Objective:To investigate the activity concentration of tritium in urine of nuclear power plant(NPP)workers,in order to evaluate the occupational exposure levels.Methods:Three chosen NPPs were respectively located in s...Objective:To investigate the activity concentration of tritium in urine of nuclear power plant(NPP)workers,in order to evaluate the occupational exposure levels.Methods:Three chosen NPPs were respectively located in southern,southeastern and northeastern China.Workers involved in operating,service,nuclear cleaning,chemical analysis,health physics,technical support,among others were randomly selected as the research targets,and 69 urine samples of no less than 50 mL were collected.The oxidative distillation method was used to pretreat the urine samples,and the activity concentration of tritium in distillate was then measured using liquid scintillation counter.The formula for the committed effective dose was also applied used to estimate the internal doses.Results:The highest tritium activity concentrations in urine samples from three NPPs were 2412.7,6351.4,and 478.7 Bq/L,respectively.Correspondingly,the internal doses due to tritium intake were 1.8,4.8 and 0.4μSv,respectively.Conclusions:The urine tritium activity concentration of workers varied greatly dependent on their job categories.The values for urine tritium radioactivity concentrations of workers involved in health care,nuclear cleaning and maintenance were generally higher than those for other job categories.The difference in urine tritium activity concentration mainly came from the different exposure time and tritium concentrations.From the dose assessment results,the internal dose caused by tritium intake did not exceed the public annual effective dose limit.展开更多
In this study, sixteen soil and vegetable samples from Tafila district were collected and analyzed from eight locations. Measurements of specific activity of natural gamma emitter radionuclides, 23SU and 235U, in thes...In this study, sixteen soil and vegetable samples from Tafila district were collected and analyzed from eight locations. Measurements of specific activity of natural gamma emitter radionuclides, 23SU and 235U, in these samples using gamma spectrometry, with the help of Genie 2000 software. Measurements were used to calculate the soil-vegetable transfer factor, and then the external radiation dose and internal radiation dose due to radioactivity of the ingested food. The specific activity of238U and 235U in soil were found to vary from （in Bq/kg）： 26-575 and 1.4-35.5, respectively. The specific activity of 238U and 235U in vegetables were found to vary from （in Bq/kg）： 0.019 to 0.632 and 0.0013-0.0375, respectively. The calculated transfer factor of Z3SU and Z35U range from 5.9 × 10^-4to 14.6 × 10^-4 for 238U and 4.9 × 10^-4 to 16.1 × 10^-4 for 235U. External absorbed dose rates were calculated to be in the range from 12.42 to 266.00 nGy/h. The annual effective dose was found to vary from 28.94 to 619.78 μSv/y. The annual internal effective dose due to 23SU and 23SU for fresh weights ofvegetablesl were found to vary from 0.9 × 10^-3 to 35.1 × 10^-3 μSv/y for 238U and 0.61 × 10^-4 to 17.62 × 10^-4 μSv/y for 235U.展开更多
It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the ...It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the software of controlling, interface and internal dose estimation programs to the original iron cabin shielding whole-body counter. The preliminary application shows that its data processing is rapid and correct, and can meet the requirement of rapid internal radioactive contamination monitoring and diagnosing in case of lots of internal contamination subjects happened innuclear accident.展开更多
基金This work was supported by Environmental Radioactivity Research Network Center(Japan,Grant Number:I-20-15)the Key Program of Tianjin Municipal Natural Science Foundation(China,Grant Number:19JCZDJC40500).
文摘Objective:To investigate the activity concentration of tritium in urine of nuclear power plant(NPP)workers,in order to evaluate the occupational exposure levels.Methods:Three chosen NPPs were respectively located in southern,southeastern and northeastern China.Workers involved in operating,service,nuclear cleaning,chemical analysis,health physics,technical support,among others were randomly selected as the research targets,and 69 urine samples of no less than 50 mL were collected.The oxidative distillation method was used to pretreat the urine samples,and the activity concentration of tritium in distillate was then measured using liquid scintillation counter.The formula for the committed effective dose was also applied used to estimate the internal doses.Results:The highest tritium activity concentrations in urine samples from three NPPs were 2412.7,6351.4,and 478.7 Bq/L,respectively.Correspondingly,the internal doses due to tritium intake were 1.8,4.8 and 0.4μSv,respectively.Conclusions:The urine tritium activity concentration of workers varied greatly dependent on their job categories.The values for urine tritium radioactivity concentrations of workers involved in health care,nuclear cleaning and maintenance were generally higher than those for other job categories.The difference in urine tritium activity concentration mainly came from the different exposure time and tritium concentrations.From the dose assessment results,the internal dose caused by tritium intake did not exceed the public annual effective dose limit.
文摘In this study, sixteen soil and vegetable samples from Tafila district were collected and analyzed from eight locations. Measurements of specific activity of natural gamma emitter radionuclides, 23SU and 235U, in these samples using gamma spectrometry, with the help of Genie 2000 software. Measurements were used to calculate the soil-vegetable transfer factor, and then the external radiation dose and internal radiation dose due to radioactivity of the ingested food. The specific activity of238U and 235U in soil were found to vary from （in Bq/kg）： 26-575 and 1.4-35.5, respectively. The specific activity of 238U and 235U in vegetables were found to vary from （in Bq/kg）： 0.019 to 0.632 and 0.0013-0.0375, respectively. The calculated transfer factor of Z3SU and Z35U range from 5.9 × 10^-4to 14.6 × 10^-4 for 238U and 4.9 × 10^-4 to 16.1 × 10^-4 for 235U. External absorbed dose rates were calculated to be in the range from 12.42 to 266.00 nGy/h. The annual effective dose was found to vary from 28.94 to 619.78 μSv/y. The annual internal effective dose due to 23SU and 23SU for fresh weights ofvegetablesl were found to vary from 0.9 × 10^-3 to 35.1 × 10^-3 μSv/y for 238U and 0.61 × 10^-4 to 17.62 × 10^-4 μSv/y for 235U.
文摘It is capable of giving the initial intakes of radionuclides and the assessment quantities used in radiation protection according to its measured results of radionuclides in vivo. It is accomplished by providing the software of controlling, interface and internal dose estimation programs to the original iron cabin shielding whole-body counter. The preliminary application shows that its data processing is rapid and correct, and can meet the requirement of rapid internal radioactive contamination monitoring and diagnosing in case of lots of internal contamination subjects happened innuclear accident.
