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Date Published: 28/02/2023
Online Published: 03/03/2023
Abstract Views: 240
Views PDF: 147
DOI: https://doi.org/10.55046/vjrnm.50.739.2023
Issue
No. 50 (2023)
Section
Scientific research
How to Cite
Nguyễn, V. N., Nguyễn, T. C. T., & Trần, V. S. (2023). CALCULATION OF RADIATION SHIELDING FOR MEGAVOLTAGE GAMMA RAY FACILITY USING MONTE CARLO CODE EGSnrc. Vietnamese Journal of Radiology and Nuclear Medicine, 50, 52-60. https://doi.org/10.55046/vjrnm.50.739.2023

CALCULATION OF RADIATION SHIELDING FOR MEGAVOLTAGE GAMMA RAY FACILITY USING MONTE CARLO CODE EGSnrc

Nguyễn Văn Ngân, Nguyễn Thị Cẩm Tú, Văn Sóng Trần

Main Article Content

Abstract

This research applies the Monte Carlo simulation method EGSnrc Code with two code is dedicated, BEAMnrc code is used to simulate the beam emitted from the accelerator head and DOSXYZnrc be used to calculate the dose emitted from the accelerator. From there, evaluate beam attenuation of radiation emitted from the accelerator through the layers of shielding material. Initial study results showed that doses limited at staff area (area Control) is 0,11 mSv/ week (5,5 mSv / year) and in the public area (area Uncontrol) is 0,022 mSv/week (1,1 mSv/year).


Keywords: Accelerator, Radiation Safety, MCNP, EGSnrc, DOSXYZnrc and BEAMnrc.


 

Article Details

Keywords

Máy gia tốc, An toàn bức xạ, MCNP, EGSnrc, DOSXYZnrc và BEAMnrc.

References

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3. Podgorsak E.B. (2005), Radiation oncology physics: A handbook for teachers and students, IAEA. 4. Rogers D.W.O., Walters B., and Kawrakow I. (2002), “BEAMnrc Users Manual”, National Research Council of Canada Report PIRS-0509a, Ottawa.
5. Thông tư số 19/2012/TT-BKHCN ngày 08 tháng 11 năm 2012, Bộ Khoa học Công nghệ Quy định về kiểm soát và bảo đảm an toàn bức xạ trong chiếu xạ nghề nghiệp và chiếu xạ công chúng.