Simulation of gamma reference field at Institute for Nuclear Science and Technology using Monte Carlo method

Ky Bui Duc1, Ngoc Quynh Nguyen, Huu Quyet Nguyen, Thi My Linh Dang, Thi Nhung Duong, Dang Nguyen Nguyen, Minh Hue Dang
1 s:4:"INST";

Main Article Content

Abstract

This paper presents the characterization of two gamma reference fields of 137Cs and 60Co sources at the Institute for Nuclear Science and Technology. The characterization of the fields in terms of gamma fluence Φ, mean energy, EΦ, kerma weighted mean energies, Eₖ, air kerma, Eair,  were determined at various distances from the source center by Monte Carlo simulation using MCNP6. The air kerma results were compared with the measurements obtained by using a calibrated ionization chamber. The discrepancy between the simulated and measured air kerma was less than 4.5%. The scatterred component was also simulated and calculated. The results of both methods showed that the contribution of the scattered components to the gamma reference field is less than 3%. This contribution comply with the international standard criteria of ISO 4037 (<5%). The results confirmed that the characterization of the gamma reference field could be determined using the simulation code.

Article Details

References

[1]. ISO, Radiological protection - X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 1: Radiation characteristics and production methods, ISO 4037, 2019.
[2]. ISO, Radiological protection - X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV, ISO 4037, 2019.
[3]. ISO, Radiological protection - X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence, ISO 4037, 2019.
[4]. Denise B. Pelowitz, MCNP6 User’s Manual (Version 1.0), LA-CP-13-00634, 2013.
[5]. P.N.N. Laboratory, Compendium of Material Composition Data for Radiation Transport Modeling, PNNL-15870, Rev. 2. (2021).
[6]. ICRU, Operational Quantities for External Radiation Exposure, ICRU Report 95, 2020.
[7]. Hubbell J. H., Seltzer, S. M., Tables of X-Ray Mass Attenuation Coefficients and Mass Energy-Absorption Coefficients (version 1.4), National Institute of Standards and Technology, 2004.
[8]. Harald. Dombrowski, On the conversion coefficient from air kerma to ambient dose euivalent valid for a 137Cs photon field – A critical reviews, Radiation Protection Dosimetry, 2018.