Analysis of Radiation Level and Estimation of Protection Distance of {\gamma} Mobile Flaw Detection Source

Objective To analyze the radiation dose associated with gamma-ray mobile flaw detection, estimate the extent of the supervision and control areas, and assess the associated radiation risks. Methods A combination of theoretical calculations and actual measurements was used to compare and analyze the ambient equivalent dose rates of 192 Ir and 75 Se at their nominal source strengths. Measurements were conducted at distances of 1 m, 2 m, and 5 m from the radiation source. The extents of the control and supervision areas were estimated under three working scenarios: 1 without considering air attenuation, 2 considering air attenuation, and 3 after shielding by the flaw detection workpiece, using source activities of 3.7 * 10^10 Bq and 3.7 * 10^12Bq. Results Actual measurement of radiation dose of 192 Ir and 75 Se were measured under three different nominal activities. Theoretical calculation of radiation dose estimates at various distances were obtained for both nuclides, and the results showed that the theoretical values were basically consistent with the measured values. Conclusion The estimated scope of the supervision and control areas provided in this study can serve as a reference for flaw detection companies. Technicians can use these estimates to calculate appropriate distances for safety zones based on different nuclide activities. This enables flaw detection personnel to reduce the measurement scope on-site and to quickly and accurately define area boundaries.