Occupational exposure to ionising radiation with thermoluminescence dosimetry system in Turkey, in 2003

The individual annual dose information on classified workers who are occupationally exposed to extended radiation sources by using thermoluminescence dosimetry system, in Turkey, was assessed and analysed by the Ankara Nuclear Research and Training Centre (ANAEM) dosimetry service at the Turkish Atomic Energy Authority (TAEK) for the year 2003. A total of 3721 persons were monitored with TLD and the data presented in this report were obtained by using TLD technology in 2003. The annual mean effective doses received from external radiation in different fields of activities and the distribution of the annual effective dose by dose intervals are presented. The collective annual dose by field of activity is estimated and the contribution to the total annual collective dose is determined.     

Occupational exposure in nuclear medicine in Portugal in the 1999-2003 period

The annual doses received by the staff of nuclear medicine departments from public hospitals and private clinics and evaluated by the Individual Monitoring Service of the Radiological Protection and Nuclear Safety Department (DPRSN) of the Nuclear and Technological Institute (ITN) in Portugal, in the 5 y period from 1999 to 2003, are analysed and presented in this paper. In the 1999-2003 period, ITN-DPRSN monitored on an average 462 workers from nuclear medicine departments, which represents 6% of the 8000 workers of the medical field (approximately). The medical sector represents 80-85% of all the monitored population in Portugal. The professions of the monitored workers at nuclear medicine departments were identified by the respective departments as administrative, auxiliary, medical doctor, nuclear medicine technician, nurse, pharmacist and physicist. This information was collected at the onset of the monitoring and was updated over the last 3 y. The annual whole-body doses evaluated in the period 1999-2003 were used to derive the distribution of workers by dose intervals for every profession. The respective annual average doses and annual collective doses, as well as, the total average and total collective doses for the nuclear medicine sector were also determined and are presented. Internal radiation hasn't been monitored.     

Integration of external and internal dosimetry in Switzerland

Individual monitoring regulations in Switzerland are based on the ICRP60 recommendations. The annual limit of 20 mSv for the effective dose applies to the sum of external and internal radiation. External radiation is monitored monthly or quarterly with TLD, DIS or CR-39 dosemeters by 10 approved external dosimetry services and reported as H(p)(10) and H(p)(0.07). Internal monitoring is done in two steps. At the workplace, simple screening measurements are done frequently in order to recognise a possible incorporation. If a nuclide dependent activity threshold is exceeded then one of the seven approved dosimetry services for internal radiation does an incorporation measurement to assess the committed effective dose E(50). The dosimetry services report all the measured or assessed dose values to the employer and to the National Dose Registry. The employer records the annually accumulated dose values into the individual dose certificate of the occupationally exposed person, both the external dose H(p)(10) and the internal dose E(50) as well as the total effective dose E = H(p)(10)+E(50). Based on the national dose registry an annual report on the dosimetry in Switzerland is published which contains the statistics for the total effective dose, as well as separate statistics for external and internal exposure.     

Databases in use at the individual monitoring service of ITN-DPRSN

In this work, the databases developed for routine use at the Individual Monitoring for External Radiation Service (IMS) of the Radiological Protection and Nuclear Safety Department (DPRSN) at the Nuclear and Technological Institute (ITN) in Portugal are presented. At the IMS there are two dosimetry systems running simultaneously, one based on film and the other one on thermoluminescent detectors (TLD). Two databases were initially and independently home-developed in order to meet each service's needs. A few modifications were introduced and while each service's requirements were maintained where needed, the databases were adapted in order to store the same type of information relative to the facilities and monitored workers, as well as to produce similar shaped reports and technical information. The necessary administrative features of the services were considered in the database development, made user-friendly and welcomed by the ordinary users. The improvements allowed a more direct analysis of the annual doses and an easy identification of professions and practices associated with higher dose values.     

Current status of personal dosimetry in industry, research and medicine in Lithuania

The personal dosimetry service of the Radiation Protection Centre performs individual monitoring for all the industrial, medical and research radiation workers. The RADOS and DTU TLD systems are used for monitoring of doses. The DTU TLD system is used for measurements of doses to extremities and for measurements of public external exposure. Finger ring TLDs are used in therapy which uses radiopharmaceuticals. The RADOS system is also used for evaluation of patients' doses in selected hospitals. The dosimetry service recently provided individual monitoring of approximately 3000 workers. The average occupational dose was about 1.06 mSv for medical workers and 3.2 mSv for industrial radiography workers in 1999. Detailed analysis of doses received by different categories of workers is performed. A system for the urgent review of work conditions in the case of increased dose has been set up.     

Occupational radiation protection dosimetry in Nigeria

The general features of occupational radiation protection dosimetry in Nigeria within the period 1990-1999 have been summarised. About 640 personnel, representing about 25% of the estimated number of radiation workers in Nigeria, were monitored by the TL dosimetry technique during the period, with the majority being the personnel of the teaching hospitals across the country. Most private establishments, especially the X ray diagnostic centres, operate without dosimetry coverage or supervision by a regulatory authority. The weighted mean of the annual effective dose ranged between 0 and 28.97 mSv with the upper limit of collective effective dose being 18.47 man.Sv per year. The individual risk estimate due to this is about 1.5 x 10(-3) per year and this was among the medical personnel. The value could be more if all radiation workers in the country were monitored.     

Assessment of annual whole-body occupational radiation exposure in medical practice in Ghana (2000-09)

Occupational exposure to radiation in medical practice in Ghana has been analysed for a 10-y period between 2000 and 2009. Monitored dose data in the medical institution in Ghana from the Radiation Protection Institute's database were extracted and analysed in terms of three categories: diagnostic radiology, radiotherapy and nuclear medicine. One hundred and eighty medical facilities were monitored for the 10-y period, out of which ~98% were diagnostic radiology facilities. Only one nuclear medicine and two radiotherapy facilities have been operational in the country since 2000. During the 10-y study period, monitored medical facilities increased by 18.8%, while the exposed workers decreased by 23.0%. Average exposed worker per entire medical institution for the 10-y study period was 4.3. Annual collective dose received by all the exposed workers reduced by a factor of 4 between 2000 and 2009. This is seen as reduction in annual collective doses in diagnostic radiology, radiotherapy and nuclear medicine facilities by ~76, ~72 and ~55%, respectively, for the 10-y period. Highest annual collective dose of 601.2 man mSv was recorded in 2002 and the least of 142.6 man mSv was recorded in 2009. Annual average values for dose per institution and dose per exposed worker decreased by 79 and 67.6%, respectively between 2000 and 2009. Average dose per exposed worker for the 10-y period was least in radiotherapy and highest in diagnostic radiology with values 0.14 and 1.05 mSv, respectively. Nuclear medicine however recorded average dose per worker of 0.72 mSv. Correspondingly, range of average effective doses within the diagnostic radiology, radiotherapy and nuclear medicine facilities were 0.328-2.614, 0.383-0.728 and 0.448-0.695 mSv, respectively. Throughout the study period, an average dose per medical institution of 3 mSv and an average dose per exposed worker of 0.69 mSv were realised. Exposed workers in diagnostic radiology primarily received most of the individual annual doses >1 mSv. The entire study period had 705 instances in which exposed workers received individual annual doses >1 mSv. On thermoluminescent dosemeter (TLD) return rates, facilities in Volta and Eastern Regions recorded highest return rates of 94.3% each. Ashanti Region recorded the least TLD return rate with 76.7%.     

Personal dose monitoring of employees at the institute of modern physics, China

The radiation field at the accelerator facility consists of radiation produced immediately and of secondary radiation induced by activation etc. As the accelerator building and the experimental hall are closed and inaccessible during accelerator operation, the exposure received by the employees at the IMP (Institute of Modern Physics) comes almost totally from the induced radiation. The methods and the results of personal dose monitoring from 1986 to 1999 at the IMP are presented. During the period, the total number of monitored individuals was 1960, and the average annual effective dose was 0.10 mSv. The number recording less than 0.1 mSv of effective dose was 1471 individuals. amounting to 77% of the total. Only six individuals had received effective doses between 5.0 mSv and 10 mSv. The maximum effective dose of 10 mSv was received by workers repairing the accelerator.     

Analysis of radiation workers' dose records in the Korean National Dose Registry

Data are presented on the externally received personal dose equivalent for radiation workers who used the Korea Radioisotope Association's personal monitoring and dose record keeping service since 1984, and provide initial statistics on Korean workers who have been exposed to ionising radiation in different occupations. The total number of workers registered during the period of 1984 to 1999 was 64,518. The number increased steadily and the accumulated dose also increased. The proportion of radiation workers by occupation was 38.4% for nuclear power plants, 20.3% for industrial organisations and 12.4% for non-destructive industry. The annual collective dose of radiation workers was 31.72 man.Sv in 1999. The mean annual dose by sex was 1.49 mSv for males and 0.56 mSv for females and the mean annual dose for a worker was 1.41 mSv with the highest mean dose being received by non-destructive industry (3.53 mSv). Very few workers (0.8%) received more than 20 mSv (2 rem) and only one more than 50 mSv, the legal limit for an annual dose increase. There has been a steady decline in the mean dose since 1984, showing a significant decrease in dose with time (p<0.001). The data showed that radiation protection in Korea was improving, though annual doses were still higher than other countries.     

Analysis of occupational doses of workers on the dose registry of the Federal Radiation Protection Service in 2000 and 2001

In 2000 and 2001 about 279 and 221 radiation workers, respectively, were monitored by the Federal Radiation Protection Service, University of Ibadan, in Nigeria. The distribution of the occupational doses shows that the majority of workers received doses below 4 mSv in each of the two years. The radiation workers in the two years are classified into two occupational categories: medicine and industry. The mean annual effective doses, collective doses and the collective dose distribution ratios for workers in each category and the entire monitored workers were calculated. The mean annual effective doses were compared with their corresponding worldwide values quoted by UNSCEAR. In each of the two years, a few workers in industry received doses higher than 50 mSv. The collective dose distribution ratio was found to be about 0.49, which is very close to the highest value of 0.5 in the range of values considered by UNSCEAR as normal for this parameter. This suggests that extra measures have to be taken, particularly in industry, to ensure that the proportion of workers at risk does not go outside this normal range. The occupational doses were also modelled by both the log-normal and Weibull distributions. Both distributions were found to describe the data in almost the same way.     

An assessment of annual whole-body occupational radiation exposure in Ireland (1996-2005)

Whole-body occupational exposure to artificial radiation sources in Ireland for the years 1996-2005 has been reviewed. Dose data have been extracted from the database of the Radiological Protection Institute of Ireland, which contains data on >95% of monitored workers. The data have been divided into three sectors: medical, industrial and education/research. Data on exposure to radon in underground mines and show caves for the years 2001-05 are also presented. There has been a continuous increase in the number of exposed workers from 5980 in 1996 to 9892 in 2005. Over the same time period, the number of exposed workers receiving measurable doses has decreased from 676 in 1996 to 189 in 2005 and the collective dose has also decreased from 227.1 to 110.3 man millisievert (man mSv). The collective dose to workers in the medical sector has consistently declined over the 10-y period of the study while that attributable to the industrial sector has remained reasonably static. In the education/research sector, the collective dose typically represents 5% or less of the total collective dose from all practices. Over the 10 y of the study, a total of 77 914 annual dose records have been accumulated, but only 4040 (<6%) of these represent measurable radiation doses in any given year. Over the same time period, there were 283 instances in which exposed workers received individual annual doses >1 mSv and 21 of these exceeded 5 mSv. Most of the doses >1 mSv were received by individuals working in diagnostic radiology (which also includes interventional radiology) in hospitals and site industrial radiography. There has been only one instance of a dose above the annual dose limit of 20 mSv. Evaluating the data for the period 2001-05 separately, the average annual collective dose from the medical, industrial and educational/research sectors are approximately 60, 70 and 2 man mSv with the average dose per exposed worker who received a measurable dose being 0.32, 0.79 and 0.24 mSv, respectively. Diagnostic radiology and site industrial radiography each represents >60% of the collective dose in their respective sectors. Available data on radon exposure in one underground mine and in three show caves indicate an annual collective dose of 75 man mSv from these work activities. By comparison, previous estimates of exposure of Irish air crew to cosmic radiation have given rise to an estimated collective dose of 12 000 man mSv. It can be concluded therefore that the natural radioactivity sources account for well >90% of all occupational exposure in Ireland. This evaluation does not include an estimate of exposure to radon in above-ground workplaces-these data are currently being evaluated and their inclusion will increase both the total occupational collective dose as well as the percentage of that dose due to natural radiation.     

Occupational exposure to ionising radiation in the region of Anatolia, Turkey for the period 1995-1999

For this study, the individual annual dose information on classified workers who are occupationally exposed to extended radiation sources in Turkey, was assessed and analysed by the Ankara Nuclear Research and Training Centre dosimetry service at the Turkish Atomic Energy Authority for the years 1995-1999. The radiation workers monitored are divided into three main work sectors: conventional industry (8.24%), medicine (90.20%) and research-education (1.56%). The average annual dose for all workers in each particular sector was 0.14, 0.38 and 0.08 mSv, respectively, in 1995-1999. This paper contains the detailed analysis of occupational exposure. The statistical analysis provided includes the mean annual dose, the collective dose, the distributions of the dose over the different sectors and the number of workers who have exceeded any of the established dose levels.     

Occupational exposures of Chinese medical radiation workers in 1986-2000

Data on occupational exposures from medical uses of radiation in China during 1986-2000 are presented. Individual dose monitoring results in the reports of monitoring centres in different provinces in China during 1986-2000 were collected as the basic data. These data were summarised and then analysed. From 1986 to 2000, in diagnostic radiology, nuclear medicine and radiotherapy, the annual collective effective doses varied within the range 122.4-206.6, 5.4-9.3 and 4.1-10.3 man Sv, respectively; the average annual effective dose in these categories varied within the range 1.5-2.2, 1.2-1.6 and 1.0-1.5 mSv, respectively. Almost all the average annual effective doses in medical uses of radiation were <3 mSv in 1986-2000, and no monitored workers were found to have received an occupational exposure >50 mSv in a single year or >100 mSv in a 5-y period. After 1990, the protection status of medical radiation workers in China was sufficient.     

A Brazilian government external individual monitoring service: experience since 1972

Instituto de Radioprote??o e Dosimetria, a Brazilian government research institute, provides individual monitoring services since 1972. Its dosemeters are: film-based thorax for whole body photons, thermoluminescence dosimetry (TLD) albedo for whole body neutrons and TLD ring for extremity photons. About 6000 radiation workers are currently being monitored with film dosemeters in 256 different facilities in Brazil, most of them working in health-related activities. Around 400 Brazilian radiation workers are monitored with TLD albedo neutron monitor and about 500 workers use TLD rings. This paper describes the monitoring systems used, presents the results obtained in internal quality programs and in intercomparison exercises and analyses the measured dose values from 1985 to 2009.     

Personnel doses in haemodynamic units in Greece

Personnel of haemodynamic and interventional radiology units receive continuously increasing radiation doses due to extended fluoroscopy. Moreover, there is not a parallel increase in the number of cardiology specialists involved. Doses received by 15 cardiologists and 5 nurses, in 5 Athenian hospitals were measured using thermoluminescence dosemeters (TLD) and film badges. The workload and examination protocol of each cardiologist, the technical characteristics of the X ray unit, as well as availability and use of protective equipment were recorded. Results show that doses measured by TLD and film badges differ due mainly to the irregular wear of the latter. Although X ray units performed comparably with each other, dose per procedure received by each cardiologist varied widely, due to differences in examination protocol and beam collimation used. In all cases, nurses' dose was approximately one fourth of cardiologists' dose. In half of the cases assessed, the protective equipment available was not in full use. Estimation of dose per procedure, taking into account personnel's workload assesses annual personnel doses. Evaluation of risk level and check of compliance with regulatory dose limits should be part of continuing radiation protection education.     

Implementation of dose management system at radiation protection board of Ghana Atomic Energy Commission

The dose management system (DMS) is a computer software developed by the International Atomic Energy Agency for managing data on occupational exposure to radiation sources and intake of radionuclides. It is an integrated system for the user-friendly storage, processing and control of all existing internal and external dosimetry data. The Radiation Protection Board (RPB) of the Ghana Atomic Energy Commission has installed, customised, tested and using the DMS as a comprehensive DMS to improve personnel and area monitoring in the country. Personnel dose records from the RPBs database from 2000 to 2009 are grouped into medical, industrial and education/research sectors. The medical sector dominated the list of monitored institutions in the country over the 10-y period representing ～87 %, while the industrial and education/research sectors represent ～9 and ～4 %, respectively. The number of monitored personnel in the same period follows a similar trend with medical, industrial and education/research sectors representing ～74, ～17 and ～9 %, respectively. Analysis of dose data for 2009 showed that there was no instance of a dose above the annual dose limit of 20 mSv, however, 2.7 % of the exposed workers received individual annual doses >1 mSv. The highest recorded individual annual dose and total collective dose in all sectors were 4.73 mSv and 159.84 man Sv, respectively. Workers in the medical sector received higher individual doses than in the other two sectors, and average dose per exposed worker in all sectors is 0.25 mSv.     

Routine individual monitoring of aircraft crew exposure: Czech experience and results since 1998

ICRP Publication 60 recommended that the radiation exposure due to the cosmic component at high altitudes be considered when appropriate as part of occupational exposure to the radiation. The recommendation was incorporated to the Czech regulation in 1997, and the studies on how to perform individual dosimetry of Czech companies aircraft crew started immediately. The individual monitoring values were calculated using the Transport code CARI. The results obtained since the beginning have been recalculated, now with the version 6. The information on the flight schedules and the participation of aircraft crew in the flight were received from the air company. Routine individual dosimetry had started in 1998. Main results for the period 1998-2003 are as follows: both relative frequencies, as well as, average annual effective doses vary with the company and with the year, without any evident general tendency; the average annual values of E were between 1.5 and 2 mSv; and collective effective dose increased regularly, from approximately 1.5 manSv to >2.2 manSv. More detailed analysis is presented, including the verification of the procedure by a series of onboard experimental measurements.     

Dose level of occupational exposure in China

This paper discusses the dose level of Chinese occupational exposures during 1986-2000. Data on occupational exposures from the main categories in nuclear fuel cycle (uranium enrichment and conversion, fuel fabrication, reactor operation, waste management and research activity, except for uranium mining and milling because of the lack of data), medical uses of radiation (diagnostic radiation, nuclear medicine and radiotherapy) and industrial uses of radiation (industrial radiography and radioisotope production) are presented and summarised in detail. These are the main components of occupational exposures in China. In general, the average annual effective doses show a steady decreasing trend over periods: from 2.16 to 1.16 mSv in medical uses of radiation during 1990-2000; from 1.92 to 1.18 mSv in industrial radiography during 1990-2000; from 8.79 to 2.05 mSv in radioisotope production during the period 1980-2000. Almost all the average annual effective doses in discussed occupations were lower than 5 mSv in recent years (except for well-logging: 6.86 mSv in 1999) and no monitored workers were found to have received the occupational exposure exceeding 50 mSv in a single year or 100 mSv in a five-year period. So the Chinese protection status of occupation exposure has been improved in recent years. However, the average annual effective doses in some occupations, such as diagnostic radiology and coal mining, were still much higher than that of the whole world. There are still needs for further improvement and careful monitoring of occupational exposure to protect every worker from excessive occupational exposure, especially for the workers who were neglected before.     

Occupational exposure to external ionising radiation in Poland, 1999

In 1999 about 6208 radiation workers from 389 departments were monitored by CLOR in Poland. The distribution of annual personal doses shows that 85% of controlled workers received doses below the MDL (0.4 mSv) and about 97% controlled workers received doses below 5 mSv. Doses higher than 50 mSv were received by three operators of industrial radiography units. The radiation workers under control are divided into four main work sectors: nuclear industry, research and education, medicine, and general industry. The average annual dose for all workers in each particular sector was 0.22 mSv, 0.22 mSv, 0.30 mSv and 0.80 mSv, respectively. The average annual dose for the entire monitored population was 0.47 mSv. The average annual dose in each particular sector for number of workers receiving E > 0, i.e. Hp(10) > or = 0.4 mSv, amounted to 1.78 mSv, 2.03 mSv, 1.88 mSv and 4.85 mSv, respectively. The average annual dose for the full number of workers receiving E > 0 was 3.21 mSv. This paper contains the detailed analysis of occupational exposure. The distributions of annual occupational exposure in different work sectors are also given.     

Assessment of annual whole-body occupational radiation exposure in education, research and industrial sectors in Ghana (2000-09)

Institutions in the education, research and industrial sectors in Ghana are quite few in comparison to the medical sector. Occupational exposure to radiation in the education, research and industrial sectors in Ghana have been analysed for a 10 y period between 2000 and 2009, by extracting dose data from the database of the Radiation Protection Institute, Ghana Atomic Energy Commission. Thirty-four institutions belonging to the three sectors were monitored out of which ～65% were in the industrial sector. During the 10 y study period, monitored institutions ranged from 18 to 23 while the exposed workers ranged from 246 to 156 between 2000 and 2009. Annual collective doses received by all the exposed workers reduced by a factor of 2 between 2000 and 2009. This is seen as a reduction in annual collective doses in education/research and industrial sectors by ～39 and ～62%, respectively, for the 10 y period. Highest and least annual collective doses of 182.0 man mSv and 68.5 man mSv were all recorded in the industrial sector in 2000 and 2009, respectively. Annual average values for dose per institution and dose per exposed worker decreased by 49 and 42.9%, respectively, between 2000 and 2009. Average dose per exposed worker for the 10 y period was least in the industrial sector and highest in the education/research sector with values 0.6 and 3.7 mSv, respectively. The mean of the ratio of annual occupationally exposed worker (OEW) doses for the industrial sector to the annual OEW doses for the education/research sector was 0.67, a suggestion that radiation protection practices are better in the industrial sector than they are in the education/research sector. Range of institutional average effective doses within the education/research and industrial sectors were 0.059-6.029, and 0.110-2.945 mSv, respectively. An average dose per all three sectors of 11.87 mSv and an average dose per exposed worker of 1.12 mSv were realised for the entire study period. The entire study period had 187 instances in which exposed workers received individual annual doses >1 mSv, with exposed workers in the education/research sector primarily receiving most of this individual dose.