Objective To investigate the levels and influencing factors for eye lens dose of interventional radiology workers, and to provide a basis for reasonable and scientific radiation protection. Methods Thermoluminescent eye lens dosimeters were used to monitor the left and right eye lens doses of interventional radiology workers in real time during different surgical positions and varying eye protection conditions. The annual eye lens doses for the operators were estimated based on their yearly workload. The differences in eye lens doses under different conditions were analyzed and the influencing factors were identified. Results For individual interventional operations, the range of personal dose equivalent H_p(3) of the left eye of interventional radiology workers was ( < MDL ~ 418.33) μSv, the median (Q₁, Q₃) was 9.29 ( < MDL, 40.79) μSv, and the mean was 40.79 ± 70.36 μSv. The estimated annual eye lens doses were 4.05 mSv and 17.80 mSv based on the median and mean values of the eye lens dose of a single operation multiplied by average annual frequency of operations per person, respectively. The left eye lens dose was higher than the right eye lens dose of the same operator (Z = −4.24, P < 0.05), and the dose of the right eye lens was strongly positively correlated with that of the left eye lens. The left eye lens dose of the first surgeon was higher than that of the second surgeon in the same operation (Z = −3.10, P < 0.05). The eye lens dose was influenced by operator position (χ² = 9.149, P = 0.002, OR = 8.343), eye protection (χ² = 4.619, P = 0.032, OR = 4.352), and air kerma area product (χ² = 8.032, P = 0.005, OR = 5.488). Conclusion According to the results of this study, a significant portion of interventional operators have eye lens doses that approach or exceed international occupational dose limits. It is recommended to pay attention to the operation frequency of the first operator and the air kerma area product of interventional operation, and strengthen radiation protection and dose monitoring for the eye lens of interventional radiology workers.

Objective To investigate the levels of gross α and gross β activities in different water types within a 40-kilometer radius around the Zhangzhou Nuclear Power Plant prior to its operation. Methods In 2018, drinking water samples were collected from the area surrounding the nuclear power plant during both the wet and dry seasons, including source water, treated water, tap water, and well water. The gross α and gross β activity concentrations were measured using a low-background α/β counter, followed by statistical analysis. Results A total of 80 water samples from different sources around the Zhangzhou Nuclear Power Plant were collected. The average gross α and gross β activity concentrations during the wet season were (0.110 ± 0.036) Bq/L and (0.643 ± 0.028) Bq/L, respectively, while those during the dry season were (0.124 ± 0.032) Bq/L and (0.624 ± 0.026) Bq/L, respectively. There were no significant differences in the gross α and gross β activity concentrations between the wet and dry seasons for the overall sample set (P > 0.05). However, there were statistically significant differences in the gross α and gross β activity concentrations between the wet and dry seasons for source water and well water (Z_wet = −2.005, −2.123; Z_dry = −1.943, −3.090; P < 0.05). Conclusion The radioactivity levels in different water types within various ranges around the Zhangzhou Nuclear Power Plant before its operation were determined. The measured activity concentrations were at the same level as those from previous investigations in other regions of Fujian Province.

Objective:To explore the in vitro radiation levels and in vivo neutron activation after patients receiving boron neutron capture therapy (BNCT). Methods:Totally 29 BNCT treatments were performed for 21 patients with head and neck and brain cancer using the NeuPex accelerator-based boron neutron capture therapy (AB-BNCT) system in Xiamen Humanity Hospital from October, 2022 to April, 2024. The ambient dose equivalent rate around the patients was measured with an X/gamma dose rate survey meter. The gamma radiation dose rates were measured at 0, 0.5, 1.0, and 2.0 m from the irradiation position, at 0, 0.5, 1.0, and 2.0 m from the opposite side of the irradiation position, and at the navel and the affected knee, respectively. Meanwhile, a portable high-purity germanium gamma spectrometer was used to measure the spectrum of activated nuclides in the bodies of patients who had underwent the treatment, and the types of radionuclides generated by neutron activation during each BNCT treatment were analyzed.Results:The radionuclides 24Na, 38Cl, and 49Ca were mainly produced in the bodies of patients treated with BNCT. 20 minutes after BNCT treatment, the ambient dose equivalent rate at a distance of 1.0 m from the irradiation position was lower than 2.5 μSv/h. Conclusions:The dose delivered to the staff and family members by the patients undergoing BNCT is relatively low, and the resulting radiation risk is low. According to the ALARA principle, it is recommended that certain control actions be taken for patients having received BNCT treatment to minimize the exposure doses of both patients and staff as much as possible.

Objective:To explore the in vitro radiation levels and in vivo neutron activation after patients receiving boron neutron capture therapy (BNCT). Methods:Totally 29 BNCT treatments were performed for 21 patients with head and neck and brain cancer using the NeuPex accelerator-based boron neutron capture therapy (AB-BNCT) system in Xiamen Humanity Hospital from October, 2022 to April, 2024. The ambient dose equivalent rate around the patients was measured with an X/gamma dose rate survey meter. The gamma radiation dose rates were measured at 0, 0.5, 1.0, and 2.0 m from the irradiation position, at 0, 0.5, 1.0, and 2.0 m from the opposite side of the irradiation position, and at the navel and the affected knee, respectively. Meanwhile, a portable high-purity germanium gamma spectrometer was used to measure the spectrum of activated nuclides in the bodies of patients who had underwent the treatment, and the types of radionuclides generated by neutron activation during each BNCT treatment were analyzed.Results:The radionuclides 24Na, 38Cl, and 49Ca were mainly produced in the bodies of patients treated with BNCT. 20 minutes after BNCT treatment, the ambient dose equivalent rate at a distance of 1.0 m from the irradiation position was lower than 2.5 μSv/h. Conclusions:The dose delivered to the staff and family members by the patients undergoing BNCT is relatively low, and the resulting radiation risk is low. According to the ALARA principle, it is recommended that certain control actions be taken for patients having received BNCT treatment to minimize the exposure doses of both patients and staff as much as possible.

Objective To understand the level of nuclear radiation knowledge and attitude towards nuclear power plant construction among health emergency personnel around a nuclear facility, to enhance public awareness and education targeted at these individuals, to increase confidence in the safety of nuclear power plants, and to aid health emergency response work. Methods In September 2022, following the survey plan developed by National Institute for Radiological Protection, China CDC, a survey was conducted using a questionnaire designed by the institute. The survey was conducted by filling online questionnaire by 238 individuals engaged in health emergency gathered at their working units, including designated centers for disease control, hospitals, and township health clinics at the municipal, county, and township levels. The collected data were analyzed by SPSS 22.0 statistical software. The categorical data were statistically described by proportion and subjected to chi-square test. The continuous data were described by \begin{document}$\bar{x} \pm s$\end{document} and subjected to correlation analysis using multiple linear regression. Results A total of 225 valid questionnaires were collected. The scores were relatively high for professional and technical personnel of radiation health protection agencies, personnel with postgraduate degrees, and male personnel, and their scores were 10.83 ± 2.13, 12.4 ± 1.67, and 10.48 ± 2.8, respectively. Sex and education were the factors influencing the level of radiation knowledge (P < 0.05). Most of the respondents were very concerned and worried about the safety of nuclear power plants, supported the construction of nuclear power plants by the state but took a neutral attitude towards the construction of nuclear facilities in the local area, and showed high level of trust in the government and the authoritative media. Conclusion According to the characteristics of the health emergency personnel, different publicity and education methods and activities should be used to enhance understanding of radiation knowledge. The authoritative role of the government and the media should be emphasized to build confidence in the safety of nuclear power plants.

Objective To investigate the number and categorical distribution of non-medical radiation institutions in Fujian Province, China, and to explore the current situation of radiation occupational hazards prevention and control and the occupational health management of radiation workers in employing units. Methods The industrial enterprises engaged in the application of nuclear technology in our province were investigated, and different types of employing units were selected to monitor the radioactivity level in the workplace. Results A total of 377 non-medical radiation institutions were reported in the province, with a total of 5221 radiation workers (except luggage detector units); 1246 radiation workers held radiation worker certificates, accounting for 23.87%; 5103 radiation workers carried out personal dose monitoring, accounting for 97.74%; 5061 radiation workers participated in radiation protection knowledge training, accounting for 96.94%; a total of 4895 (93.76%)radiation workers received physical examination. Conclusion Health supervision authorities in Fujian Province should strengthen the supervision of non-medical radiation institutions, further improve the level of occupational health management, and protect the health rights and interests of radiation workers to the maximum extent.

Objective To investigation the radioactivity level of ⁹⁰Sr in tea leaves within and outside 30 km range of Ningde nuclear power plant. Methods The tea leaves within and outside the 30 km range of Ningde Nuclear Power Plant were collected from 2013 to 2018. According to“Radiochemical analysis of strontium-90 in water and ash of biological samples” (HJ 815—2016), the separation and analysis of ⁹⁰Sr-⁹⁰Y were carried outusing the method of di (2-ethylhexyl) phosphate (HDEHP) chromatography. Results During the period of 2013-2018, the radioactivity concentrations of ⁹⁰Sr in the tea leaves within the range of 30 km around the Ningde nuclear power plant were 0.486～13.29 Bq/kg and that of ⁹⁰Sr in the tea leaves outside the range of 30 km around the nuclear power station were 1.021～17.19 Bq/kg. Conclusion During the six years of operation in Ningde Nuclear Power Plant, there was no increase in the radioactivity level of ⁹⁰Sr in the tea leaves around the nuclear power plant.

Objective:To explore the main risk factors and to assess the risk of thyroid 131I exposure among nuclear medical workers. Methods:From March to October in 2019, cluster sampling was adopted to collect the number of 131I automatic packer and patients treated for thyroid cancer, hyperthyroidism and liven cancer used 131I, the practicing categories, job rotation and 131I operation condition of nuclear medical staff were also investegated in the 21 nuclear medicine hospitals in Fujian Province that carried out 131I nuclide diagnosis and treatment in 2018. 131I aerosol and personnel thyroid 131I were measured in 20 hospitals using 131I for thyroid cancer or hyperthyroidism. The main risk factors leading to thyroid 131I exposure of nuclear medical staff were found and aninternal exposure risk assessment model was established. Results:The detection rate of 131I aerosol and personnel thyroid 131I were 80.0% (16/20) and 25.5% (62/243) in 20 hospitals. The situation of packaging and administration about 131I in the nearly 10 effective half-life, the concentration of 131I aerosol in the nuclear medicine workplace, the number of patients treated with 131I for thyroid cancer or hyperthyroidism were the main risk factors leading to thyroid 131I internal exposure ( OR=5.857, 6.808, 1.983, 1.150, P<0.05) . Conclusion:131I exposure is common among nuclear medical workers, attention should be paid to the protection of internal radiation, strengthen the control of main risk factors, so as to reduce the risk of internal radiation.

Objective:To explore the main risk factors and to assess the risk of thyroid 131I exposure among nuclear medical workers. Methods:From March to October in 2019, cluster sampling was adopted to collect the number of 131I automatic packer and patients treated for thyroid cancer, hyperthyroidism and liven cancer used 131I, the practicing categories, job rotation and 131I operation condition of nuclear medical staff were also investegated in the 21 nuclear medicine hospitals in Fujian Province that carried out 131I nuclide diagnosis and treatment in 2018. 131I aerosol and personnel thyroid 131I were measured in 20 hospitals using 131I for thyroid cancer or hyperthyroidism. The main risk factors leading to thyroid 131I exposure of nuclear medical staff were found and aninternal exposure risk assessment model was established. Results:The detection rate of 131I aerosol and personnel thyroid 131I were 80.0% (16/20) and 25.5% (62/243) in 20 hospitals. The situation of packaging and administration about 131I in the nearly 10 effective half-life, the concentration of 131I aerosol in the nuclear medicine workplace, the number of patients treated with 131I for thyroid cancer or hyperthyroidism were the main risk factors leading to thyroid 131I internal exposure ( OR=5.857, 6.808, 1.983, 1.150, P<0.05) . Conclusion:131I exposure is common among nuclear medical workers, attention should be paid to the protection of internal radiation, strengthen the control of main risk factors, so as to reduce the risk of internal radiation.

Objective:To ascertain the basic situation of radiotherapy in Fujian in 2016.Methods:Based on the unified questionnaire, the types and quantity of radiotherapy and its corollary equipment, the number of radiotherapy staff and the work for quality control were surveyed in the radiotherapy units in the whole province, and the data on patients undergoing radiotherapy and other types of patients were collected from 26 hospitals. The total number of radiotherapy patients in the whole province was estimated by the correlation analysis and multiple linear regression analysis.Results:Radiotherapy was performed in a total of 32 hospitals in Fujian province in 2016. Among them, there were 62 sets of radiotherapy equipment, 33 sets of the simulators, 57 sets of treatment planning systems and 762 workers. The total number of 15 156 radiotherapy patients in 26 hospital were available for the survey. Multiple linear regression models showed that the frequency of application of medical electron accelerator was positively correlated with number of outpatients, emergency patients and inpatients, number of radiotherapy staff, number of electron accelerators ( r=0.311, 0.893, 0.956, P<0.05). Meanwhile, the frequency of aterloading brachytherapy was positively correlated with number of outpatients, emergency patients and inpatients, number of radiotherapy staff, number of aterloading brachytherapy units ( r=0.307, 0.966, 0.988, P<0.05). The frequency of radiotherapy was 0.54 patients per 1 000 population in Fujian in 2016. The delivered dose calibration of accelerators was performed in all hospitals involved in line with the relevant regulations, but the number of quality control equipment for radiotherapy was insufficient, such as the QA beam checker or well-type ionization chamber. Conclusions:In recent years, the rapid development of radiotherapy has been seen in Fujian province. The radiotherapy management should focus on standardenized and improved quality control and regulation in future.