Open AccessMONTE CARLO SIMULATION BY CODE OF MCNP AND EXPERIMENTAL CHECK FOR MEASURING THICKNESS OF MATERIALS FOR THE SPECIALIZING SYSTEM OF MYO-101
Author(s) -
Phuong Sy Minh Hoang,
Hung Van Nguyen
Publication year - 2010
Publication title -
khoa học công nghệ
Language(s) - English
Resource type - Journals
ISSN - 1859-0128
DOI - 10.32508/stdj.v13i2.2129
Subject(s) - monte carlo method , nuclear engineering , detector , materials science , code (set theory) , liquid scintillation counting , nuclear physics , field (mathematics) , computational physics , computer science , physics , optics , engineering , radiochemistry , mathematics , chemistry , statistics , set (abstract data type) , programming language , pure mathematics
At present, thickness measurement of materials based on effect of backscattering gamma has been used widely in industry in our country. This report presents research in thickness of some materials such as paper, plastic, aluminum and steel using the specialized system of MYO-101 (with using scintillation detector of YAP(Ce) and gamma-ray of 60 keV of source of Am-241) by Monte-Carlo simulation with using the code of MCNP, and the simulation was checked by experimental measurements. The results show that the experiment and the simulation are in agreement in the error limit. This research can be useful for training activities in the field of application of nuclear technique in industry in Vietnam.