on changes in media material, media size and number of radiation particles (NPS). The results showed that the flux and particle track received by the surface of an object were greatly influenced by the media material and media size and the NPS value of the radiation particles.