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MONTE CARLO SIMULATION BY CODE OF MCNP AND EXPERIMENTAL CHECK FOR MEASURING THICKNESS OF MATERIALS FOR THE SPECIALIZING SYSTEM OF MYO-101

Phuong Sy Minh Hoang 1, *
Hung Van Nguyen 1
  1. Nuclear Research Institute (Dalat)
Correspondence to: Phuong Sy Minh Hoang, Nuclear Research Institute (Dalat). Email: pvphuc@hcmuns.edu.vn.
Volume & Issue: Vol. 13 No. 2 (2010) | Page No.: 83-91 | DOI: 10.32508/stdj.v13i2.2129
Published: 2010-06-30

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Copyright The Author(s) 2023. This article is published with open access by Vietnam National University, Ho Chi Minh city, Vietnam. This article is distributed under the terms of the Creative Commons Attribution License (CC-BY 4.0) which permits any use, distribution, and reproduction in any medium, provided the original author(s) and the source are credited. 

Abstract

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.

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