Measurement and calculation of gamma radiation dose in the subcritical light water reactor of reactor research school-Isfahan

Zahiri Kopai, S.; Abdi, M.R.; Jalali Hajiabadi, M.

doi:10.24200/nst.2022.1460

Measurement and calculation of gamma radiation dose in the subcritical light water reactor of reactor research school-Isfahan

Document Type : Scientific Note

Authors

S. Zahiri Kopai ¹

M.R. Abdi ¹

M. Jalali Hajiabadi ²

¹ Faculty of Physics, University of Isfahan, P.O.Box: 8174673441, Isfahan – Iran

² Reactor Research School, Nuclear Science and Technology Research Institute, P.O.Box: 81465-1589, Isfahan - Iran

https://doi.org/10.24200/nst.2022.1460

Abstract

Calculating and measuring the gamma dose of nuclear reactors is important in terms of safety and protection and is used for organizations' design and development programs. In order to achieve this goal, experimental measurement with RADOS and SMART-RAD digital dosimeters and calculations based on Monte Carlo code has been used.The three-dimensional geometry of the light water subcritical reactor of Isfahan Reactor Research School was simulated for gamma dosimetry calculation with the MCNPX2.6 code. The effective multiplication factor was estimated prior to dose calculation and revealed to be less than 6% different from the value reported in the reactor technical specifications. Analyses were performed to obtain the sought parameter, gamma dose (µSv/h), following the validation of the reactor simulation code. The F4 and F5, F4 and *F8, and *F8 and F5 tallies differed by less than 5%, 2%, and 4%, respectively. The difference between the measured and calculated values was found to be reasonable and acceptable compared to similar previous studies.

Highlights

1. J. Bennet, R. Thomson, Elements of nuclear power, 3rd Edition, American Nuclear, (1989).

2. M. Hoseini Pouya, Basics of Dosimetry in External Radiation, (Nuclear Science and Technology Research Institute, Tehran, 2015), (In Persian).

3. M. Hajizadeh Safar, Fundamentals of Detection and Dosimetry of Ionizing Radiation, (Mashhad University of Medical Sciences, Mashhad, 2014), (In Persian).

4. Maritza R. Gual, et al., Dosimetry assessment during the sipping test in the IPR-R1 TRIGA reactor, Progress in Nuclear Energy, 238-245 (2016).

5. Z. Gholamzadeh, E. Bavarnegin, Gamma and neutron dosimetry of Tehran Research Reactor containment during and after LOCA accident, Applied Radiation and Isotopes, 145, 59-67 (2019).

6. N. Xoubi, Neutrons and Gamma-Ray dose calculations in subcritical reactor facility using MCNP, Atoms, 4, 1-9 (2016).

7. K. Ambrozic, G. Zerovnik, L. Snoj, Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities, Applied Radiation and Isotopes, 130, 140–152 (2017).

8. D.B Pelowitz, MCNPXTM User`s Manual Version 2.6.0, LA-CP-07-1473, Los Alamos National Laboratory, (2008).

9. M. Arkani, et al, Prompt Neutron Decay Constant in Esfahan Light Water Subcritical Reactor (ELWSCR) Comparison of Rossi-α Experiment and Monte Carlo Simulation, J. of Nuclear Sci. and Tech, 80, 18-24 (2017).

10. M. Arkani, et al, Measurement of Prompt Neutron Decay Constant in Esfahan Light Water Subcritical Reactor Utilizing Feynman-α Analysis, J. of Nuclear Sci. and Tech, 76, 1-7 (2016).

11. N. Nasiri Mofkham, Z. Nasr Azadani, J. Sadegh zade, Determination of physical reactor based on experimental and theoretical results, J. Nucl. Sci. Tech, 60(1), 55-60 (2012).

12. Sh. Shirvani, M.Sc. Thesis, Islamic Azad University of Central Tehran Branch, (2011).

Keywords

Light water sub-critical reactor

MCNP code

Gamma dosimetry

Reactor simulation