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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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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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@#This scoping review aimed to determine the dosage of noise exposure among motorcycle riders and the sources contributing to a rider’s noise exposure. A systematic search of several scientific databases was conducted from 1981 until 2021. Eligible articles were included into the defined criteria. The dosage of noise exposure, sources, and standardization method were extracted. A total of 37 studies were included. There was scarce publication regarding the exact level of noise exposure experienced by the riders. There was, however, abundant evidence on indirect sources of noise exposure for riders, which requires further critical analysis. The dosage of noise exposure among riders was significantly higher than the recommended level. Seven sources were determined to generate noise which could potentially affect the riders, presented in this paper along with their respective evidence.
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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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Objective To investigate the current status of interventional radiology resources, radiation protection equipment, and the rate of wearing of personal dosimeters in Qingdao, China, and to provide a data basis for strengthening radiation protection and health management for interventional radiation workers. Methods A questionnaire survey was performed on all medical institutions with interventional radiation services in Qingdao. The data from April 1, 2020 to March 31, 2021 were pooled and analyzed. Results A total of 31 medical institutions in Qingdao were investigated, including 23 (74.20%) tertiary hospitals and 8 (25.80%) secondary hospitals. There were 88 pieces of interventional radiation equipment in total in Qingdao, 89.77% of which were in tertiary hospitals. A total of 921 interventional professionals participated, with 865 (93.92%) from tertiary hospitals and 56 (6.08%) from secondary hospitals. The mean annual number of visits to interventional services was 5.72 per 1000 people. Among personal protective equipment, the equipment rates of lead-rubber aprons, lead-rubber caps, and lead-rubber collars were highest, all being 100%. The rate of equipment of interventional protective gloves was lowest, which was only 51.61%. The mean number of each accessory protective equipment for each interventional machine was less than 1. The rate of wearing of dual-dosimeters was 84.36%. Conclusion Tertiary hospitals were dominant among the medical institutions in this survey of interventional radiology services in Qingdao. The most frequently equipped personal protective goods were lead-rubber aprons, caps, and collars. The equipment rates of interventional protective gloves and protective accessories and the rate of wearing of dual-dosimeters were relatively low.
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Objective To investigate the effect of gaseous effluent from the six generator sets on the radiation level of the surrounding terrestrial environment in Daya Bay Nuclear Power Base after the operation of Ling’ao Nuclear Power plant. Methods The radiation level in the peripheral environment of the Base was monitored using the thermoluminescence dosimeter （TLD）. Twenty-five monitoring sites were set around the Base to investigate the variation of radiation level over a long period of time by collecting the TLDs every three months. Results From 2011 to 2020, the annual γ dose rate of the 25 sites ranged from 76.7 to 207.1 nGy/h, with an average value of (123.3 ± 5.7) nGy/h and a relative deviation of 2%-12%. The TLD monitoring and instantaneous measuring results of γ dose rate were consistent with the survey of the State Environmental Protection Administration in the 20th century and the baseline level prior to the operation of the nuclear power plant. Conclusion There are great differences in natural environmental radiation level across the TLD monitoring sites. The overall environmental γ radiation level within 50 km of the nuclear power base remains unchanged. The emission of gaseous effluent from the operation of the nuclear power plant does not have a cumulative impact on the radiation level of surrounding environment.
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Objective To evaluate the performance of energy discriminating dosimeter and compare the impact of the assessment results. Methods CTLD-J4000 energy discriminating dosimeter was irradiated with different energy photons, and the differences covered by the dosimeters were used. Density filtering materials have different filtering effects on photons, and the ratio curve of the readings to the photon energy was fitted to identify the photon energy. Results The coincidence between the non-filter/light filter of the CTLD-J4000 energy discrimination dosimeter and the manufacturer's reference value was better than that of the non-filter/re-filter. The latter had higher deviation values at 48 keV(12.8%)and 83 keV(15.5%), respectively. Using the average scale factor, the maximum energy response deviation was 23.5%. Conclusion Using a discriminating dosimeter can better identify the ray energy, thereby reducing the energy response error caused by using the average scale factor.
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Objective:To investigate the application of therapeutic grade ionization chamber to rapid measurement of short pulsed and high-dose-rate X-ray.Methods:The half-value layer of pulsed X-ray caused by an electron accelerator was measured by interpolation method and its equivalent energy was estimated. The cumulative doses from a certain amount of pulsed radiation at different distances in the same direction around the equipment were compared using the therapeutic grade ionization chamber and thermoluminescence measurement method . The relationship between the measurement result by using ionization chamber dosimeter and the distances away from source was analyzed. The cumulative doses from a certain amount of pulsed radiation at the same location at different frequencies were compared.Results:In working condition, 100 pulses of radiation were received accumulatively at 1 to 12 meters away from the outer wall of the equipment. The range of air Kerma was 0.08-9.65 mGy measured by using thermoluminescence dometers and 0.08 - 9.85 mGy using the ionization chamber dosimeters, respectively. The difference between both is within 10%. At different frequencies (1-10 Hz), there was no significant difference in X-ray air Kerma from 100 pulses measured by ionization chamber dosimeter at 2 m away from the front of the equipment ( P>0.05). Conclusions:The therapeutic grade ionization chamber dosimeter can be used for the rapid measurement of short pulsed X-ray radiation dose in the range of dose rates and pulse frequencies involved in the experimental accelerator device.
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Objective@#To compare the test results of domestic and imported eye lens and ring dosimeters, and master some dosimetric performance indexes of eye lens and ring dosimeters.@*Methods@#According to IEC 62387—2012 and GBZ 128—2019, the performance of the eye lens dosimeters and ring dosimeters with the domestic thermoluminescence detectors were compared with the imported thermoluminescence detectors in photon response. The dose response deviation of the im- ported eye lens dosimeter and imported ring dosimeter was studied under the same irradiation condition. The difference of linear response between imported ring dosimeter and domestic ring dosimeter was studied under the same irradiation condition. @*Results@#The same dose was irradiated to domestic and imported thermoluminescence detectors in the imported eye lens and imported ring dosimeters, and the linear correlation coefficient all met R2 > 0.999. The maximum response devi- ation of the imported eye lens dosimeter and ring dosimeter was less than 10.0% for the same dose. Two kinds of imported ring dosimeters and one kind of domestic ring dosimeter were irradiated with the same dose, and the linear correlation coefficient all met R2 > 0.99.@*Conclusion@#Both domestic detectors and imported detectors can meet the needs of monitoring re- quirements. There was no obvious difference in linear response between imported ring dosimeter and domestic ring dosimet- er. The repeatability of imported eye lens dosimeter and imported ring dosimeter met the performance requirements of the dosimeter.
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Objective To compare the calibration result of standard X-ray RQR radiation field between SSDL (NIRP) and CEA LIST LNHB (France),and to explore the feasibility of calibrating Hp (3) in standard X-ray RQR radiation field of SSDL (NIRP).Methods Using a column model with a diameter and high of 20 cm,TLD was calibrated in SSDL (NIRP) and CEA LIST LNHB (France) to measure the personal dose equivalent eye lens dose Hp (3),X-ray RQR radiation field included RQR4 (60 kV),RQR7 (90 kV),RQR9 (120 kV),with energy response,angle response and linear response.Results In terms of energy response,the calibration results of TLD in both SSDL (NIRP) and CEA LIST LNHB (France) were in good agreement.The difference between exposure value and response value was less than 10％.In terms of angle response,the calibration result of TLD in CEA LIST LNHB (France) was better in SSDL (NIRP).The difference between exposure value and response value in CEA LIST LNHB (France) was less than 6％,while the difference between exposure value and response value in SSDI (NIRP) was more than 10％ at angle of 20°.In terms of linear response,both calibration result of SSDL (NIRP) and CEA LIST LNHB (France) were in good agreement.Conclusions The standard X-ray RQR field in SSDL (NIRP) can be used for the calibration of Hp (3).
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Objective@#To compare the calibration result of standard X-ray RQR radiation field between SSDL (NIRP) and CEA LIST LNHB(France), and to explore the feasibility of calibrating Hp(3) in standard X-ray RQR radiation field of SSDL(NIRP).@*Methods@#Using a column model with a diameter and high of 20 cm, TLD was calibrated in SSDL (NIRP) and CEA LIST LNHB (France) to measure the personal dose equivalent eye lens dose Hp(3), X-ray RQR radiation field included RQR4(60 kV), RQR7(90 kV), RQR9(120 kV), with energy response, angle response and linear response.@*Results@#In terms of energy response, the calibration results of TLD in both SSDL (NIRP) and CEA LIST LNHB (France) were in good agreement. The difference between exposure value and response value was less than 10%. In terms of angle response, the calibration result of TLD in CEA LIST LNHB (France) was better in SSDL(NIRP). The difference between exposure value and response value in CEA LIST LNHB (France) was less than 6%, while the difference between exposure value and response value in SSDL(NIRP) was more than 10% at angle of 20°. In terms of linear response, both calibration result of SSDL (NIRP) and CEA LIST LNHB (France) were in good agreement.@*Conclusions@#The standard X-ray RQR field in SSDL (NIRP) can be used for the calibration of Hp(3).
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Aim: In the present study, surface doses within the target area and contralateral breast (CLB) received during conventional treatment of carcinoma breast are evaluate and compared for treatment on two different beam energies, i.e., Co-60 γ-ray and 6 MV X-ray beams with thermoluminescent dosimeter, LiF:Mg, Ti (TLD-100). Materials and Methods: The study includes a group of 23 patients comprising 11 patients treated with Co-60 γ-ray beam and 12 patients by 6 MV X-ray beam. Results and Discussion: The treatment using Co-60 γ-ray and 6 MV X-ray beams contributes an average percentage dose of 8.15% ± 0.56% and 4.73% ± 0.94%, respectively, to CLB in mastectomy patients. The contribution of tangential fields (mastectomy) to the CLB doses ranges between 12.71 and 16.40 cGy (5.45%–7.03%) for treatment with Co-60 γ-ray beam and 6.33–10.95 cGy (1.86–4.69%) for treatment with 6 MV X-ray beam. The supraclavicular field (SCF) contributes 1.45%–1.93% and 1.02%–1.43% for treatment with Co-60 γ-ray and 6 MV X-ray beams, respectively. The average surface dose (normalized with breast dose) 89.1% ± 8.5% for Co-60 beam in the SCF region differs significantly from the 60.2% ± 13.0% value for 6 MV X-ray beam. Conclusion: The CLB doses for mastectomy patients are higher for Co-60 beam as compared to 6 MV X-ray beam, and better dose homogeneity is achieved within the irradiated breast from 6 MV X-ray beam. The CLB doses are slightly higher for patients treated with breast conservative radiotherapy or lumpectomy. The average surface dose to SCF decreases by ~30% of treated breast dose for treatment with 6 MV X-ray beam
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Purpose: In low-density (LD) gel dosimeter, diffusive spin–spin relaxation rate (R2)-dispersion caused by susceptibility-induced internal gradient leads to a significant deviation in the measured R2 from the real value. In this study, the effect of induced internal gradient on R2 was visualized and quantified algebraically as an important cause of inaccuracy in LD gel dosimeters. Materials and Methods: In this method, two sets of LD and unit-density (UD) gel dosimeters were prepared. The LD gel was made by mixing the UD gel with expanded polystyrene spheres. The R2 was used to determine the spatially resolved decay rates due to diffusion in internal magnetic field. The internal gradient was calculated for a multiple spin–echo sequence. Results: It is shown that in a LD gel, the internal gradient leads to overestimation of mean R2 value (R2mean). Pixel-by-pixel R2 measurements inside a LD gel showed significant deviation from R2 mapping in UD gel. Conclusion: It appears that significant differences between R2mean in a selected region of interest and pixel-by-pixel R2 values are the main source of inaccuracy in dose mapping of a LD gel
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Objective To estimate the hand dose of occupational staff in five procedures of interventional radiology.Methods The thermoluminescence ring dosimeter(TLD,LiF:Mg,Ti)calibrated in dose equivalent Hp(0.07) was used to monitor the radiation dose to the both hands in five procedures of interventional radiology in four hospitals.Meanwhile,the tube voltage and current and the fluoroscopy time,accumulated doses,DAPs (Dosed-Area Product) and photographic frames were also recorded for statistical analysis(SPSS 18.0).Results In this study,five interventional procedures were monitored in 119 cases.The doses to the left and right hands of occupational personnel in the five interventional procedures were analyzed,and the difference was statistically significant (t =1.99,P＜ 0.05).The differences in the dose to the left hand and the right hand of the first operator with different interventional procedures were statistically significant (F =455.83,116.45,P＜0.01).Tube voltage,current,fluoroscopy time,and photographic frames in influence factor analysis were statistically significant (r =0.570,0.712,0.564,0.711,P＜ 0.05),indicating that four factors might affect the operator's hand doses.In addition,increasing these four factors directly led to increase in the operator's hand doses.The variables with statistical significance in the above single factor analysis were introduced into the multiple linear regression equation and the stepwise regression method was used to fit the equation.The fitting equation was y=225.763+ 1.862x1-98.125x2 (F=22.726,P＜0.05).Where,x1 was the fluoroscopy time and x2 was the photographic frames which showed that they were the main factors affecting the hand dose.Conclusions The dose to the hands of the primary operator was the highest,followed by the second operator,the assistant or nurses.The order of average doses to the hands of the primary operator was PM＞RFA＞CA＞ PTCA+PCI ＞ ITCA in the five procedures.The annual equivalent dose to primary operator's hands may exceed the dose limit for hands in practicing large amount of the PM procedures.
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Objective: To carry out comparative study on energy respond characteristics of 4 kinds of medical diagnostic X-ray dosimeters that included general new imported equipment and domestic equipment.Methods: In the standard radiation field of secondary standard dosimetry laboratory(SSDL)of IAEA,substitution method was adopted to complete contrast measurement of 10 kinds of X-ray diagnosis radiations which voltage were 60-150 kV,tube current were 10 mA and 2.5 mmAl was used as filterable addition.Results: The results of energy respond performances of domestic RD-98 diagnosis dosimeter and imported dosimeter indicated that all of these responses of different energy to dose were within ±5％when X-ray range was 6-150 kV.Conclusion: The energy response characteristics of 4 kinds of new diagnosis X-ray dosimeter were better,and the response of different energy to dose conforms to the requirement of IEC in diagnosis dosimeters of semiconductor detector and air ionization chamber.
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Objective To understand the dosimetric performance of energy differential type dosimeter.Methods A differential type dosimeter (CTLD-J4000) was chosed to conduct a series of dosimetric performance tests,including linear standard curves,relative response to mean photon radiation energy and incidence angle.Results The linear correlation of CTLD-J4000 energy differential dosimeter was good,with the average photon radiation energy response deviation within ± 20％ and the maximum incidence angle response deviation of 10％.The energy identification could be achieved according to the energy reference value provided by the manufacturer to a certain extent.Conclusions Further experiments are needed to find out the factors influencing measurement result from different dose values and incidence angles.
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Objective To measure the doses to eye lens and hands of workers,using thermo luminescent dosimeter (TLD) and optically stimulated luminescence dosimeter (OSLD).Methods TLDs in the same batch were annealed,packed and stuck to the flat abdomen of Alderson-Phantom at a distance of about 15 cm from 125I seed source,while irradiated at different doses:1.0,1.5,3.0,5.0,10.0,12.0,20.0,25.0,30.0,50.0 and 60.0 μ Gy.And then TLDs were measured by dosimeters to establish a dose calibration curve.By implanting seed source into the selected lung for 14 cases,belly for 10 cases,pelvic for 5 case and neck for 6 cases while placing calibrated TLDs on the left,middle and right above eyes,left and right hands of the workers to obtain the location-specific kerma values.Finally,the conversion factors Hp (3) and Hp (0.07) were used to calculate the values of dose equivalent to eye lens and hands.Additionally,OSLDs were used to measure the doses to workers in the same way.Results The TLD-measured eye lens dses to the operator and his assistant were 0.8 and 1.6 mSv in lungs,1.3 and 1.2 mSv in bellies,0.9 and 0.6 mSv in pelves,0.3 mSv in necks,respectively.Meanwhile,hand doses to the operator and his assistant were 1.4 and 2.1 mSv in lungs,1.2 and 1.0 mSv in bellies,0.5 and 0.9 mSv in pelves,0.1 mSv in necks,respectively.The maximum doses to eye lens and hands were 1.2 and 1.0 mSv,respectively in a single treatment.OSLD-measured dose equivalents from lung therapy were 0.2 and 0.1 mSv for eye lens of the operator and his assistant and 0.4 and 0.6 mSv for hands.For belly therapy,the accumulated dose equivalent to hands of the operator was 0.1 mSv while those for other types of therapy were 0 mSv.Conclusions TLDs have the capability to measure not only accumulated dose but also dose equivalent from a single therapy According to ICRP 118 publication and as estimated in the present study,the number of therapy should be not more than 17 every year.OSLDs only give the accumulated dose,the accuracy of which needs to be studied in low-dose measurement.
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Objective To use thermoluminescense dosimeters (TLDs) to evaluate the radiation doses to various critical organs in the computerized imaging reference systems (CIRS) 5 years old pediatric anthropomorphic phantom result ing from Varian kilovohage cone beam CT (kV-CBCT) system based on the standard scanning protocols.Effective dose were also calculated based on dose measurement.Methods A batch of TLDs with consistency no larger than 2％ were selected and annealed.First,the doses in an anthropomorphic pelvic phantom were measured using a CT chamber and TLDs,respectively,based on the standard pelvic protocols.The ratio of the both measurements is the TLD conversion coefficient.Other TLDs from the same batch were placed between two tissue-equivalent inserts and placed into the pre-drilled organ cavities of the pediatric phantom.By using standard protocols,the organs dose were measured,based on which the corresponding effective doses were calculated.Results The TLD conversion coefficient was 3.91 mGy/per reading.By using the standard head,low-dose thorax,pelvis protocol,the whole body effective dose was 0.63,6.85 and 19.3 mSv,respectively.Conclusions It is feasible for using the CT chamber-calibrated TLDs to measure the radiation doses from kV-CBCT to pediatric anthropomorphic phantom.The effective dose in pelvic protocol was higher than in thorax and head protocol,indicating that the pelvic protocol has a penitential to lead to larger radiation damage and higher risk of secondary cancer.
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Objective To measure absorbed dose and verify two-dimensional dose distribution from IMRT MLC using thermoluminescence dosimeters (TLDs) and films.Methods The teflon phantom was scanned by CT and its images were transmitted to TPS for planning.The 6 Gy-corresponding MUs were calculated at 90 cm SSD and 10 cm depth and on 5 cm × 5 cm radiation field.All the plans were implemented at 7 medical linear accelerators,which were produced by Varian,Elekta and Siemens and selected from 7 third-grade first-class hospitals according to the technical conditions of various regions in Sichuan province.The homogeneous solid phantoms used in hospitals were covered by 30 cm × 30 cm and 25 cm × 25 cm films.Then,the films were covered by thicker-than-20 cm phantoms.Finally,the plans were implemented by aligning the center of beams to the films center.Results The relative deviations of the measured absorbed dose to TPS-planned dose were 1.4％,3.7％,-2.5％,-0.3％,4.9％,4.9％,5.0％ for TLDs and 4.7％,4.3％,1.5％,3.9％,-1.6％,3.3％,-1.3％ for films,respectively,all consistent with the limit of less than 5％.The passing rates of 2D dose distribution (3 mm/3％) were 99.9％,98.5％,98.5％,97.9％ and 70.0％ for 5 accelerators,with only one not consistent with the requirements.Conclusions It is convenient to measure the absorbed dose to photon beam field and verify two-dimensional dose distribution using TLDs and films,which can provide quality assurance for radiation treatment plans.
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Objective To verify the absorbed dose and two-dimensional dosimetry delivered by MLC-shaped IMRT photon beams using thermoluminescent dosimeters (TLDs) and radiochromic films.Methods Different types of medical linear accelerators at 7 third-grade first-class hospitals in Hubei were selected for this audit study.Besides TLDs and films,a small polystyrene phantom measuring 15 cm × 15 cm × 15 cm,supplied by the International Atomic Energy Agency (IAEA),was also used.The TPS dose calculation were performed with 6 MV X-ray beam and by delivering 6 Gy dose to the TLDs or films at 10 cm depth for 5 cm × 5 cm field size at 90 cm SSD.After irradiation,comparations were conducted of dose derivations between TPS-calculated values and TLD-or film-measured values.The two-dimensional dosimetry audit was carried out by using 30 cm × 30 cm homogeneous solid phantoms in which a 25 cm × 25 cm film was located at 5 cm depth.A single-filed profile generated by TPS was delivered to the film,and the film was measured.And then,two-dimensional dose distribution was analyzed using the film analysis system.Results The results suggested that the relative deviations of TLD and film to TPS dose was-8.5％ and-1.9％ for accelerator 1,5.4％ and 0.5％ for accelerator 7,respectively,whereas those for other accelerators were within ± 5％.The passing rates for two-dimensional dose distribution at all accelerators were all higher than 90％.Conclusions TLD and film quality audit for IMRT can be applied for a wide range of application in view of its simplicity,reliability and postal convenience.