Objective To investigate the effects of low dose radiation on the level of oxidative damage and antioxidant in population of high background radiation area of Guangdong.Methods A total of 48 male residents who lived in high background radiation area(HBRA) of Guangdong province and 48 male residents who lived in neighboring Enping control area were chosen as the objectives and control respectively.The peripheral venous blood of two groups was collected,and then the levels of 8-OHdG and TrxR were determined by enzyme linked immunosorbent assay (ELISA).Results Compared with the CA group [(315.39 ± 100.59) ng/ml],the level of 8-OHdG [(272.64 ± 96.85) ng/ml] decreased significantly in HBRA (t =2.121,P ＜0.05).Compared with the CA group [(0.467 ±0.056) ng/ml],the level of TrxR [(0.496 ± 0.044) ng/ml] increased significantly in HBRA (t =-2.823,P ＜ 0.05).The results of multiple linear regression analysis demonstrated that the chronic exposure to low dose of radiation had significant effects on the expression level of 8-OHdG and TrxR (t =-2.327,2.367,P ＜ 0.05) after adjustment for confounding factors such as age,drinking,tea drinking,smoking,medical exposure and stressful events.Conclusions Chronic exposure to low dose radiation may decrease the level of oxidative and enhance the level of antioxidant.

Objective To analyze the occupational hazards and protective measures for personnel in an iodine-125(¹²⁵I) seed source production company. Methods In 2022, a ¹²⁵I seed source production enterprise in Guangdong Province was selected as the research subject. The occupational hazards in the workplace of the research subject was identified using the system engineering analysis method. The FLUAK program based on Monte Carlo method was used to simulate the blocking protection of the production of the ¹²⁵I seed source, and to estimate the dose of internal and external irradiation of seed source that affected workers. Results The main occupational radiation hazards in the seed production were non-sealed radioactive materials, including external irradiation from X-ray and γ ray and internal irradiation from aerosols formed by iodine volatilization. Estimated maximum dose equivalent rate around the chest and eye lens for workers were 0.52 and 0.02 μSv/h, respectively. The expected annual effective dose for workers in each work site was 0.035 mSv, and the expected annual equivalent dose to the eye lens for all workers in various work sites was 0.001 mSv. The maximum annual equivalent dose of operator's hand was 80.620 mSv. The maximum dose of internal irradiation to the worker was 18.750 mSv, which was caused by the volatilization of nuclides. Conclusion With effective protection measures for internal and external irradiation in place, the annual exposure doses for seed production personnel and operator’s hand are below the national limits. Adequate measures should be taken on hand protection.

Objective To investigate the radiation dose at the entrance of the accelerator treatment room, and to guide the radiation protection detection at the entrance of the treatment room. Methods The FLUKA program was used to build the model of accelerator head and treatment room. Under the simulation conditions of 10 MV and 600 cGy/min for the accelerator, the radiation dose rate inside the entrance of the treatment room was measured at different gantry angles, irradiation conditions, and labyrinths. Results The entrance dose rate with a water tank was significantly higher than that without a water tank under different inner labyrinth wall thicknesses and gantry angles. The entrance dose rate reached the maximum at the inner labyrinth wall thickness of 1800 mm and the gantry angle of 90°. When the inner labyrinth wall thickness was 1000 mm and the gantry angles were 0° and 180°, the entrance dose rate was significantly higher than that at other conditions. The dose rate at the entrance of the treatment room reached (82.26 ± 48.95) μSv/h to (314.09 ± 96.34) μSv/h under the following conditions: the inner labyrinth wall thickness of 1800 mm, the gantry angle of 90°, with a water tank, and the width of the inner labyrinth entrance of 1400-2200 mm. Conclusion The dose at the entrance of the accelerator treatment room mainly comes from the scattering and leakage radiation of the useful wire harness on the patient’s body surface, and the entrance dose rate increases with the increase in the width of the inner labyrinth entrance. In the entrance protection test, the gantry angle should be determined considering the inner labyrinth wall thickness, and the test should be performed at four angles in the uncertain case to ensure the comprehensiveness and accuracy of test results.

Objective To analyze the relevant measures of radiation protection for dental X-ray diagnostic projects in 44 dental clinics in Guangdong Province, China, and discuss common problems. Methods Based on the three principles of radiation protection, relevant laws, regulations and standards of the state, combined with field investigations and test results of radiation protection, the situation of radiation protection and management was analyzed. Results The layout of 56 dental diagnostic rooms in 44 clinics was (basically) reasonable. The protective performances and quality control tests of 56 dental X-ray diagnostic machines met the standard requirements, and the dose equivalent rate around 56 dental diagnostic rooms was from the background to 1.47 μSv/h, which met the national standard. The coincidence rates of ionizing radiation warning signs, working status indicator lights and door light interlocks, automatic door closing devices, power ventilation devices, and personal protective equipment were from 85.70% to 98.20%. The compliance rates of dental radiologists and full-time (part-time) administrative staffs, occupational health monitoring, management system related to radiation protection, and radiation health files were from 79.5% to 100.0%. Conclusion The current situation of radiation protection and management in the dental X-ray diagnostic room is good, and relevant national regulations and standards should be promulgated or improved to standardize the cone-beam CT quality control testing, dental clinic location requirements, and radiation staff configuration.

Objective To study the dose level of proton beams outside the main shield of the 230 MeV proton therapy room with six different types of concrete as the main wall, and to obtain the shielding performance of six different types of concrete. Methods The FLUKA program was used to build a calculation model, and different concrete compositions were introduced into the FLUKA program to simulate the change in ambient dose equivalent rate of the focus with concrete thickness under 230 MeV proton beam irradiation. The transmission curves of six different types of concrete were fitted to obtain shielding performance parameters. Results On the condition that the 230 MeV proton beam irradiated to the water target in 90° direction and the concrete thickness exceeded 40 cm, the proton beam was exponentially decayed for six different types of concrete, and the fitted decay curves had a R² of > 0.99. The linear attenuation coefficients for normal concrete, barite concrete, magnetite concrete, limonite concrete, phosphorite concrete, and ferrosilicate concrete were 0.0148 cm⁻¹, 0.0172 cm⁻¹, 0.0196 cm⁻¹, 0.0219 cm⁻¹, 0.0256 cm⁻¹, and 0.0290 cm⁻¹, respectively. Conclusion The composition and proportion of elements in concrete materials directly affect the shielding ability of concrete against proton beams to a large extent, and the shielding performance of six different types of concrete against proton beams varies greatly. Therefore, shielding materials for the proton therapy room should be selected by a comprehensive consideration of the material compositions and shielding performance of concrete, the difficulty of construction, and construction cost.

Objective To analyze the dose distribution of induced radiation in fixed proton beam therapy room and the influence of shielding materials, and to provide a basis for radiation protection and shielding material selection in proton therapy. Methods FLUKA was used to simulate the dose distribution of induced radiation in fixed proton beam therapy room, the dose over time, and the influence of different concrete materials. Results The dose of induced radiation was mainly concentrated around the target, and the dose rapidly decreased to 1/5-1/10 of the value at the time of stopping irradiation after cooling for 3-5 min. The induced radiation in concrete formed a slightly higher dose area at the end of the main beam near the inner side of the shield. The content of Fe, O, and H in concrete had significant effects on induced radiation (P < 0.01), and the dose was negatively correlated with the content of Fe. Conclusion The patients after proton therapy as well as the induced radiation in air and shielding materials are the main sources of external radiation dose for workers, and waiting for a period of time is the most effective way to protect the staff. Without considering the difficulty in construction and based on the analysis of shielding materials in protection against external irradiation and their influence on induced radiation, heavy concrete with a relatively high level of Fe is the best choice of the shielding material for proton therapy room.

OBJECTIVE: To analyze the influencing factors that cause occupational stress among female workers in a large electronic manufacturing enterprise. METHODS: A total of 1 081 female workers from a large electronic manufacturing enterprise were selected by the cluster random sampling method. The Chinese version of Job Content Questionnaire and Effort Reward Imbalance Questionnaire were used to assess occupational stress and its influencing factors were analyzed.RESULTS: Among 1 081 female workers,70. 95% and 19. 43% of them showed high level of occupational stress of job demand-control( JDC) model and effort-reward imbalance( ERI) model,respectively. Educational level with senior high school and above,assembly line working and exposure to occupational hazards were risk factors for high occupational stress of JDC model in female workers( P < 0. 01). The risk of high occupational stress ERI model in female workers with junior high school educational level and below was higher than that of senior high school educational level and above( P < 0. 01).CONCLUSION: The occupational stress rate of female workers in this electronic manufacturing enterprise is high. The main occupational stress model is JDC model. The main influencing factors of JDC model are educational level,operation mode and status of occupational hazard exposure.