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

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.

Keywords

• light water sub-critical reactor
• mcnp code
• gamma dosimetry
• reactor simulation