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Introduction Anesthetists play an important role during interventional radiology procedures. Like the main operator, anesthetists may also be subject to significant radiation levels in the fluoroscopy suite. Due to its complexity, hepatic chemoembolization procedures demand high fluoroscopic times and digital subtraction angiography images, exposing patients and medical staff to high radiation doses. Objective To assess and quantify the radiation to which one anesthetist was exposed over the course of seven consecutive hepatic chemoembolization procedures, and compare it to the exposure received by the main operator. Methods Medical staff dosimetry was evaluated during seven consecutive hepatic chemoembolization procedures conducted in a private hospital in Recife (Brazil), using thermoluminiscent dosimeters placed in regions of the head and torso. Results For the seven procedures evaluated in this study, the anesthetist received, on average, absorbed doses to the glabella, left eyebrow, right eyebrow and effective dose of 142.4 ± 72 µSv, 117.3 ± 66 µSv, 137.8 ± 71 µSv and 12.4 ± 8.4 µSv, respectively. Conclusions In some cases, ocular dose and effective dose received by the anesthetist may be 4 and 4.7 times greater, respectively, when compared to the main operator. According to the results of this study, the current occupational annual dose limit to the lens of the eye of 20 mSv can be exceeded with only two hepatic chemoembolization procedures per week if adequate radiation protection conditions are not guaranteed.
Introducción El anestesiólogo desempeña un papel importante durante los procedimientos de radiología intervencionista. Al igual que el operador principal, el anestesiólogo también puede estar expuesto a niveles significativos de radiación en la sala de fluoroscopía. Debido a su complejidad, durante los procedimientos de quimioembolización hepática se deben utilizar imágenes de fluoroscopía y angiografía de sustracción digital por períodos prolongados, exponiendo a los pacientes y al personal médico a dosis elevadas de radiación. Objetivo Evaluar y cuantificar la radiación a la cual se expuso un anestesiólogo durante el transcurso de siete procedimientos consecutivos de quimioembolización hepática, y comparar con la exposición recibida por el operador principal. Métodos Evaluación de la dosimetría ocupacional durante siete procedimientos consecutivos de quimioembolización hepática realizados en un hospital privado de Recife (Brasil) por medio de dosímetros termoluminiscentes ubicados en regiones de la cabeza y el torso. Resultados Para los siete procedimientos evaluados en este estudio, el anestesiólogo recibió, en promedio, dosis absorbidas en el entrecejo, la ceja izquierda, la ceja derecha y dosis efectivas de 142,4 ± 72 µSv, 117,3 ± 66 µSv, 137,8 ± 71 µSv y 12,4 ± 8,4 µSv, respectivamente. Conclusiones En algunos casos, la dosis ocular y la dosis efectiva que recibe el anestesiólogo puede ser, respectivamente, entre 4 y 4,7 veces más alta que la que recibe el operador principal. De acuerdo con los resultados de este estudio, el límite ocupacional anual de dosis en cristalino (20 mSv) se puede superar con apenas dos procedimientos de quimioembolización hepática a la semana en caso de no garantizarse las condiciones adecuadas de protección contra la radiación.
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Objective:To analyze the abnormal dose monitoring result of radiation staff in medical institutions and provide a basis for standardizing the personal dose management of radiation staff in medical institutions.Methods:Through the occupational radiation disease monitoring subsystem of the National Radiation Health Information Platform, 516 individual dose monitoring abnormal result of 410 radiation workers in a single monitoring period, which in 168 medical institutions under the 18 cities in Henan province were collected from 2020 to 2022 as research objects. Based on gender, age, length of service, occupational category, medical institution level, whether the dosimeter wearing standard, the abnormal result of radiation workers were grouped to analyze the influencing factors of individual dose monitoring result.Results:The incidence of abnormal individual dose monitoring result in 2020-2022 was 6.83 × 10 -3, 5.22 × 10 -3 and 6.30 × 10 -3, respectively. Abnormal results were mainly distributed in male radiology workers (66.83%), diagnostic radiology (59.51%) and interventional radiology (34.63%), tertiary (54.39%) and secondary medical institutions (36.34%). In the case of wearing personal dosimeter in a standard or irregular way, there were statistically significant differences in the incidence of abnormal outcomes between different levels of medical institutions and different occupational categories( χ2=14.42, 6.56, 32.96, 177.15, P<0.05). The median annual individual dose of radiology workers with " abnormal exposure dose" due to increased workload was 3.95 mSv, and the annual individual dose of interventional radiology workers was higher than that of radiotherapeutic workers ( Z=5.07, P<0.05). Conclusions:The education and training of radiological protection should be strengthened, and the wearing of individual dosimeters should be standardized; focus on the occupational exposure of interventional radiology staff, and take effective measures to reduce their exposure dose.
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With the extensive use of neutron sources in industry, medicine, and scientific research, the number of people exposed to neutron has been increasing, which highlights the importance of personal neutron dose monitoring in the field of radiation protection. In the past decades, researchers have developed and improved a variety of techniques and methods for personal neutron dose monitoring. This paper focuses on the problems and research progress of track dosimeters (solid-state nuclear track dosimeters and fluorescent nuclear track dosimeters), luminescent dosimeters (thermoluminescent dosimeters and optically stimulated luminescent dosimeters), and bubble dosimeters in personal neutron dose monitoring.
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@#<b>Objective</b> To determine the effectiveness of quality control measures in the laboratory by participating in the national personal dose monitoring ability assessment, and to improve personal dose monitoring ability and quality. <b>Methods</b> According to the requirements of the National Personal Dose Monitoring Ability Assessment Program and standards, seven groups of personal dosimeter were prepared and irradiated by accurate radiation source as requested, and the dose was measured by the laboratory participating in the assessment. The data were processed, and the uncertainty of the measurement results was evaluated. <b>Results</b> In 2018, the assessment results <i>H</i><sub>p</sub> (10) dose range was 0.68-4.27 mSv, the single group performance deviation was −0.01 to −0.06, and the comprehensive performance deviation was 0.04, and the result was qualified. In 2019, the assessment results <i>H</i><sub>p</sub> (10) dose range was 0.74-8.06 mSv, the single group performance deviation was 0.00 to −0.08, and the comprehensive performance deviation was 0.04, and the result was qualified. In 2020, the assessment results <i>H</i><sub>p</sub>(10) dose range was 0.83-3.93 mSv, the single group performance deviation was −0.01 to −0.10, and the comprehensive performance deviation was 0.06, and the result was excellent. <b>Conclusion</b> The personal dose monitoring system in our laboratory runs smoothly, and the monitoring results are accurate and reliable. The laboratory can issue test reports that meet the requirements of national standards.
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Objective To develop a reasonable plan of monitoring personal internal exposure dose. Methods This paper introduced the methods of monitoring the individual dose and direct measurement of three representative radionuclides. Results The maximum monitoring periods were determined according to the radionuclide retention characteristics and the reporting standards and requirements, which were m(1)/m(T/2) ≤ 3 and m(T/2)/m(T) ≤ 3. The lower detection limit of the instrument was derived from the monitoring periods and the annual radionuclide intake limit, which should be lower than the derived method detection limit of the corresponding radionuclide. Then the measuring duration of the instrument that meets the corresponding conditions was derived from the derived method detection limit of the instrument and the maximum monitoring period. Conclusion Our results provide a reference for the formulation of a plan of monitoring personal internal exposure dose.
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Objective To analyze the results of national personal dose monitoring intercomparison and assessment of Hubei Provincial Hospital for Occupational Disease in 2016—2021, to investigate the influencing factors for monitoring results, and to improve the ability of personal dose monitoring. Methods The assessment was completed according to the requirements of The National Comparison Scheme for Individual Dose Monitoring Ability and Testing Criteria of Personnel Dosimetry Performance for External Exposure (GBZ 207—2016). Results The assessment results were qualified in 2016—2017 and 2020 and excellent in 2018—2019 and 2021. Conclusion The ability of personal dose monitoring in our laboratory has been continuously improved. The monitoring results are accurate and the data processing is standardized, which meet the requirements of relevant standards for personal external exposure dose monitoring.
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@#<b>Objective</b> To analyze the process of intercomparison of national personal dose monitoring, evaluate the ability of personal dose monitoring, and ensure the accuracy and reliability of monitoring results in our laboratory. <b>Methods</b> In accordance with the intercomparison protocol for 2019—2021, an energy-discriminant thermoluminescence dosimeter was used for measurement at different doses. The uncertainty of measurement was evaluated and compared with the reference value. <b>Results</b> <i>H</i><sub>p</sub>(10) was measured for intercomparison in 2019—2021. In 2019, the single group performance difference was −0.02 to 0.02 and the comprehensive performance was 0.02. These values were 0.02-0.10 and 0.05 in 2020, and −0.02 to 0.02 and 0.01 in 2021. The intercomparison results were rated as excellent in the three consecutive years. <b>Conclusion</b> The personal dose monitoring system in our laboratory was in good condition, and the monitoring results were accurate and reliable. Improving the knowledge of personnel and cultivating a serious working attitude are important for intercomparison and personal dose monitoring.
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@#<b>Objective</b> To study whether the disinfection methods for thermoluminescence dosimeters used by major hospitals during the COVID-19 pandemic had an impact on monitoring personal dose of external irradiation, and to screen for the disinfection procedures suitable for use during the pandemic. <b>Methods</b> Hospitals with fever clinics during the epidemic in Shandong Province were selected from March to October 2020, we investigated the disinfection methods as well as the types and frequency of use of disinfection supplies used for thermoluminescence dosimeters during the pandemic in hospitals. Simulations were performed in experimental and control groups. <b>Results</b> The average doses measured by the disc dosimeter with different disinfection methods and the control group were 0.92-0.99 mSv and 0.98 mSv, respectively, and the deviation was ≤ 6%. The average doses measured by the glass tube dosimeter with different disinfection methods and the control group were 0.20-0.22 and 0.21, respectively, and the deviation was ≤ 5%. <b>Conclusion</b> The results showed that the commonly used disinfection methods had no influence on personal dose monitoring, but some disinfection measures were not suitable for dosimeters.
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Background Individual monitoring of occupational external exposure is an essential part of the occupational health management of radiation workers, and is an important basis for the evaluation of individual absorbed dose and the diagnosis of occupational radiation diseases. Continuous participation of monitoring service providers in intercomparison is a fundamental quality assurance for routine monitoring, which can identify problems and improve them in time. Objective Taking the Laboratory of Radiation Protection in Shanghai Institute of Preventive Medicine as an example, to evaluate the performance of an individual occupational external dose monitoring system in the laboratory, identify influencing factors of the monitoring results, and provide a basis for improving the quality of daily monitoring by analyzing the process and results of a national intercomparison of individual dose monitoring. Methods According to the Testing criteria of personnel dosimetry performance for external exposure (GBZ 207-2016), and the relevant requirements of Class II (photon) inspection, a total of 20 groups of blind sample dosimeters were measured for four consecutive years from 2018 to 2021. The radiation energy source of each group was identified, and related personal dose equivalent Hp(10), the uncertainty of measurement results, and the deviation between the reported value and the reference value were calculated. The national intercomparison process and results of individual dose monitoring were also analyzed. Results The energy sources of the blind samples in the tested laboratory for four years were N100 or Cs-137. The reported dose values of the blind samples were 0.57-4.61 mSv, the combined uncertainties were 0.043-0.365 mSv, the expanded uncertainties (k=2) were 0.09-0.73 mSv, and the relative expanded uncertainties (k=2) were 13.8%-16.4%. The single-group performance ∣Pi∣ of 20 sets of blind samples in the four years was ≤0.10, the yearly comprehensive performance of 5 sets of blind samples was ≤0.10, and the yearly Q score of the test report was >15 points. The laboratory achieved excellent results in the national intercomparison of individual dose monitoring in four consecutive years, except the Q value not reaching full score. Conclusion The laboratory exhibits standardized data processing of individual dose monitoring, generates accurate and reliable results, and meets the requirements of relevant national standards; but it should continue to participate in the national intercomparison of individual dose monitoring, strengthen the angular response research of energy identified dosimeter, improve the monitoring ability of low-dose X-rays, analyze the key points of reducing the uncertainty of measurement results, and continuously improve the monitoring ability.
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@#<b>Objective</b> To analyze the monitoring results of external exposure dose of interventional radiology staff in a tertiary general hospital in Beijing, China, 2018—2020, and to provide a basis for safe guarding staff health and hospital radiation protection management. <b>Methods</b> A total of 321 interventional radiology staff in a hospital in Beijing were selected to collect information on the types of interventional work, positions, and personal dose monitoring results in 2018—2020. The dose monitoring results were analyzed using SPSS 22.0. <b>Results</b> The effective monitoring rate for the three years was 78.82%, 81.65%, and 96.85%, respectively, showing an increasing trend (<i>χ</i><sup>2</sup><sub> trend</sub> = 16.134, <i>P</i> < 0.001). The annual dose equivalent per capita was 0.142, 0.142, and 0.265 mSv, respectively. The annual dose equivalent per capita in 2020 was significantly higher than those in 2018 (<i>H</i> = 24.562, <i>P</i> < 0.001) and 2019 (<i>H</i> = 39.378, <i>P</i> < 0.001). The annual dose equivalent per capita in 2020 was in the order of interventional clinician > interventional nurse > technician (<i>H</i> = 10.699, 6.562, <i>P</i> < 0.01). The annual dose equivalent per capitain 2020 was higher in the cardiology interventional department than in the comprehensive interventional, neuro interventional, and vascular surgery departments (<i>H</i> = 35.530, 37.614, 35.496, <i>P</i> < 0.001). <b>Conclusion</b> The number of interventional radiology staff monitored from 2018 to 2020 increased year by year, so did the effective monitoring rate.The external exposure dose was at low levels, which generally meets the requirements of national occupational exposure limits. Training on radiation protection for interventional radiology staff should be further strengthened to raise awareness of radiation protection.
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Objective To investigate the personal dose level of occupational external exposure among interventional radiology workers in Liaoning Province of China, and to provide a reference for better occupational radiation protection. Methods According to the national standard GBZ 128—2016 Specifications for individual monitoring of occupational external exposure, the thermoluminescence method was used to measure the monitoring dose inside the lead clothes (HW) and outside the lead clothes (HN) of interventional radiology workers, and the Mann-Whitney U test and the Kruskal-Wallis H test were used for statistical analysis. Results Dual dosimeter monitoring data were collected from 307 interventional radiology workers in Liaoning Province in 2019, with a mean annual effective dose of 0.81 mSv and a maximum annual effective dose of 7.03 mSv, and 72.96% of the workers monitored had an annual effective dose of less than 1 mSv. The interventional radiology workers in tertiary hospitals had a significantly higher mean annual effective dose than those in secondary hospitals (0.95 mSv vs 0.65 mSv, P < 0.05). There was a significant difference in mean annual effective dose between departments (P < 0.05), and the department of interventional radiology had a significantly higher mean annual effective dose than the other departments (0.92 mSv vs 0.64 mSv), while the department of cardiology had a similar mean annual effective dose to the cerebrovascular department (0.78 mSv vs 0.78 mSv). Conclusion The occupational exposure dose of 307 interventional radiology workers in Liaoning Province meets the requirements in national regulations and standards and is higher than the national level, which suggests that radiation protection supervision and personal training should be further strengthened for interventional radiology.
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OBJECTIVE: To analyze the abnormal results and their causes of personal dose monitoring on medical radiation workers.METHODS: The medical radiation workers monitored from 2016 to 2019 in the personal dose monitoring room of Guangdong Province Hospital for Occupational Disease Prevention and Treatment were selected as the study subjects using convenient sampling method. The abnormal results and their causes of the medical radiation workers with personal dose equivalent ≥1.25 mSv(investigation level) in a single period were analyzed. RESULTS: The rate of abnormal results of personal dose monitoring was 0.26%(263/102 284). The false result rate was 0.19%(194/102 284), and that of the true result rate was 0.07%(69/102 284). A total of 73.38%(193/263) of medical radiation workers had abnormal results with an personal dose equivalent less than 5.00 mSv. Among different occupational groups, the abnormal results and false results in personal dose monitoring in interventional radiology group were the highest(all P<0.01). The abnormal result rate and false result rate were higher in the Pearl River Delta area than that in the non-Pearl River Delta area(0.27% vs 0.17%, 0.20% vs 0.12%, all P<0.05). The rate of false result of personal dose monitoring in the tertiary hospitals was lower than that in the non-tertiary hospitals(0.18% vs 0.30%, P<0.05). The main reason for the true results of personal dose monitoring was the increase of workload(43.48%), and the main reason for the false results was that the dosimeter was left in the workplace(57.73%). CONCLUSION: The rate of abnormal results of personal dose monitoring in the medical radiation workers is high. Radiological protection should be strengthened with emphasis on medical radiation workers in interventional radiology, Pearl River Delta area hospitals and non-tertiary hospitals.
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Objective In order to improve the personal dose monitoring ability of radiation health technical institutions, and standardize the detection methods and procedures. Methods Develop adetailed assessment plan according to GBZ 207—2016 “Testing criteria of personnel dosimetry performance for external exposure”, organize a national assessment of personal dose monitoring capabilities in 2020, analyze the problems arising from the assessment, and strengthen supervision and training in the future. Results A total of 457 institutions participated in this assessment, of which 421 were qualified (including 74 excellent institutions, with an excellent rate of 16.2%), and 36 were unqualified, accounting for 92.1% and 7.9% respectively. Conclusion The number of institutions that participated in the assessment this year reaches a record high, with a passing rate 4.08% higher than that in 2019. The overall monitoring capacity of the country has been greatly improved. However, some institutions still have problems such as irregular symbol writing, unupdated detection standards, and large deviations in testing data. It is necessary to improve the ability of loboratory detection and data analysis, standardize the operation process, and ensure the quality of assessment.
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Objective To investigate the reasons why the routine monitoring of personal dose of occupational external exposure of some radiological workers in our province reached the investigation level in 2018, so as to provide technical support for the correct decision making of administrative departments. Methods The registration forms for monitoring and verifying the personal dose of occupational external exposure were issued to radiation workers whose periodic dose reached or exceeded 1.25 mSv/ cycle. Results A total of 102 person-times were sent out in 53 verification forms, and 95 person-times were collected in 47 copies. The recovery rate was 88.68%, and 7 person-times did not feedback the verification forms. There were 15 cases of actual exposure, accounting for 15.79%, including 5 cases of radiological diagnostic staff, who did not close the protective door when operating exposure. Among them, the other 80 cases, accouting for 84.21% didn't receive actual exposure. Conclusion The vast majority of radiological workers who reached the survey level didn't receive actual exposure. 5 person-time radiological diagnostic staff, during the work did not close the protective door, subjected to abnormal radiation. Interventional medicine, nuclear medicine and industrial mobile flaw detection workers are at higher risk of abnormal exposures during their work. The suspicious results of the questionnaires without feedback were all less than the annual dose limit and the requirements of audit management. We will strengthen supervision of radiation health protection, raise the awareness of radiation protection among radiation workers, and improve radiation protection management and protection conditions for radiation workers in interventional medicine, nuclear medicine and industrial mobile flaw detection furtherly.
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Objective A case of abnormal personal doses of external exposure was reported in this paper. According to the investigation of the dose rates of the radiation sources and the workplace, the actualdose was estimated correctly. Methods The radiation level of storage containers at work site was measured by BH3103A portable X and γ radiation dosimeter. The thermoluminescence personal dosimeter was placed in the work site for a month, then it was measured with the RGD3 dosimeter to estimate the dose rateat the work site. The actual personal dose of external exposure was calculated based on the dose rateand the effective working time of the staff in the field. Results The location with highest dose rate was the empty containers which had been filled with raw materials. The second was a container filled with ingredients. The dose rate on the surface of empty container is generally higher than that of full container. The time weighted method was used to calculate the possible dose which was 2.32 mSv for this position. Conclusion The personal dose measured by the personal dosimeter was found to be erroneous, and it should be recorded with the revised dose of 2.32 mSv.
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Objective To investigate the status of radiological protection in Baoji City. Methods Using the questionnaire survey method, the survey forms were sent to the radiology clinics and other relevant units in the counties and districts of the city to investigate the basic situation of radiology and treatment of medical and health institutions, basic information of radiology and treatment equipment, personal information of radiation workers, and health monitoring of radiation workers. Results There is 1.13 X-ray diagnostic equipment per 10, 000 people, 0.015 radiotherapy equipment per 10, 000 people in Baoji City, and One million people own 11.4 CTs. There are 1, 102 radiation workers in Baoji City, and 2.92 per 10, 000 people. The occupational health check rate of medical radiation personnel was 87.7% within 2 years, the personal dose monitoring rate was 90.4%, the radiation worker training rate was 73.6% within 2 years, about the holding rate of "Radiation Staff Certificate" in Baoji City was 73.0%, and the occupational health file rate was 89.2%. The evaluation indexes of various health monitoring were lower, especially in township hospitals (35.7%～50.8%). Conclusion On the whole, the number of radiological diagnosis and treatment equipment is small, and Class A large equipment is almost blank. The city is stronger than the county in health monitoring. The status of health monitoring is very different from urban to rural areas.
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OBJECTIVE: To analyze the results of occupational health monitoring on radiation workers in national medical institutions in 2018. METHODS: Through the National Radiation Health Information Platform Subsystem Occupational Radiation Diseases and Occupational Health Monitoring System, the monitoring data including the overview of radiological diagnosis and treatment institutions, occupational health management, and occupational health examination information across the country were collected for analysis in 2018. RESULTS: In 2018, there were a total of 55 902 radiological diagnosis and treatment institutions with 353 141 radiation workers nationwide. The radiation dose monitoring rate on individuals and hospitals was 94.6%(334 222/353 141) and 97.3%(91 051/93 559), respectively. The rate of health examination was 84.6%(298 914/353 141) and 95.4%(87 031/91 244) respectively.The monitoring rate on chromosomal aberration in peripheral blood lymphocytes was 0.3% in radiation workers. The rate of opacity under the posterior lens capsule was 4.3% and the rate of thyroid nodules was 25.7% in interventional radiology and nuclear medicine workers. CONCLUSION:s The personal dose monitoring rate and occupational health examination rate of radiation workers in medical institutions in China are maintained at a relatively high level. However, monitoring attention should also be paid to the analysis of chromosome aberrations in peripheral blood lymphocytes, the examination of eye lens and thyroid gland.
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Objective To explore the applicable conditions for using urine plutonium monitoring data to assess personal internal doses,in order to provide references for the occupational health management and the urine plutonium monitoring in nuclear sector.Methods Using some plutonium mixtures from DOE nuclear facilities,as an example,the urine plutonium levels were estimated through simulation calculation at 1 mSv effective dose arising from either acute or chronic inhalation of plutonium compounds,respectively.The results were compared with the typical detection limit of radiochemical separation and α-spectrometry.The feasibility of urine plutonium monitoring for dose assessment of internal radiation exposure was discussed.Results Only for type M plutonium compunds,1 mSv detection limit can be achieved using radiochemical separation and α-spectrometry within 10 d after inhalation.Conclusions Before the monitoring plan of urine plutonium is made,detection limits of monitoring method should be considered.Internal dose could be accessed using workplace air monitoring and working hours when necessary.
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OBJECTIVE: To analyze the growth arrest and DNA damage gene 45( GADD45) mRNA expression in peripheral blood of radiation workers,and its relationship with exposure dose. METHODS: Using a typical sampling method,97 radiation workers from a hospital of Guangdong were selected as radiation group,48 hospital administrative staff without exposure to radiation and other occupational hazard factors were selected as control group. The real-time quantitative polymerase chain reaction was used to detect GADD45 mRNA expression of two groups. With the use of thermoluminescence dosimetry,we detected and collected personal dose data of radiation group over the past year. RESULTS: The GADD45 mRNA relative expression of the radiation group was higher than that of the control group( P < 0. 01).There was no correlation between GADD45 mRNA relative expression and factors such as personal dose,sex,age,length of service,smoking,and alcohol drinking( P > 0. 05). CONCLUSION: The ionizing radiation can lead to up-regulation of GADD45 mRNA expression in peripheral blood of radiation workers,but there was no linear relationship between GADD45 mRNA expression and its personal dose.
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Objective To evaluate the reliability of HARSHAW-3500 thermoluminescence dosimetry system by testing its performances.Methods HARSHAW-3500 thermoluminescence dosimetry system had its performances tested and evaluated according to Verification regulation of thermoluminescence dosimetry systems used in persontal and environmental monitoring forXandgammaradiation(JJG 593-2006),Testingcriteriaofpersonneldosimetryperformanceforexternalexposure (GBZ 207-2016),Specifications for individual monitoring of occupational external exposure (GBZ 128-2016) and Thermoluminescence dosimetry systems for personal and environmental monitoring (GB/T 10264-2014),such as batch homogeneity,repeatability,linearity,incidence angle response,stability,energy response and scale factor,quantity inspection,residual dose,detection limit and etc.Results Testing results of various performance indicators proved to be within the limits according to national and industrial standards.Conclusion HARSHAW-3500 thermoluminescence dosimetry system conforms to the requirements for radiation dose measurement.It is beneficial to the improvement of quality and performance of thermoluminescence dosimetry by performances analysis and evaluation.