Radiation Dose to Post-Chernobyl Cleanup Workers

Science.gov (United States)

Radiation dose calculation for post-Chernobyl Cleanup Workers in Ukraine - both external radiation exposure due to fallout and internal doses due to inhalation (I131 intake) or ingestion of contaminated foodstuffs.

Dose Data Analysis of the Occupational Exposed Workers in Slovenia in 2000

International Nuclear Information System (INIS)

Janzekovic, H.; Breznik, B.; Jovanovic, P.; Zdesar, U.; Rojc, J.; Stuhec, M.; Vaupotic, J.

2001-01-01

Full text: The Central State Dose Register at the Health Inspectorate includes dosimetry data of all occupationally exposed workers in the year 2000 in Slovenia. The register contains a comprehensive set of data related to the registered dose of around 4500 workers. The set includes among others the following parameters: type of workplaces based on the extended UNSCEAR form, classification of sources based on the ICPR 60 weighting factors, employer identification, licensee identification, personal data of workers, worker cumulative dose received in the past, data related to the worker education concerning radiation protection and data related to the worker health surveillance. The analysis of the external and internal dose data for the year 2000 regarding the dose limits given in 96/29/Euratom and the state legislation will be given. The dose analysis of the annual doses as well of monthly doses measured in different branches of industry, medicine, education and state institutions will be presented. The comparison of the doses received by different categories of workers will be shown. The measured doses above 4 mSv per month will be discussed. The common problems related to the assurance of the correct measurements of the doses will be also briefly discussed. (author)

Trends in doses to radiation workers recorded on the Central Index of Dose Information

International Nuclear Information System (INIS)

Greenslade, E.; Kendall, G.M.; Fillary, K.; Bines, W.P.

1991-01-01

This paper presents a preliminary analysis of the doses stored on the Central Index of Dose Information for the calendar years 1986, 1987 and 1988. Mean doses are low, and both mean doses and the proportion of workers exceeding 15 mSv in a year are decreasing with time. Underground miners are the occupational group receiving the highest doses, though in this and other relatively high dose groups the exposures are falling with time. Only 6% of workers are female and their average individual dose is about half that of men. Patterns of employment are different for women and men but there is a tendency for women to receive lower doses than men even within the same occupation. (author)

AGING FACILITY WORKER DOSE ASSESSMENT

International Nuclear Information System (INIS)

R.L. Thacker

2005-01-01

The purpose of this calculation is to estimate radiation doses received by personnel working in the Aging Facility performing operations to transfer aging casks to the aging pads for thermal and logistical management, stage empty aging casks, and retrieve aging casks from the aging pads for further processing in other site facilities. Doses received by workers due to aging cask surveillance and maintenance operations are also included. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation. There are no Category 1 event sequences associated with the Aging Facility (BSC 2004 [DIRS 167268], Section 7.2.1). The results of this calculation will be used to support the design of the Aging Facility and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Environmental and Nuclear Engineering

Doses to road transport workers from radioactive materials

International Nuclear Information System (INIS)

Lawrence, B.E.; van der Vooren, A.

1988-12-01

Each year approximately 750,000 packages of radioactive materials are shipped throughout Canada. Regulatory controls on these shipments are designed to keep radiation doses received by transport workers well within acceptable limits. Since many of these workers are not monitored for radiation exposure, however, little factual information has been available in Canada to support theoretical estimates. A study to document actual radiation doses received by a select group of transport workers that is actively involved in the shipment of radioactive materials, was carried out in 1987 and 1988. This study involved the monitoring of 31 candidates from nine transport companies from across the country that handle medical isotopes, industrial isotopes, uranium fuel cycle materials and associated radioactive wastes. Each of the candidates (consisting of driver, dock workers, sorters, and supervisors) was issued personal thermoluminescent dosimeter (TLD) badges that were worn each day during the six month monitoring period. Some of the candidates were also issued cab or area dosimeters that were left in the cabs of the vehicles or in work areas so that the dose received in these areas could be differentiated from total personal exposure. During the monitoring program, the candidates filled out reporting sheets at the end of each working day to document information such as the quantity of materials handled, handling times and vehicle size. This information and the dosimetry data were used in the development of correlations between materials handled and doses reported so that doses for other handling similar materials could be estimated. Based on the results of the study, it was learned that while most of the transport workers receive doses that are at or near background levels, other (particularly those handling medical isotopes) are exposed to levels of radiation that may result in their receiving doses above the 5 mSv per annum limit set for members of the general public. On

Dose received by radiation workers in Australia, 1991

Energy Technology Data Exchange (ETDEWEB)

Morris, N D

1994-07-01

Exposure to radiation can cause genetic defects or cancer. People who use sources of radiation as part of their employment are potentially at a greater risk than others owing to the possibility of their being continually exposed to small radiation doses over a long period. In Australia, the National Health and Medical Research Council has established radiation protection standards and set annual effective dose limits for radiation workers in order to minimise the chance of adverse effects occurring. These standards are based on the the recommendations of the International Commission on Radiological Protection (ICRP 1990). In order to ensure that the prescribed limits are not exceeded and to ensure that doses are kept to a minimum, some sort of monitoring is necessary. The primary purpose of this report is to provide data on the distribution of effective doses for different occupational categories of radiation worker in Australia. The total collective effective dose was found to be of the order of 4.9 Sv for a total of 34750 workers. 9 refs., 16 tabs., 6 figs.

Dose received by radiation workers in Australia, 1991

International Nuclear Information System (INIS)

Morris, N.D.

1994-07-01

Exposure to radiation can cause genetic defects or cancer. People who use sources of radiation as part of their employment are potentially at a greater risk than others owing to the possibility of their being continually exposed to small radiation doses over a long period. In Australia, the National Health and Medical Research Council has established radiation protection standards and set annual effective dose limits for radiation workers in order to minimise the chance of adverse effects occurring. These standards are based on the the recommendations of the International Commission on Radiological Protection (ICRP 1990). In order to ensure that the prescribed limits are not exceeded and to ensure that doses are kept to a minimum, some sort of monitoring is necessary. The primary purpose of this report is to provide data on the distribution of effective doses for different occupational categories of radiation worker in Australia. The total collective effective dose was found to be of the order of 4.9 Sv for a total of 34750 workers. 9 refs., 16 tabs., 6 figs

Analysis of the occupational doses of female radiation workers in India

Energy Technology Data Exchange (ETDEWEB)

Pardasani, P B; Joshi, V D; Awari, J M; Kher, R K [Bhabha Atomic Research Centre, Mumbai (India). Radiation Protection Services Div.

1994-04-01

Basis for control of occupational exposures of women are same as that of men except for pregnant women. Analysis of annual and cumulative occupational doses of female radiation workers as a group has been done. The average annual dose data in the four broad categories and age wise dose distribution is presented. The average working period for female radiation workers is about 3 to 5 years which is same as that of all the radiation workers on our records. The average cumulative dose for female workers is about 3 mSv. (author). 4 refs., 4 tabs.

Analysis of the occupational doses of female radiation workers in India

International Nuclear Information System (INIS)

Pardasani, P.B.; Joshi, V.D.; Awari, J.M.; Kher, R.K.

1994-01-01

Basis for control of occupational exposures of women are same as that of men except for pregnant women. Analysis of annual and cumulative occupational doses of female radiation workers as a group has been done. The average annual dose data in the four broad categories and age wise dose distribution is presented. The average working period for female radiation workers is about 3 to 5 years which is same as that of all the radiation workers on our records. The average cumulative dose for female workers is about 3 mSv. (author). 4 refs., 4 tabs

Assessment and recording of radiation doses to workers

International Nuclear Information System (INIS)

1986-01-01

The assessment and recording of the radiation exposure of workers in activities involving radiation risks are required for demonstrating compliance with institutional dose limitations and for a number of other complementary purposes. A significant proportion of the labor force involved in radiation work is currently represented by those specialised workers who operate as itinerant contractors for different nuclear installations and in different countries. In order to ensure that the exposure of these workers is adequately and consistently controlled and kept within acceptable limits, there is a need for the criteria and methods for dose assessment and recording to be harmonised throughout the different countries. An attempt in that direction has been made in this report, which has been prepared by a group of experts convened by the Committee on Radiation Protection and Public Health of the OECD Nuclear Energy Agency. Its primary purpose is to describe recommended technical procedures for an unified approach to the assessment and recording of worker doses. The report is published under the responsibility of the Secretary-General of the OECD, and does not commit Member governments

Trends in doses to some UK radiation workers

International Nuclear Information System (INIS)

Best, R.J.; Kendall, G.M.; Pook, E.A.; Saunders, P.J.

1990-01-01

The NRPB runs a Personal Monitoring Service which issues dosemeters and keeps radiation dose records for over 10 000 workers. This database is a valuable source of information on occupational exposure to radiation though it is likely that in future the Central Index of Dose Information (CIDI) will provide more comprehensive statistics, albeit restricted to radiation workers in the sense of Ionising Radiation Regulations. This note describes doses incurred to the end of 1987 with some preliminary figures for 1988. It does not cover the same ground as earlier reports but gives more details of the structure of the monitored population by age and sex and examines evidence that mean radiation doses are decreasing with time. (author)

Radiation dose to workers due to the inhalation of dust during granite fabrication

International Nuclear Information System (INIS)

Zwack, L M; Stewart, J H; McCarthy, J F; Allen, J G; McCarthy, W B

2014-01-01

There has been very little research conducted to determine internal radiation doses resulting from worker exposure to ionising radiation in granite fabrication shops. To address this issue, we estimated the effective radiation dose of granite workers in US fabrication shops who were exposed to the maximum respirable dust and silica concentrations allowed under current US regulations, and also to concentrations reported in the literature. Radiation doses were calculated using standard methods developed by the International Commission on Radiological Protection. The calculated internal doses were very low, and below both US occupational standards (50 mSv yr −1 ) and limits applicable to the general public (1 mSv yr −1 ). Workers exposed to respirable granite dust concentrations at the US Occupational Safety and Health Administration (OSHA) respirable dust permissible exposure limit (PEL) of 5 mg m −3 over a full year had an estimated radiation dose of 0.062 mSv yr −1 . Workers exposed to respirable granite dust concentrations at the OSHA silica PEL and at the American Conference of Governmental Industrial Hygienists Threshold Limit Value for a full year had expected radiation doses of 0.007 mSv yr −1 and 0.002 mSv yr −1 , respectively. Using data from studies of respirable granite dust and silica concentrations measured in granite fabrication shops, we calculated median expected radiation doses that ranged from <0.001 to 0.101 mSv yr −1 . (paper)

Occupational radiation doses among diagnostic radiation workers in South Korea, 1996-2006

International Nuclear Information System (INIS)

Lee, W. J.; Cha, E. S.; Ha, M.; Jin, Y. W.; Hwang, S. S.; Kong, K. A.; Lee, S. W.; Lee, H. K.; Lee, K. Y.; Kim, H. J.

2009-01-01

This study details the distribution and trends of doses of occupational radiation among diagnostic radiation workers by using the national dose registry between 1996 and 2006 by the Korea Food and Drug Administration. Dose measurements were collected quarterly by the use of thermoluminescent dosemeter personal monitors. A total of 61 732 workers were monitored, including 18 376 radiologic technologists (30%), 13 762 physicians (22%), 9858 dentists (16%) and 6114 dental hygienists (9.9%). The average annual effective doses of all monitored workers decreased from 1.75 to 0.80 mSv over the study period. Among all diagnostic radiation workers, radiologic technologists received both the highest effective and collective doses. Male radiologic technologists aged 30-49 y composed the majority of workers receiving more than 5 mSv in a quarter. More intensive monitoring of occupational radiation exposure and investigation into its health effects on diagnostic radiation workers are required in South Korea. (authors)

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

International Nuclear Information System (INIS)

Ogundare, F.O.; Balogun, F.A.

2003-01-01

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. (author)

Recent trend of radiation doses of medical workers

Energy Technology Data Exchange (ETDEWEB)

Anzai, I [Tokyo Univ. (Japan). Faculty of Medicine; Tanaka, M; Nakamura, S; Nawa, H; Nukazawa, A

1981-10-01

Radiation doses of medical workers in Japan between 1976 and 1979 were analysed based on the data provided by a film badge servicing company. Average annual radiation doses between April, 1978 and March, 1979 were 129 mrems for 2556 doctors, 108 mrems for 2074 radiographers, and 60 mrems for 1915 nurses. It was also suggested that the log-normal distribution could provide a good fit to the frequency distribution of radiation doses of these medical staffs. Time series data of monthly average doses during the period between April, 1976 and March, 1979 were analysed using a computer code named EPA that had been developed by the Japanese Economic Planning Agency. The EPA code separated the original time series data into three components, i.e., the trend and cycle factor, the seasonal factor and the irregular factor based on a multiplicative model. The results of analyses strongly suggested that there existed a significant common pattern among the trend factors of doctors, radiographers and nurses. The similar phenomenon was also observed about the seasonal factors. Some specific cases of medical workers who received considerably high radiation doses were studied, and it was pointed out that, in order to lower the doses of medical workers, the factors which are peculiar to each medical facility must be precisely examined in addition to the strengthening of general radiological protective measures.

The analysis of annual dose distributions for radiation workers

International Nuclear Information System (INIS)

Mill, A.J.

1984-05-01

The system of dose limitation recommended by the ICRP includes the requirement that no worker shall exceed the current dose limit of 50mSv/a. Continuous exposure at this limit corresponds to an annual death rate comparable with 'high risk' industries if all workers are continuously exposed at the dose limit. In practice, there is a distribution of doses with an arithmetic mean lower than the dose limit. In its 1977 report UNSCEAR defined a reference dose distribution for the purposes of comparison. However, this two parameter distribution does not show the departure from log-normality normally observed for actual distributions at doses which are a significant proportion of the annual limit. In this report an alternative model is suggested, based on a three parameter log-normal distribution. The third parameter is an ''effective dose limit'' and such a model fits very well the departure from log-normality observed in actual dose distributions. (author)

Longevity extension of worker honey bees (Apis mellifera) by royal jelly: optimal dose and active ingredient

OpenAIRE

Yang, Wenchao; Tian, Yuanyuan; Han, Mingfeng; Miao, Xiaoqing

2017-01-01

In the Western honey bee, Apis mellifera, queens and workers have different longevity although they share the same genome. Queens consume royal jelly (RJ) as the main food throughout their life, including as adults, but workers only eat worker jelly when they are larvae less than 3 days old. In order to explore the effect of RJ and the components affecting longevity of worker honey bees, we first determined the optimal dose for prolonging longevity of workers as 4% RJ in 50% sucrose solution,...

The Mayak Worker Dosimetry System (MWDS-2013): determination of the individual scenario of inhaled plutonium intake in the Mayak workers

International Nuclear Information System (INIS)

Sokolova, A. B.; Efimov, A. V.; Vostrotin, V. V.; Birchall, A.; Dorrian, M.-D.

2017-01-01

In order to estimate doses of workers exposed to plutonium, it is necessary to make assumptions about both the route and the time course of intake. The objective of this study was to determine a time course for the inhalation rate for plutonium (intake regime) useful for biokinetic modeling. Records from workplace air sampling, personnel biophysical examinations and autopsy data from former Mayak Production Association (MPA) workers were used. Plutonium accumulation strongly correlated with the volumetric activity of plutonium in workplace air. Using data from activity in air at MPA workplaces over time, a three-step function of intake was adopted. The adequacy of this three-step function was tested by comparing predicted doses using more complicated intake regimes. Uncertainties on the three-step function were also characterized based on air sampling data. The three-step function was assumed to be common to all workers, but an individual intake regime for each worker was calculated by convoluting it with the worker's actual employment history. (authors)

A survey of doses to worker groups in the nuclear industry

International Nuclear Information System (INIS)

Khan, T.A.; Baum, J.W.

1991-01-01

The the US National Council on Radiation Protection and Measurements (NCRP) has suggested ''...as guidance for radiation programs that cumulative exposure not exceed the age of the individual in years x 10 mSv (years x 1 rem).'' The International Commission on Radiological Protection (ICRP) has recommended a dose limit of 10 rem averaged over 5 years. With these developments in mind, the US Nuclear Regulatory Commission (NRC) requested the ALARA Center of the Brookhaven National Laboratory to undertake two parallel studies. One study, which is still ongoing, is to examine the impact of the newly recommended dose limits on the nuclear industry as a whole; the other study was intended to assist in this larger project by looking more closely at the nuclear power industry. Preliminary data had indicated that the critical industry as far as the impact of new regulatory limits were concerned would be the nuclear power industry, because, it was conjectured, there existed a core of highly skilled workers in some groups which routinely get higher than average exposures. The objectives of the second study were to get a better understanding of the situation vis grave a vis the nuclear power industry, by identifying the high-dose worker groups, quantifying the annual and lifetime doses to these groups to see the extent of the problem if there was one, and finally to determine if there were any dose-reduction techniques which were particularly suited to reducing doses to these groups. In this presentation we describe some of the things learned during our work on the two projects. For more detailed information on the project on dose-reduction techniques for high-dose worker groups in the nuclear power industry, see NUREG/CR-5139. An industry/advisory committee has been set up which is in the process of evaluating the data from the larger project on the impact of new dose limits and will shortly produce its report. 7 refs., 5 figs., 6 tabs

Levels of doses to radiological workers in Ethiopia: 1977-1988

International Nuclear Information System (INIS)

Bayou, Teshome.

1991-01-01

During the period 1977 to 1988, a total of 10,494 Eastman Kodak type 2 film badges and 19,236 Vinten lithium fluoride thermoluminescence dosimeters (TLDS) were delivered to medical workers in Ethiopia of which 5,135 (48.93%) film badges and 19,177 (99.69%) TLDS were evaluated. The annual average occupational doses to the workers were estimated to be of 1.44 and 4.51 man-Sv with corresponding collective dose equivalents to 0.29 and 4.51 man-Sv respectively. Comparisons of doses to similar workers in different countries were compiled from the literature. Based on the TLD results and the 1977 International Commission on Radiological Protection (ICRP) risk coefficients it is estimated that the occurrence of extra fatal and non-fatal cancer cases is in the order of 74 per million radiological workers per year. The hereditary defects expected are 18 and 36 cases in the next two and in all future generations respectively. During these periods, the number of institutions monitored rose from 35 to 88 while the workers monitored increased from 100 to 450

A study on exposure dose from injection work and elution work for radiation workers and frequent workers in nuclear medicine

International Nuclear Information System (INIS)

Ju, Yong Jin; Chung, Woon Kwan; Dong, Kyung Rae; Choi, Eun Jin; Kwak, Jong Gil; Ryu, Jae Kwang

2017-01-01

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a signifcant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity

A study on exposure dose from injection work and elution work for radiation workers and frequent workers in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Ju, Yong Jin; Chung, Woon Kwan [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of); Dong, Kyung Rae [Dept. of Radiological Technology, Gwangju Health University, Gwangju (Korea, Republic of); Choi, Eun Jin; Kwak, Jong Gil [Dept. of Public Health and Medicine, Dongshin University Graduate School, Naju (Korea, Republic of); Ryu, Jae Kwang [Dept. of Nuclear Medicine, Asan Medical Center, Seoul (Korea, Republic of)

2017-03-15

Compared to other occupations, there is a greater risk of exposure to radiation due to the use of radioisotopes in nuclear medicine for diagnostic evaluations and therapy. To consider ways to reduce exposure dose for those in nuclear medicine involved in injection work and elution work among radiation workers as well as for sanitation workers and trainees among frequent workers an investigation into exposure dose and situational analysis from changes in yearly exposure dose evaluations, changes in work environment and changes in forms of inspection were conducted. Exposure dose measurements were taken by using EPD MK2 worn during working hours for one injection worker, one elution worker, two sanitation workers, and one trainee at a general hospital in the Seoul area for three days from July 18th to 20th 2016. Radiation from radioisotopes which are a part of nuclear medicine can significantly affect not only radiation workers who deal with radioisotopes directly but also frequency works as well. According to this study the annual dose limit for elution workers and injection workers were considered safe as the amount of exposure was not large enough to have a signifcant effect. The limits of this study consist in the duration of this study and the quantity of participants. Also there was a limitation of the measurement device involving accumulated exposure, where the EPD MK2 cannot check the changes in exposure according to a particular activity.

Workers doses in central European PWR NPPs

International Nuclear Information System (INIS)

Janzekovic, H.; Krizman, M.

2003-01-01

As is stated, the ISOE database which was established in 1992 forms an excellent basis for studies and comparisons of occupational exposure data between nuclear power plants. In the year 2001, 69% of all participating reactors were pressurised water reactors. The ISOE database presents workers' exposure from 213 participating pressurised reactors (PWR) from 27 countries in that year. Among these 32 PWRs belong to six Central European Countries. The analysis of the exposure of workers based on radiation protection performance indicators (collective dose, average dose etc.) in these PWRs could be related to some nuclear safety performance indicators for recent years using ISOE database. The comparison is made to ISOE world - wide data. In the six Central European Countries altogether 32 PWR operated in the year 2001.The international databases of performance indicators related to radiation protection as for example the ISOE or the UNSCEAR database can be use as an efficient tool in the management of radiation protection of workers in a nuclear facilities and regulatory bodies. The databases enable the study of performance trends and the improvement of radiation protection. (authors)

Study of External Radiation Expose Dose on Hands of Nuclear Medicine Workers

International Nuclear Information System (INIS)

Park, Jun Chul; Pyo, Sung Jae

2012-01-01

The aims of this study are to assess external radiation exposed doses of body and hands of nuclear medicine workers who handle radiation sources, and to measure radiation exposed doses of the hands induced by a whole body bone scan with high frequency and handling a radioactive sources like 99m Tc-HDP and 18 F-FDG in the PET/CT examination. Skillful workers, who directly dispense and inject from radiation sources, were asked to wear a TLD on the chest and ring finger. Then, radiation exposed dose and duration exposed from daily radiation sources for each section were measured by using a pocket dosimeter for the accumulated external doses and the absorbed dose to the hands. In the survey of four medical institutions in Incheon Metropolitan City, only one of four institutions has a radiation dosimeter for local area like hands. Most of institutions uses radiation shielding devices for the purpose of protecting the body trunk, not local area. Even some institutions were revealed not to use such a shielding device. The exposed doses on the hands of nuclear medicine workers who directly handles radioactive sources were approximately twice as much as those on the body. The radiation exposure level for each section of the whole body bone scan with high frequency and that of the PET/CT examination showed that radiation doses were revealed in decreasing order of synthesis of radioactive medicine and installation to a dispensing container, dispensing, administering and transferring. Furthermore, there were statistically significant differences of radiation exposure doses of the hands before and after wearing a syringe shielder in administration of a radioactive sources. In this study, although it did not reach the permissible effective dose for nuclear medicine, the occupational workers were exposed by relatively higher dose level than the non-occupational workers. Therefore, the workers, who closely exposed to radioactive sources should be in compliance with safety

Health effects of low doses at low dose rates: dose-response relationship modeling in a cohort of workers of the nuclear industry

International Nuclear Information System (INIS)

Metz-Flamant, Camille

2011-01-01

The aim of this thesis is to contribute to a better understanding of the health effects of chronic external low doses of ionising radiation. This work is based on the French cohort of CEA-AREVA NC nuclear workers. The mains stages of this thesis were (1) conducting a review of epidemiological studies on nuclear workers, (2) completing the database and performing a descriptive analysis of the cohort, (3) quantifying risk by different statistical methods and (4) modelling the exposure-time-risk relationship. The cohort includes monitored workers employed more than one year between 1950 and 1994 at CEA or AREVA NC companies. Individual annual external exposure, history of work, vital status and causes of death were reconstructed for each worker. Standardized mortality ratios using French national mortality rates as external reference were computed. Exposure-risk analysis was conducted in the cohort using the linear excess relative risk model, based on both Poisson regression and Cox model. Time dependent modifying factors were investigated by adding an interaction term in the model or by using exposure time windows. The cohort includes 36, 769 workers, followed-up until age 60 in average. During the 1968- 2004 period, 5, 443 deaths, 2, 213 cancers, 62 leukemia and 1, 314 cardiovascular diseases were recorded. Among the 57% exposed workers, the mean cumulative dose was 21.5 milli-sieverts (mSv). A strong Healthy Worker Effect is observed in the cohort. Significant elevated risks of pleura cancer and melanoma deaths were observed in the cohort but not associated with dose. No significant association was observed with solid cancers, lung cancer and cardiovascular diseases. A significant dose-response relationship was observed for leukemia excluding chronic lymphatic leukemia, mainly for doses received less than 15 years before and for yearly dose rates higher than 10 mSv. This PhD work contributes to the evaluation of risks associated to chronic external radiation

Summary of recorded external radiation doses for Hanford workers 1944--1989

International Nuclear Information System (INIS)

Buschbom, R.L.; Gilbert, E.S.

1993-10-01

This report summarizes recorded external radiation doses for the years 1944 through 1989 received by operations workers who were included in the Hanford Mortality Study. This study population includes all operations workers who were initially employed at the Hanford site from 1944 through 1978. Descriptive summaries are provided for both annual and cumulative whole body penetrating doses. Although the main emphasis of the report is on recorded whole body penetrating dose, summary tables are included for the components of whole body penetrating dose, non-penetrating dose, and extremity dose. Summaries are provided for the entire study population and for subgroups of the population defined by sex, age, number of years since first monitoring, and socioeconomic groups

Trend of collective dose and dose reduction measures of Mitsubishi Electric Corporation workers in nuclear power plants

International Nuclear Information System (INIS)

Yamato, I.; Nakayama, T.; Shimokawa, F.; Yamamoto, T.

1996-01-01

MELCO has supplied the reactor instrumentation control system, reactor coolant pump motors, turbine generator and central control system for the pressurized water type nuclear power plant. For the legal periodical inspection and repair work, MELCO has also received orders for the periodical inspection for 23 power plants (including 4 plants under construction) of 5 electric power companies, and executed the inspection work from the view point of preventive maintenance. The annual dose for MELCO's workers is liable to be decreased in spite of increased number of plants. The dose for new plant in particular is 50, or less as compared with that for conventional plant. This is because the measures taken for the conventional plant against the dose reduction is reflected upon the new plant. The dose reduction measures are taken for each system for which order was received. Such measures are mainly intended to improve the work procedures and equipment for reduction of work time in the radioactive area and to arrange the working process, so as to perform the work in such period when the dose level at the working environment is low. To enhance the workers' consciousness for reduction of dose, MELCO provided the workers with dose predictive training, and let them aware of such items known at the tool box briefing (TBX), which could realize the dose reduction for workers. MELCO has been positively promoting the activity to arrange the desirable work environment for extermination of 3Ks (giken, gitsui, titanai) or 3Ds (dangerous, difficult, dirty) including protection against radiation in corporation with electric power companies. (author)

Comments on ICRP-60 rationale for dose limits for the pregnant worker

International Nuclear Information System (INIS)

Myers, D.K.

1992-06-01

ICRP Publication 60 has recently recommended new dose limits for the radiation exposure of pregnant workers. These new dose limits for pregnant workers are more restrictive than the current limits in force in Canada. Recent presentations by Dr. R.H. Mole have faulted the arguments provided by ICRP as justification for reducing the previously recommended limits for pregnant radiation workers. The present paper provides a brief review of the development of the human conceptus, of the biological effects of low doses of radiation on the foetus, and discusses R.H. Mole's comments on ICRP-60. On the critical issues concerning the presence or absence of threshold doses for induction of specific biological endpoints, Dr. Mole and ICRP-60 appear to be in agreement. The basic disagreement between Dr. Mole and ICRP-60 seems to revolve around the philosophical question of whether dose limits should be based on quantitative risks to the foetus or whether dose limits to the pregnant worker should provide a standard of protection to the foetus which is broadly comparable with that provided for members of the general public. Further research is recommended on one of the topics raised by Dr. Mole, namely, foetal doses from radionuclides inhaled or ingested by the mother

Estimation of radiation dose received by the radiation workers during radiographic testing

International Nuclear Information System (INIS)

Mohammed, N. A. H. O.

2013-08-01

This study was conducted primarily to evaluate occupational radiation dose in industrial radiography during radiographic testing at Balil-Hadida, with the aim of building up baseline data on radiation exposure in the industrial radiography practice in Sudan. Dose measurements during radiographic testing were performed and compared with IAEA reference dose. In this research the doses measured by using hand held radiation survey meter and personal monitoring dosimeter. The results showed that radiation doses ranged between minimum (0.448 mSv/ 3 month) , and maximum (1.838 mSv / 3 month), with an average value (0.778 mSv/ 3 month), and the standard deviation 0.292 for the workers used gamma mat camera. The analysis of data showed that the radiation dose for all radiation worker are receives less than annual limit for exposed workers 20 mSv/ year and compare with other study found that the dose received while body doses ranging from 0.1 to 9.4 mSv/ year, work area design in all the radiography site followed the three standard rules namely putting radiation signs, reducing access to control area and making of boundaries. Thus the accidents arising from design faults not likely to occur at these site. Results suggest that adequate fundamental training of radiation workers in general radiography prior to industrial radiography work will further improve the standard of personnel radiation protection. (Author)

Annual dose distribution of Nuclear Malaysia radiation workers for monitoring period from year 2003 to 2007

International Nuclear Information System (INIS)

Hairul Nizam Idris; Azimawati Ahmad; Norain Ab Rahman

2008-08-01

Estimation of radiation dose (external exposure) received by Nuklear Malaysia's radiation workers are measured by using personal dosimetry device which are provided by SSDL-Nuklear Malaysia. Dose assessment report for monitoring period from year 2003 - 2007 shows that almost all radiation workers received annual doses less than 20 mSv, only in very small percentage of radiation workers received annual doses between 20.1 to 50 mSv and none of the workers received doses higher than 50 mSv/year. Exposure dose below 20 mSv/year (the new annual dose limit to be used in Malaysia soon) could be fully achieved by improving the compliance with the safety regulations and enhancing the awareness about radiation safety among the workers. (Author)

Longevity extension of worker honey bees (Apis mellifera by royal jelly: optimal dose and active ingredient

Directory of Open Access Journals (Sweden)

Wenchao Yang

2017-03-01

Full Text Available In the Western honey bee, Apis mellifera, queens and workers have different longevity although they share the same genome. Queens consume royal jelly (RJ as the main food throughout their life, including as adults, but workers only eat worker jelly when they are larvae less than 3 days old. In order to explore the effect of RJ and the components affecting longevity of worker honey bees, we first determined the optimal dose for prolonging longevity of workers as 4% RJ in 50% sucrose solution, and developed a method of obtaining long lived workers. We then compared the effects of longevity extension by RJ 4% with bee-collected pollen from rapeseed (Brassica napus. Lastly, we determined that a water soluble RJ protein obtained by precipitation with 60% ammonium sulfate (RJP60 contained the main component for longevity extension after comparing the effects of RJ crude protein extract (RJCP, RJP30 (obtained by precipitation with 30% ammonium sulfate, and RJ ethanol extract (RJEE. Understanding what regulates worker longevity has potential to help increase colony productivity and improve crop pollination efficiency.

Longevity extension of worker honey bees (Apis mellifera) by royal jelly: optimal dose and active ingredient.

Science.gov (United States)

Yang, Wenchao; Tian, Yuanyuan; Han, Mingfeng; Miao, Xiaoqing

2017-01-01

In the Western honey bee, Apis mellifera , queens and workers have different longevity although they share the same genome. Queens consume royal jelly (RJ) as the main food throughout their life, including as adults, but workers only eat worker jelly when they are larvae less than 3 days old. In order to explore the effect of RJ and the components affecting longevity of worker honey bees, we first determined the optimal dose for prolonging longevity of workers as 4% RJ in 50% sucrose solution, and developed a method of obtaining long lived workers. We then compared the effects of longevity extension by RJ 4% with bee-collected pollen from rapeseed ( Brassica napus ). Lastly, we determined that a water soluble RJ protein obtained by precipitation with 60% ammonium sulfate (RJP 60 ) contained the main component for longevity extension after comparing the effects of RJ crude protein extract (RJCP), RJP 30 (obtained by precipitation with 30% ammonium sulfate), and RJ ethanol extract (RJEE). Understanding what regulates worker longevity has potential to help increase colony productivity and improve crop pollination efficiency.

Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Seo, JaeSeok; Jeong, SeongYoung; Lee, JungJun; Song, HaeSang; Lee, SangWha; Son, BongKi

2014-01-01

Highlights: • The method of exposure dose assessment to workers during decommissioning of nuclear facilities. • The environments of simulation were designed under a virtual reality. • To assess exposure dose to workers, human model was developed within a virtual reality. - Abstract: This objective of this paper is to develop a method to simulate and assess the exposure dose to workers during decommissioning of nuclear facilities. To simulate several scenarios, decommissioning environments were designed using virtual reality. To assess exposure dose to workers, a human model was also developed using virtual reality. The exposure dose was measured and assessed under the principle of ALARA in accordance with radiological environmental change. This method will make it possible to plan for the exposure dose to workers during decommissioning of nuclear facilities

The Study of External Radiation Dose for Radiation Worker at PRSG-BATAN Serpong

International Nuclear Information System (INIS)

Sunarningsih; Mashudi; A Lilik W; Yosep S

2012-01-01

The study of External radiation dose for radiation worker at PRSG-BATAN Serpong has been carried out. The sample is taken from the System Reactor division (BSR), Operation Reactor division, (BOR) Safety division UPN, UJM and head of PRSG by setting Thermoluminescence Dosemeter (TLD) on the chest, then is detected by a tool TLD reader model 6600. The aim of this study is to evaluate the occupational exposure dose that has been accepted by the radiation worker for the last five years. The result in average doses at BSR is 0,99 mSv, BOR is 3,27 mSv, at BK is 0,69 mSv and UPN + UJM + head of PRSG is 0,03 mSv. The result highest doses at BSR is 6,58 mSv, BOR is 28,94 mSv, BK is 4,24 mSv, and UPN UJM Head of PRSG is 0,52 mSv. Dose interval radiation worker at PRSG BATAN ttd - 28,98 mSv. To overall the external personal dose acceptant for radiation worker at PRSG BATAN one below maximum permissible dose acceptant that allowed by BAPETEN, that is 20 mSv in average every year during five years. (author)

Personal radiation monitoring and assessment of doses received by radiation workers (1991)

International Nuclear Information System (INIS)

Morris, N.D.

1992-06-01

The Australian Radiation Laboratory has operated a Personal Radiation Monitoring Service since the early 1930's so that people working with radiation can determine the radiation doses that they receive due to their occupation. Since late 1986, all persons monitored by the Service have been registered on a data base which maintains records of the doses received by each individual wearer. Ultimately, this data base will become a National Register of the doses received within Australia. At present, the Service regularly monitors approximately 20,000 persons, which is roughly 70 percent of those monitored in Australia, and maintains dose histories of over 35,000 people. The skin dose for occupationally exposed workers can be measured by using one of the four types of monitor issued by the Service: 1. Thermoluminescent Dosemeter (TLD monitor) 2. Finger TLD 3. Neutron Monitor 4. Special TLD. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 4 figs

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

International Nuclear Information System (INIS)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo; Koo, Bon Cheol; Chang, Byung Uck

2016-01-01

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries

Development of internal dose assessment procedure for workers in industries using raw materials containing naturally occurring radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Choi, Cheol Kyu; KIm, Yong Geon; Ji, Seung Woo; Kim, Kwang Pyo [College of Engineering, Kyung Hee University, Yongin (Korea, Republic of); Koo, Bon Cheol; Chang, Byung Uck [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2016-09-15

It is necessary to assess radiation dose to workers due to inhalation of airborne particulates containing naturally occurring radioactive materials (NORM) to ensure radiological safety required by the Natural Radiation Safety Management Act. The objective of this study is to develop an internal dose assessment procedure for workers at industries using raw materials containing natural radionuclides. The dose assessment procedure was developed based on harmonization, accuracy, and proportionality. The procedure includes determination of dose assessment necessity, preliminary dose estimation, airborne particulate sampling and characterization, and detailed assessment of radiation dose. The developed dose assessment procedure is as follows. Radioactivity concentration criteria to determine dose assessment necessity are 10 Bq·g-1 for 40K and 1 Bq·g-1 for the other natural radionuclides. The preliminary dose estimation is performed using annual limit on intake (ALI). The estimated doses are classified into 3 groups (<0.1 mSv, 0.1-0.3 mSv, and >0.3 mSv). Air sampling methods are determined based on the dose estimates. Detailed dose assessment is performed using air sampling and particulate characterization. The final dose results are classified into 4 different levels (<0.1 mSv, 0.1-0.3 mSv, 0.3-1 mSv, and >1 mSv). Proper radiation protection measures are suggested according to the dose level. The developed dose assessment procedure was applied for NORM industries in Korea, including coal combustion, phosphate processing, and monazite handing facilities. The developed procedure provides consistent dose assessment results and contributes to the establishment of optimization of radiological protection in NORM industries.

Professional exposure of medical workers: radiation levels, radiation risk and personal dose monitoring

International Nuclear Information System (INIS)

Bai Guang

2005-01-01

The application of radiation in the field of medicine is the most active area. Due to the rapid and strong development of intervention radiology at present near 20 years, particularly, the medical workers become a popularize group which most rapid increasing and also receiving the must high of professional exposure dose. Because, inter alias, radiation protection management nag training have not fully follow up, the aware of radioactive protection and appropriate approach have tot fully meet the development and need, the professional exposure dose received by medical workers, especially those being engaged in intervention radiology, are more higher, as well as have not yet fully receiving the complete personal dose monitoring, the medical workers become the population group which should be paid the most attention to. The writer would advice in this paper that all medical workers who being received a professional radiation exposure should pay more attention to the safety and healthy they by is strengthening radiation protection and receiving complete personal dose monitoring. (authors)

Determination of eye lens doses and identification of risk groups among radiation exposed workers. An Austrian pilot study; Bestimmung der Augenlinsen-Dosis und Identifizierung von Risikogruppen bei beruflich strahlenexponierten Personen. Eine Pilotstudie in Oesterreich

Energy Technology Data Exchange (ETDEWEB)

Stadtmann, H.; Hranitzky, C.; Willer, H. [Seibersdorf Labor GmbH, Seibersdorf (Austria). Radiation Protection Dosimetry; Strebl, F.; Ernst, G. [Seibersdorf Labor GmbH, Seibersdorf (Austria). Radiation Safety and Applications; Aspek, W. [Allgemeine Unfallversicherungsanstalt (AUVA), Wien (Austria). Abt. Unfallverhuetung und Berufskrankheitenbekaempfung (HUB)

2015-07-01

On European level, in 2014 the dose limit for the lens of the eye of radiation exposed workers has been reduced from 150 to 20 mSv per year (2013/59/Euratom). Data about eye lens exposition measured under realistic operational conditions of Austrian radiation exposed workers is sparse and there is no information to verify, if all professional groups identified to be at risk for elevated eye doses will remain below the new annual dose limit. Therefore, financed by the Austrian Workers Compensation Board, AUVA, a pilot study has been initiated to answer this question. Based on published information professional groups of radiation exposed workers and operational tasks with an enhanced risk of elevated eye lens doses have been identified. By dosimetric measurements with volunteers (forehead dose meters and parallel measurements with whole-body TL-dose meters above and under the lead apron) realistic lens doses will be estimated during selected radiation exposed tasks. Comparison of yielded doses will show whether a TLD outside the apron could serve as an alternative to forehead dose meters dedicated to measure eye lens doses. Measurements with leaded protective eyewear based on IEC61331 yield results for lead equivalent in good agreement with manufacturers' information. Results for eye lens doses determined by use of a RANDO head phantom and a standardized phantom simulating a body in a typical exposition situation for interventional radiologists show that wearing of leaded goggles allows for a 90% dose reduction. Under such conditions the eye lens dose is dominated by backscatter and stray radiation from the operator's head and patient body. This has to be considered for the evaluation of protective effectiveness for leaded eye wear.

Dose Record Analysis of External Exposure of Workers in Madagascar

International Nuclear Information System (INIS)

Andriambololona, R.; Ratovonjanahary, J. F.; Randriantsizafy, R. D.

2004-01-01

External personnel monitoring of workers in diagnostic radiology in Madagascar using thermoluminescence techniques has been studied in previous work for the period of 1990 to 2000. The study was based on the average of Hp(0.07) and Hp(10) and on the annual dose distribution. The results showed that mean doses are very low compared with the annual dose limits for workers of 20 mSv per year and are comparable with natural contribution of telluric X and gamma exposure which is evaluated as 3.21 mSv per year in Antananarivo. No trend in the average was observed, however, the last 4 years, the results showed a substantial decrease in the average from 2 mSv to 1 mSv. It was assumed that this was the impact of the implementation by radiation staff in their workplace of the in force regulation which is in compliance with the new basic safety standards. Indeed, since 1996, Madagascar-Institut National des Sciences et Techniques Nucleaires (Madagascar-INSTN) and the Association Nationale de Radioprotection de Madagascar (ANARAPMAD), the Madagascar radiation protection society and associate member of IRPA, set up a national program for training of radiation workers. The number of workers trained during this period is evaluated as 50% of the total number of radiation workers in Madagascar. The present work is a continuation of the above mentioned survey during the period of 2001 to 2003. The training program was upgraded to involve personnel who will be in charge of radiation protection and safety in workplace and the training cycle lasts 2 years instead of 3 days in the previous program. The survey has been extended to include all radiation workers in Madagascar though the medical field is still the main application and represents more than 90 percent of the latter. The results shows that for this last 3 years, an other substantial decrease from 1 mSv to 0.5 mSv was observed in the average. In the dose distribution, more than 98 percent of the Hp(0.07) and more than 99

Ocular organ dose assessment of nuclear medicine workers handling diagnostic radionuclides

International Nuclear Information System (INIS)

Cho, Yong In; Kim, Ja Mee; Kim, Jung Hoon

2017-01-01

The dose distribution in the ocular organs of nuclear medicine workers during the handling of diagnostic radionuclides was assessed via simulation in virtual space. The cornea and lenses received the highest dose, and the dose distribution tended to be proportional to the gamma-ray energy emitted from the radiation source being handled. Moreover, calculations on the dose-reduction effects of eye-wear protectors for the eyes of the workers showed that the effects were inversely proportional to the emitted gamma-ray energy, with the dose-reduction effect decreasing in the order of "2"0"1Tl, "1"2"3I, "9"9mTc, "6"7Ga, "1"1"1In and "1"8F. Among the considered sources, the dose-reduction effect was significant for sources that emit relatively less energy, namely "1"2"3I, "2"0"1Tl and "9"9mTc, while it was lower for the remaining sources, namely "1"8F, "1"1"1In and "6"7Ga. (authors)

Social-demographic profile and dose evaluation of the radiopharmaceutical facility workers

Energy Technology Data Exchange (ETDEWEB)

Sanches, Matias P.; Carneiro, Janete C. Gaburo; Sordi, Gian Maria A.A. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)], e-mail: msanches@ipen.br

2009-07-01

The main aims of this work are to identify the social-demographic profile of the workers based on stratification variables such as gender, age, and tasks performed by the workers, and to evaluate the annual collective doses of workers with potential risk of ionizing radiation exposure at the workplace during the years 2004 to 2008. In this context, the knowledge of the workforce composition in the facility responsible for the radioisotope production and its distribution was used. The individual monitoring programme has been carried out by individual dosimeters, TLDs, and internal contamination monitoring (in vivo method). The reported doses, in the period studied, suggest that the external exposure was the main source of occupational exposure in radioisotope production and distribution areas. The internal exposure was not included in the doses estimated, because it was negligible. This study has an important exploratory character, in order to analyze possible correlations related to adverse health effects, aiming to provide directions for occupational epidemiology research. (author)

Social-demographic profile and dose evaluation of the radiopharmaceutical facility workers

International Nuclear Information System (INIS)

Sanches, Matias P.; Carneiro, Janete C. Gaburo; Sordi, Gian Maria A.A.

2009-01-01

The main aims of this work are to identify the social-demographic profile of the workers based on stratification variables such as gender, age, and tasks performed by the workers, and to evaluate the annual collective doses of workers with potential risk of ionizing radiation exposure at the workplace during the years 2004 to 2008. In this context, the knowledge of the workforce composition in the facility responsible for the radioisotope production and its distribution was used. The individual monitoring programme has been carried out by individual dosimeters, TLDs, and internal contamination monitoring (in vivo method). The reported doses, in the period studied, suggest that the external exposure was the main source of occupational exposure in radioisotope production and distribution areas. The internal exposure was not included in the doses estimated, because it was negligible. This study has an important exploratory character, in order to analyze possible correlations related to adverse health effects, aiming to provide directions for occupational epidemiology research. (author)

Estimation of annual dose equivalent (internal and external) for new thorium plant workers of IRE OSCOM, Orissa

International Nuclear Information System (INIS)

Vidya Sagar, D.; Tripathy, S.K.; Khan, A.H.; Maharana, L.N.

2001-01-01

In addition to thoron, thoron daughters and gamma radiation, the New Thorium Plant workers are exposed to long lived alpha emitters due to inhalation of thorium fine dust present in the working environment. Air samplers were used for measurement of thoron daughters and long lived alpha concentration. Each sample was counted for 3-4 hours for alpha activity and the long lived alpha concentration was calculated after taking the self absorption effect of the deposit on the filter paper into account. Internal dose of individual workers due to thoron daughter concentration and long lived alpha concentration was determined using time weighted factors. Based on the results, it is observed that contribution of thoron daughters, long lived alpha and external gamma is about 2 mSv /y, 1 mSv /y and 5 mSv/y, respectively, to total dose to the workers. (author)

The Assessment of I-131 Internal Doses of Nuclear Medicine Workers in Korea Using Thyroid uptake system

International Nuclear Information System (INIS)

Bahn, Young Kag; Oh, Gi Back; Lee, Chang Ho; Lee, Jong Doo; Yeom, Yu Sun; Hwang, Young Muk

2012-01-01

There are possibilities the radiation workers could intake the radiation when workers deal with radiation-materials. Therefore, internal radiation doses of radiation workers need to be assessed. Although an application of the nuclear medicine is continuously increased in Korea, there is not a proper tool and form to monitor the internal doses of nuclear medicine workers. However, it is possible to attain the internal doses of I-131 to evaluate using thyroid uptake and well count system. In this study, we measured and evaluated the I-131 internal doses of nuclear medicine workers in Korea using thyroid uptake and well count system and performed an air sampling

A comparative analysis of exposure doses between the radiation workers in dental and general hospital

International Nuclear Information System (INIS)

Yang, Nam Hee; Chung, Woon Kwan; Dong, Kyung Rae; Ju, Yong Jin; Song, Ha Jin; Choi, Eun Jin

2015-01-01

Research and investigation is required for the exposure dose of radiation workers to work in the dental hospital as increasing interest in exposure dose of the dental hospital recently accordingly, study aim to minimize radiation exposure by making a follow-up study of individual exposure doses of radiation workers, analyzing the status on individual radiation exposure management, prediction the radiation disability risk levels by radiation, and alerting the workers to the danger of radiation exposure. Especially given the changes in the dental hospital radiation safety awareness conducted the study in order to minimize radiation exposure. This study performed analyses by a comparison between general and dental hospital, comparing each occupation, with the 116,220 exposure dose data by quarter and year of 5,811 subjects at general and dental hospital across South Korea from January 1, 2008 through December 31, 2012. The following are the results obtained by analyzing average values year and quarter. In term of hospital, average doses were significantly higher in general hospitals than detal ones. In terms of job, average doses were higher in radiological technologists the other workers. Especially, they showed statistically significant differences between radiological technologists than dentists. The above-mentioned results indicate that radiation workers were exposed to radiation for the past 5 years to the extent not exceeding the dose limit (maximum 50 mSv y -1 ). The limitation of this study is that radiation workers before 2008 were excluded from the study. Objective evaluation standards did not apply to the work circumstance or condition of each hospital. Therefore, it is deemed necessary to work out analysis criteria that will be used as objective evaluation standard. It will be necessary to study radiation exposure in more precise ways on the basis of objective analysis standard in the future. Should try to minimize the radiation individual dose of

A comparative analysis of exposure doses between the radiation workers in dental and general hospital

Energy Technology Data Exchange (ETDEWEB)

Yang, Nam Hee; Chung, Woon Kwan; Dong, Kyung Rae; Ju, Yong Jin; Song, Ha Jin [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of); Choi, Eun Jin [Dept. of Public Health and Medicine, Dongshin University, Naju (Korea, Republic of)

2015-02-15

Research and investigation is required for the exposure dose of radiation workers to work in the dental hospital as increasing interest in exposure dose of the dental hospital recently accordingly, study aim to minimize radiation exposure by making a follow-up study of individual exposure doses of radiation workers, analyzing the status on individual radiation exposure management, prediction the radiation disability risk levels by radiation, and alerting the workers to the danger of radiation exposure. Especially given the changes in the dental hospital radiation safety awareness conducted the study in order to minimize radiation exposure. This study performed analyses by a comparison between general and dental hospital, comparing each occupation, with the 116,220 exposure dose data by quarter and year of 5,811 subjects at general and dental hospital across South Korea from January 1, 2008 through December 31, 2012. The following are the results obtained by analyzing average values year and quarter. In term of hospital, average doses were significantly higher in general hospitals than detal ones. In terms of job, average doses were higher in radiological technologists the other workers. Especially, they showed statistically significant differences between radiological technologists than dentists. The above-mentioned results indicate that radiation workers were exposed to radiation for the past 5 years to the extent not exceeding the dose limit (maximum 50 mSv y{sup -1}). The limitation of this study is that radiation workers before 2008 were excluded from the study. Objective evaluation standards did not apply to the work circumstance or condition of each hospital. Therefore, it is deemed necessary to work out analysis criteria that will be used as objective evaluation standard. It will be necessary to study radiation exposure in more precise ways on the basis of objective analysis standard in the future. Should try to minimize the radiation individual dose of

Monitoring and radiation dose estimation for internal contamination of occupational workers

Energy Technology Data Exchange (ETDEWEB)

Kol, R; Laichter, Y [Israel Atomic Energy Commission, Beersheba (Israel). Nuclear Research Center-Negev

1996-12-01

The assessment of interval radiation doses due to intake of radionuclides differs totally from external dosimetry. External dosimetry is relatively straight forward: Workers are equipped with appropriate dosimeters that give the dose upon direct reading. Internal dosimetry is actually an assessment of the dose based on results of personnel and environmental monitoring (authors).

Risks of circulatory diseases among Mayak PA workers with radiation doses estimated using the improved Mayak Worker Dosimetry System 2008

Energy Technology Data Exchange (ETDEWEB)

Moseeva, Maria B.; Azizova, Tamara V.; Grigoryeva, Evgenia S. [Southern Urals Biophysics Institute (SUBI), Ozyorsk, Chelyabinsk Region (Russian Federation); Haylock, Richard [Public Health of England, London (United Kingdom)

2014-05-15

The new Mayak Worker Dosimetry System 2008 (MWDS-2008) was published in 2013 and supersedes the Doses-2005 dosimetry system for Mayak Production Association (PA) workers. It provides revised external and internal dose estimates based on the updated occupational history data. Using MWDS-2008, a cohort of 18,856 workers first employed at one of the main Mayak PA plants during 1948-1972 and followed up to 2005 was identified. Incidence and mortality risks from ischemic heart disease (IHD) (International Classification of Diseases (ICD)-9 codes 410-414) and from cerebrovascular diseases (CVD) (ICD-9 codes 430-438) were examined in this cohort and compared with previously published risk estimates in the same cohort based on the Doses-2005 dosimetry system. Significant associations were observed between doses from external gamma-rays and IHD and CVD incidence and also between internal doses from alpha-radiation and IHD mortality and CVD incidence. The estimates of excess relative risk (ERR)/Gy were consistent with those estimates from the previous studies based on Doses-2005 system apart from the relationship between CVD incidence and internal liver dose where the ERR/Gy based on MWDS-2008 was just over three times higher than the corresponding estimate based on Doses-2005 system. Adjustment for smoking status did not show any effect on the estimates of risk from internal alpha-particle exposure. (orig.)

Potential Indoor Worker Exposure From Handling Area Leakage: Dose Calculation Methodology and Example Consequence Analysis

International Nuclear Information System (INIS)

Nes, Razvan; Benke, Roland R.

2008-01-01

The U.S. Department of Energy (DOE) is currently considering design options for preclosure facilities in a license application for a geologic repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. The Center for Nuclear Waste Regulatory Analyses (CNWRA) developed the PCSA Tool Version 3.0.0 software for the U.S. Nuclear Regulatory Commission (NRC) to aid in the regulatory review of a potential DOE license application. The objective of this paper is to demonstrate PCSA Tool modeling capabilities (i.e., a generic two-compartment, mass-balance model) for estimating radionuclide concentrations in air and radiological dose consequences to indoor workers in a control room from potential leakage of radioactively contaminated air from an adjacent handling area. The presented model computes internal and external worker doses from inhalation and submersion in a finite cloud of contaminated air in the control room and augments previous capabilities for assessing indoor worker dose. As a complement to the example event sequence frequency analysis in the companion paper, example consequence calculations are presented in this paper for the postulated event sequence. In conclusion: this paper presents a model for estimating radiological doses to indoor workers for the leakage of airborne radioactive material from handling areas. Sensitivity of model results to changes in various input parameters was investigated via illustrative example calculations. Indoor worker dose estimates were strongly dependent on the duration of worker exposure and the handling-area leakage flow rate. In contrast, doses were not very sensitive to handling-area exhaust ventilation flow rates. For the presented example, inhalation was the dominant radiological dose pathway. The two companion papers demonstrate independent analysis capabilities of the regulator for performing confirmatory calculations of frequency and consequence, which assist the assessment of worker

Planning of occupational dose reduction at BWR power plant by past dose record analysis combined with on-site workers' idea analysis

International Nuclear Information System (INIS)

Konno, T.; Taira, J.; Hayashida, T.; Suzuki, A.; Hayashi, K.; Kato, S.; Ishikawa, T.; Konno, T.; Hayashi, K.

2011-01-01

In order to establish a plan for occupational dose reduction at operating plants, outage inspection works that involve high-dose exposure were selected and a determination of the major causes of high-dose exposure made by plant-by-plant comparison of doses received during inspection works. The comparison was made to investigate the relationship between exposure and the volume of objects to be inspected, working time and man-hour of each work process and ambient dose rates at work areas. In parallel with this, an analysis has also been carried out on 400 data items in a questionnaire survey conducted on relevant individuals, including foremen, radiation safety personnel, on-site workers and plant designers regarding ideas for dose reduction methods. With combination of these two analyses, matters that require improvement will be highlighted, then modification of equipment or revision of work procedures necessary for occupational dose reduction will be planned by plant designers through review. (authors)

Low-Dose Radiation Cataract and Genetic Determinants of Radiosensitivity

Energy Technology Data Exchange (ETDEWEB)

Kleiman, Norman Jay [Columbia University

2013-11-30

The lens of the eye is one of the most radiosensitive tissues in the body. Ocular ionizing radiation exposure results in characteristic, dose related, progressive lens changes leading to cataract formation. While initial, early stages of lens opacification may not cause visual disability, the severity of such changes progressively increases with dose until vision is impaired and cataract extraction surgery may be required. Because of the transparency of the eye, radiation induced lens changes can easily be followed non-invasively over time. Thus, the lens provides a unique model system in which to study the effects of low dose ionizing radiation exposure in a complex, highly organized tissue. Despite this observation, considerable uncertainties remain surrounding the relationship between dose and risk of developing radiation cataract. For example, a growing number of human epidemiological findings suggest significant risk among various groups of occupationally and accidentally exposed individuals and confidence intervals that include zero dose. Nevertheless, questions remain concerning the relationship between lens opacities, visual disability, clinical cataract, threshold dose and/or the role of genetics in determining radiosensitivity. Experimentally, the response of the rodent eye to radiation is quite similar to that in humans and thus animal studies are well suited to examine the relationship between radiation exposure, genetic determinants of radiosensitivity and cataractogenesis. The current work has expanded our knowledge of the low-dose effects of X-irradiation or high-LET heavy ion exposure on timing and progression of radiation cataract and has provided new information on the genetic, molecular, biochemical and cell biological features which contribute to this pathology. Furthermore, findings have indicated that single and/or multiple haploinsufficiency for various genes involved in DNA repair and cell cycle checkpoint control, such as Atm, Brca1 or Rad9

Doses to railroad workers from shipments of radioactive materials

International Nuclear Information System (INIS)

Fields, D.E.; Cottrell, W.D.

1988-01-01

Fissile and high-level radioactive wastes are currently transported over long distances by truck and by rail transportation systems. The primary form of fissile material is spent reactor fuel. Transportation operations within DOE are controlled through the Transportation Operations and Management System. DOE projected increases in the rate of shipments have generated concern by railroad companies that railroad workers may be exposed to levels of radiation sufficiently high that a radiation protection program may need to be implemented. To address railroad company concerns, the Health and Safety Research Division at Oak Ridge National Laboratory has estimated doses to railroad workers for two exposure scenarios that were constructed using worker activity data obtained from CSX Transportation for crew and maintenance workers. This characterization of railroad worker activity patterns includes a quantitative evaluation of the duration and rate of exposure. These duration and exposure rate values were evaluated using each of three exposure rate vs. distance models to generate exposure estimates. 14 refs., 1 tab

Dose received by occupationally exposed workers at a nuclear medicine department

Science.gov (United States)

Ávila, O.; Sánchez-Uribe, N. A.; Rodríguez-Laguna, A.; Medina, L. A.; Estrada, E.; Buenfil, A. E.; Brandan, M. E.

2012-10-01

Personal Dose Equivalent (PDE) values were determined for occupational exposed workers (OEW) at the Nuclear Medicine Department (NMD) of "Instituto Nacional de Cancerología" (INCan), Mexico, using TLD-100 thermoluminescent dosemeters. OEW at NMD, INCan make use of radiopharmaceuticals for diagnosis and treatment of diseases. Radionuclides associated to a pharmaceutical compound used at this Department are 131I, 18F, 68Ga, 99mTc, 111In and 11C with main gamma emission energies between 140 and 511 keV. Dosemeter calibration was performed at the metrology department of "Instituto Nacional de Investigaciones Nucleares" (ININ), Mexico. Every occupational worker used dark containers with three dosimeters which were replaced monthly for a total of 5 periods. Additionally, control dosemeters were also placed at a site free of radioactive sources in order to determine the background radiation. Results were adjusted to find PDE/day and estimating annual PDE values in the range between 2 mSv (background) and 9 mSv. The mean annual value is 3.51 mSv and the standard deviation SD is 0.78 mSv. Four of the 16 OEW received annual doses higher than the average +1 SD (4.29 mSv). Results depend on OEW daily activities and were consistent for each OEW for the 5 studied periods as well as with PDE values reported by the firm that performs the monthly service. All obtained values are well within the established annual OEW dose limit stated in the "Reglamento General de Seguridad Radiológica", México (50 mSv), as well as within the lower limit recommended by the "International Commission on Radiation Protection" (ICRP), report no.60 (20 mSv). These results verify the adequate compliance of the NMD at INCan, Mexico with the norms given by the national regulatory commission.

Determination of effective dose for workers hemodynamics service using double dosimetry; Determinacion de la dosis efectiva para los trabajadores del servicio de hemodinamica usando doble dosimetria

Energy Technology Data Exchange (ETDEWEB)

Ruiz Lopez, M. A.; Lobato Munoz, M.; Jodar Lopez, C. A.; Ramirez Ros, J. C.; Jerez Sainz, M. I.; Pamos Urena, M.; Carrasco Rodriguez, J. L.

2013-07-01

The use of an additional dosimeter at the level of the neck above the lead apron we can provide an indication of the dose in the head (the Crystal dose). In addition, it is possible to combine the two readings of the dosimeter to provide an improved estimate of the effective dose. In the hemodynamics service of our Hospital we have maintained a worker for 3 years with the double dosimetry read monthly. With the readings from these dosimeters will do following algorithms, several estimates of the effective dose to see if, with working conditions that occur in this service, it would be necessary to extend this practice to the rest of the workers to get a better estimation of effective dose. (Author)

Implementation of ICRP-60 recommendations on dose limits to radiation workers in India

International Nuclear Information System (INIS)

Parthasarathy, K.S.

2000-01-01

The handling of radioactive material and radiation generating plants in India is regulated by the Atomic Energy Act, 1962 and rules issued under the Act. The Atomic Energy Regulatory Board enforces the rules. Currently, there are about 40,000 radiation workers in the country. Nearly half of them are employed in nuclear installations. During 1989, the Board considered the impact of restricting the maximum individual exposure to different values of dose limits. Through this analysis, the Board alerted all radiation users including persons responsible for radiation safety in nuclear facilities. When ICRP published ICRP-60, the Board issued directives to all radiation installations reducing the dose limit to occupational workers in a phased manner (40 mSv for 1991, 35 mSv for 1992 and 30 mSv for 1993). To meet the recommendations of ICRP-60, AERB issued a directive for the five year block 1994-1998, restricting the cumulative effective dose constraint to one hundred milliSievert (100 mSv) for individual radiation workers. Also, the annual effective dose to individual workers in any calendar year during the five-year block was restricted to thirty milliSievert (30 mSv). The stipulations of AERB are thus more conservative than those of ICRP. There was near total compliance with the dose limits by radiation installations in the country. For instance, in 1989, the number of radiation workers in nuclear power plants, who exceeded the dose level of 20 mSv/year was 9% of the total. This declined gradually to 2.2% in 1993 and 0.3% in 1997. During 1998, only 9 out of 10,145 exceeded 20 mSv/year. This has been achieved by the concerted efforts of the management, health physics staff and radiation workers. The health physicists regulated the radiation doses to workers by issuing work permits when the workers are assigned any job in high radiation areas. Appropriate training programmes are also in place. The broad guidelines to regulate radiation exposures in nuclear facilities

Relationship between radiation dose and changes of blood cells in medical diagnostic X-ray workers in China

International Nuclear Information System (INIS)

Zhao Wenzheng

1984-01-01

The hematological changes of 2867 cases of medical X-ray workers and 1152 cases of non-X-ray medical workers were compared. It was shown that the total number of leukocytes, the numbers of neutrophils, lymphocytes and platelets were significantly lower in X-ray workers than those in controls. However, the percentages of monocytes, eosinophils, basophils and the concentration of hemoglobin were higher in the irradiated group. the difference between the two groups was statistically significant. The degree of changes in the number of blood cells was dose-dependent. A negative correlation could be found between the changes of leukocyte and neutrophil counts and cumulative dose (<250 mGy), annual dose (<15 mGy/a) and length of service of the X-ray workers; and a positive correlation existed between the percentages of basophils, eosinophils and monocytes, and the radiation dose. The abnormality rate of blood picture in the irradiated group was higher than that in the control group. Most X-ray workers with abnormal blood picture were distributed in low-dose group. The data also showed that radiation effect on male X-ray workers was greater than that on female workers. (Author)

Dose response effect of cement dust on respiratory muscles competence in cement mill workers.

Science.gov (United States)

Meo, Sultan A; Azeem, Muhammad A; Qureshi, Aijaz A; Ghori, G Moinudin; Al-Drees, Abdul Majeed; Feisal Subhan, Mirza Muhammad

2006-12-01

Electromyography (EMG) of respiratory muscles is a reliable method of assessing the ventilatory muscle function, but still its use has not been fully utilized to determine the occupational and environmental hazards on respiratory muscles. Therefore, EMG of intercostal muscles was performed to determine the dose response effect of cement dust on respiratory muscles competence. Matched cross-sectional study of EMG in 50 non-smoking cement mill workers with an age range of 20 - 60 years, who worked without the benefit of cement dust control ventilation or respiratory protective devices. EMG was performed by using surface electrodes and chart recorder. Significant reduction was observed in number of peaks (p competence and stratification of results shows a dose-effect of years of exposure in cement mill.

Assessment of eye lens doses for workers during interventional radiology procedures

International Nuclear Information System (INIS)

Urboniene, A.; Sadzeviciene, E.; Ziliukas, J.

2015-01-01

The assessment of eye lens doses for workers during interventional radiology (IR) procedures was performed using a new eye lens dosemeter. In parallel, the results of routine individual monitoring were analysed and compared with the results obtained from measurements with a new eye lens dosemeter. The eye lens doses were assessed using H p (3) measured at the level of the eyes and were compared with H p (10) measured with the whole-body dosemeter above the lead collar. The information about use of protective measures, the number of performed interventional procedures per month and their fluoroscopy time was also collected. The assessment of doses to the lens of the eye was done for 50 IR workers at 9 Lithuanian hospitals for the period of 2012-2013. If the use of lead glasses is not taken into account, the estimated maximum annual dose equivalent to the lens of the eye was 82 mSv. (authors)

Quantitative determination of circulating endothelial cells in persons with low dose radioactivity exposure

International Nuclear Information System (INIS)

Al-Massarani, Gh.; Najjar, F.

2013-04-01

The aim of this study was to determine the risk of occupational exposure to low doses of ionizing radiation on the endothelium detachment through the quantification of circulating endothelial cells (CEC) in the peripheral blood of 63 workers in the Atomic Energy Commission in Syria (AECS) using a Magnetic Immuno-separation technique (IMS) and compare the results with 28 healthy (controls) is not exposed during their careers for any type of ionizing radiation. Our study showed for the first time the significantly increasing in the circulating endothelial cells count (P <0.0001) when employees are exposed to low doses of radiation less than 50 mSv. This result with previous studies about the late effects of radiation, assuming the existence of impact late radiation exposure on the cohesion of the endothelium, despite the lack of correlation with radiation dose measured during the past four years of work in AECS (between 2006-2010). This is due to several reasons, including the small sample size and lack of commitment by some workers develop individual control films during some periods of their work. The prospective studies for such workers can allow us to know if the rise in the number of CEC will be considered an early indicator for the risk of a cardiovascular disease when workers exposed to low-doses of ionizing radiation( tens of millisievert) that up to date are considered harmless (author).

Risks for radiation workers

International Nuclear Information System (INIS)

Rotblat, J.

1978-01-01

The following topics are discussed: recommendations of the International Commission on Radiological Protection; methods for determining dose limits to workers; use of data from survivors of Hiroshima and Nagasaki for estimating risk factors; use of data from survivors of nuclear explosions in Marshall Islands, uranium miners, and patients exposed to diagnostic and therapeutic radiation; risk factors for radioinduced malignancies; evidence that risk factors for persons exposed to partial-body radiation and Japanese survivors are too low; greater resistance of A-bomb survivors to radiation; and radiation doses received by U.K. medical workers and by U.K. fuel reprocessing workers. It is suggested that the dose limit for radiation workers should be reduced by a factor of 5

Radiation Dose Contribution To The Worker Health Level At Serpong Area

International Nuclear Information System (INIS)

Yuwono, Indro

2000-01-01

Analysis of internal and external radiation doses received for radiation and non-radiation workers of P2TBDU have been done. In the period of 1997/1998 and 1998/1999 there were no significant increasing level of radiation doses received that was 0.55 mSv and highest received radiation dose was 2.66% from dose limit value. Increasing of healthy difference on the same period was 5.76%. Increasing of healthy difference no cause by increasing of radiation dose received but maybe the food consumption design

Studies of workers exposed to low doses of external radiation

International Nuclear Information System (INIS)

Gilbert, E.S.

1991-04-01

Currently, several epidemiologic studies of workers who have been exposed occupationally to low levels of radiation are being conducted, and include studies of workers in the United States, Great Britain, and Canada involved in the production of both defense materials and nuclear power. This paper focuses on studies that evaluate the possible adverse effects resulting from external exposure to radiation. The radiation risk estimates that have been used to establish radiation protection standards for workers and others have been obtained mainly from studies of persons exposed at high doses and dose rates. However, questions remain with regard to the extrapolation process that has been necessary for estimating low-level radiation risks. Occupational studies provide a direct assessment of risk based on data on persons exposed at the actual levels of interest. If current risk estimates are correct, these studies have very little chance of detecting risk, but can still be used to provide useful upper limits on risks. The studies are also adequate to detect serious underestimation of risks. 36 refs., 3 figs., 3 tabs

Radiation dose of workers originating from radon in the show Cave of Tapolca, Hungary

International Nuclear Information System (INIS)

Somlai, J.; Szeiler, G.; Szabo, P.; Kovacs, T.; Tokonami, S.; Ishikawa, T.; Sorimachi, A.; Yoshinaga, S.

2009-01-01

In the last few decades attention has been given to improve workplace conditions, primarily to reduce the different health risks. In the air that accumulates in underground workplaces radon may constitute one of the health risks. The radon concentration in the show cave in Tapolca is especially high in summer months, with the annual average in the year 2005 being 7227 Bq/m 3 , in 2006 8591 Bq/m 3 . The radon concentration was found to be independent on the location of the measurement. Its value was rather similar for working hours and for the total period. The hours spent in the cave by the workers depend on the number of visitors. The radiation dose, estimated on the basis of personal dosimeters, is significant for those working there especially, employed during the whole year. Taking into consideration the actual working hours and the equilibrium factor, F = 0.4, given in the literature, it approaches and even exceeds the dose limit of 20 mSv/year. With a well organized work schedule, as well as the employment of outside workers during the summer period, the dose limit of 20 mSv/year can probably be maintained. However, on the basis of recent measurements, the actual equilibrium factor was determined to be F 0.5, which in turn means a further 25% increase in the dose effect. (author)

Study of feasibility of detecting effects of low-dose radiation in shipyard workers. Final report, May 15-August 15, 1978

International Nuclear Information System (INIS)

Matanoski, G.M.

1982-12-01

There is very little information available on the chronic health effects from repeated low-level doses of radiation. This study examines the adequacy of determining radiation exposure doses in shipyard workers, the procedures used in the radiation control programs, and the feasibility of establishing an appropriate population of nuclear and non-nuclear shipyard workers for long-term studies of low-level radiation. The availability of records and the methods of population identification and of measurement of radiation dose were determined during initial visits to the yards. Personnel, industrial hygiene, radiation and medical records were examined for suitability, completeness and accuracy. It was necessary to assure that no possible errors or omissions in personnel and radiation records existed in order that the final data will have validity. Preliminary investigations on the methods of follow-up in the Portsmouth population and the time required for each procedure were also undertaken in order to have a better estimate of the total cost for a long term study

Assessment of dose to the expected overexposed radiation workers in Malaysia using dicentric technique from 2005 - 2006

International Nuclear Information System (INIS)

Noraisyah Mohd Yusof; Mohd Rodzi Ali; Noriah Jamal; Rehir Dahalan

2008-08-01

Malaysian Nuclear Agency is recognized by the Atomic Energy Licensing Board (AELB) as a National Biodosimetry Laboratory for performing the chromosome aberration tests in Malaysia. The test is to be done for radiation workers who received doses of more than the annual dose limit of 50 mSv or losses of film badge. This paper aims at presenting results of assessment of dose to the expected overexposed radiation workers in Malaysia using dicentric technique from year 2005 to 2006. Between that period of time, 20 blood samples (loss of film badge: 5 samples, overexposed: 13 samples and follow-up cases: 2 samples) were received from the AELB and the assessment of chromosome aberration were performed. The information on whole body exposure (WBE) was also received together with the samples for overexposed worker. We used the gold standard technique, which is the dicentric assay to analyze the blood samples. The technique is described in the IAEA Technical Report Series No. 405. The results were then analyzed and compared with the respective WBE for the overexposed worker. We found that no doses were observed for workers who loss their film badges and for follow-up cases. 30.8% of the overexposed workers show doses of more than 50 mSv. However, 69.2% shows doses lower than the annual limit. Variation of results may be due to delayed blood sampling from the workers. This technique is especially useful for immediate assessment of radiation exposure. (Author)

The Mayak Worker Dosimetry System (MWDS-2013): implementation of the dose calculations

International Nuclear Information System (INIS)

Zhdanov, A.; Vostrotin, V.; Efimov, A.; Birchall, A.; Puncher, M.

2017-01-01

The calculation of internal doses for the Mayak Worker Dosimetry System (MWDS-2013) involved extensive computational resources due to the complexity and sheer number of calculations required. The required output consisted of a set of 1000 hyper-realizations: each hyper-realization consists of a set (1 for each worker) of probability distributions of organ doses. This report describes the hardware components and computational approaches required to make the calculation tractable. Together with the software, this system is referred to here as the 'PANDORA system'. It is based on a commercial SQL server database in a series of six work stations. A complete run of the entire Mayak worker cohort entailed a huge amount of calculations in PANDORA and due to the relatively slow speed of writing the data into the SQL server, each run took about 47 days. Quality control was monitored by comparing doses calculated in PANDORA with those in a specially modified version of the commercial software 'IMBA Professional Plus'. Suggestions are also made for increasing calculation and storage efficiency for future dosimetry calculations using PANDORA. (authors)

Radioactivity concentration variation with depth and assessment of workers' doses in selected mining sites

Directory of Open Access Journals (Sweden)

C.U. Nwankwo

2015-04-01

Full Text Available Mining workers are exposed to radiation in the process of extracting minerals from the earth crust. In this research, activity concentration of the radionuclides in samples collected at different depths in Komu (0–220 ft and Olode (0–30 ft mining sites, Oyo State, Nigeria and the associated workers' radiological risks were assessed. Gemstones from these sites are mined for local and international markets. The radionuclide contents of the samples were determined using Gamma spectroscopy technique. At Komu, 238U and 232Th concentrations, with few exceptions, increased with depth while that of 40K had no defined pattern. At Olode site, 238U and 232Th concentrations decreased with depth while that of 40K was almost constant. Internal hazard indices at Komu in some cases indicated an unacceptable level of risk to workers. Workers' doses would have been underestimated by between 12 and 55% if the activity concentrations of samples in the pit were not included in the calculation.

Integrated Worker Radiation Dose Assessment for the K Basins

International Nuclear Information System (INIS)

NELSON, J.V.

1999-01-01

This report documents an assessment of the radiation dose workers at the K Basins are expected to receive in the process of removing spent nuclear fuel from the storage basins. The K Basins (K East and K West) are located in the Hanford 100K Area

Health effects of low doses at low dose rates: dose-response relationship modeling in a cohort of workers of the nuclear industry; Effets sanitaires des faibles doses a faibles debits de dose: modelisation de la relation dose-reponse dans une cohorte de travailleurs du nucleaire

Energy Technology Data Exchange (ETDEWEB)

Metz-Flamant, Camille

2011-09-19

The aim of this thesis is to contribute to a better understanding of the health effects of chronic external low doses of ionising radiation. This work is based on the French cohort of CEA-AREVA NC nuclear workers. The mains stages of this thesis were (1) conducting a review of epidemiological studies on nuclear workers, (2) completing the database and performing a descriptive analysis of the cohort, (3) quantifying risk by different statistical methods and (4) modelling the exposure-time-risk relationship. The cohort includes monitored workers employed more than one year between 1950 and 1994 at CEA or AREVA NC companies. Individual annual external exposure, history of work, vital status and causes of death were reconstructed for each worker. Standardized mortality ratios using French national mortality rates as external reference were computed. Exposure-risk analysis was conducted in the cohort using the linear excess relative risk model, based on both Poisson regression and Cox model. Time dependent modifying factors were investigated by adding an interaction term in the model or by using exposure time windows. The cohort includes 36, 769 workers, followed-up until age 60 in average. During the 1968- 2004 period, 5, 443 deaths, 2, 213 cancers, 62 leukemia and 1, 314 cardiovascular diseases were recorded. Among the 57% exposed workers, the mean cumulative dose was 21.5 milli-sieverts (mSv). A strong Healthy Worker Effect is observed in the cohort. Significant elevated risks of pleura cancer and melanoma deaths were observed in the cohort but not associated with dose. No significant association was observed with solid cancers, lung cancer and cardiovascular diseases. A significant dose-response relationship was observed for leukemia excluding chronic lymphatic leukemia, mainly for doses received less than 15 years before and for yearly dose rates higher than 10 mSv. This PhD work contributes to the evaluation of risks associated to chronic external radiation

Radiation dose registration and epidemiological study for workers of nuclear institutions in Japan

International Nuclear Information System (INIS)

Kumatori, T.

1992-01-01

The first nuclear reactor was operated in 1957 at Tokai-mura in Japan. Since then radiation dose of workers has been controlled by nuclear institutions according to the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. However, many nuclear power plants and other nuclear facilities were built, resulting in the remarkable increase of workers in controlled areas. Further, periodical inspection and repair work at nuclear facilities were carried out by employees of subcontractors, who were engaged in such work at many different facilities, so that it was getting more and more difficult to obtain accurate information of radiation dose on these workers. In order to meet this situation, the open-quotes Radiation Dose Registration Center for Workersclose quotes (RADREC) was established in November 1977 within the open-quotes Radiation Effects Associationclose quotes (REA), which was founded in September 1960 for the purpose of supporting the research on radiation effects and radiation protection. In January 1978, RADREC was designated by the Government as an organization to preserve the records on exposure of radiation workers, which was linked up with the registration system

Relationship between mutation frequency of GPA locus and cumulative dose among medical diagnostic X-ray workers

International Nuclear Information System (INIS)

Wang Jixian; Yu Wenru; Li Benxiao; Fan Tiqiang; Li Zhen; Gao Zhiwei; Chen Zhenjun; Zhao Yongcheng

2000-01-01

Objective: To explore the feasibility of using GPA locus mutation assay as a bio-dosimeter for occupational exposure to ionizing radiation. Methods: An improved technique of GPA locus mutation assay was used in th study. The frequencies of mutant RBC in peripheral blood of 55 medical X-ray workers and 50 controls employed in different calendar-year periods were detected. The relationship between mutation frequencies (MFs) and period of entry, working years and cumulative doses were analyzed. Results: The MFs were significantly elevated among X-ray workers employed before 1970. This finding is similar to the result of cancer epidemiological study among medical X-ray workers , in which the cancer risk was significantly increased only X-ray workers employed before 1970. The MFs of GPA increased with increasing cumulative dose. The dose-effect relationship of Nφ MF with cumulative dose was closer than that of NN MF. Conclusion: There are many problems to be solved for using GPA MF assay as a bio-dosimeter such as individual variation, specificity and calibration curve of dose-effect relationship

Internal dose evaluation of workers involved in radioisotopes and radiopharmaceuticals handling for medical use

International Nuclear Information System (INIS)

Cesar, R.B.P.; Mesquita, C.H. de

1987-01-01

The internal dose levels of IPEN workers, involved in the production of radioisotopes and radiopharmaceuticals for medical use are surveyed. In this production, the workers were splited in six group: research and development, routine production, quality control, packaging, radiological protection and maintenance. The internal dose was evaluated according to the models described by ICRP-30, from the results obtained in the whole body counters monitoring. (C.G.C.) [pt

Average annual doses, lifetime doses and associated risk of cancer death for radiation workers in various fuel fabrication facilities in India

International Nuclear Information System (INIS)

Iyer, P.S.; Dhond, R.V.

1980-01-01

Lifetime doses based on average annual doses are estimated for radiation workers in various fuel fabrication facilities in India. For such cumulative doses, the risk of radiation-induced cancer death is computed. The methodology for arriving at these estimates and the assumptions made are discussed. Based on personnel monitoring records from 1966 to 1978, the average annual dose equivalent for radiation workers is estimated as 0.9 mSv (90 mrem), and the maximum risk of cancer death associated with this occupational dose as 1.35x10 -5 a -1 , as compared with the risk of death due to natural causes of 7x10 -4 a -1 and the risk of death due to background radiation alone of 1.5x10 -5 a -1 . (author)

Radiological assessment of worker doses during sludge mobilization and removal at the Melton Valley storage tanks

International Nuclear Information System (INIS)

Kerr, G.D.; Coleman, R.L.; Kocher, D.C.; Wynn, C.C.

1996-01-01

This report presents an assessment of potential radiation doses to workers during mobilization and removal of contaminated sludges from the Melton Valley Storage Tanks at Oak Ridge National Laboratory. The assessment is based on (1) measurements of radionuclide concentrations in sludge and supernatant liquid samples from the waste storage tanks, (2) measurements of gamma radiation levels in various areas that will be accessed by workers during normal activities, (3) calculations of gamma radiation levels for particular exposure situations, especially when the available measurements are not applicable, and (4) assumed scenarios for worker activities in radiation areas. Only doses from external exposure are estimated in this assessment. Doses from internal exposure are assumed to be controlled by containment of radioactive materials or respiratory protection of workers and are not estimated

Experimental ratio between the 'real' dose per organ and the calculated dose determined by means of the Embalse nuclear power plant's personal dosimeter

International Nuclear Information System (INIS)

Thomasz, E.; Salas, C.A.

1987-01-01

The specific purpose of the study was to determine the experimental ratio between the reading of dosimeters used by the personnel of the Embalse nuclear power plant and the 'real' dose absorbed by the worker in different organs. An anthropomorphic phantom ALDERSON internal and externally loaded with approximately 150 TLD crystals was used. This phantom was placed in five enclosures that were usually occupied by workers of the Embalse nuclear power plant. In this way, the average dose per organ and the effective equivalent dosis in each enclosure could be calculated and compared with the personal dosimeters placed over the thorax and the conversion factor rem/rem for each enclosure was determined. The average factor resulting from the five considered enclosures was 0.73 rem/rem. This means that the personal dosimeters over value the real dosis absorbed by the personnel of the Embalse nuclear power plant in approximately 37%. (Author)

Collective effective dose equivalent, population doses and risk estimates from occupational exposures in Japan

International Nuclear Information System (INIS)

Maruyama, Takashi; Nishizawa, Kanae; Kumamoto, Yoshikazu; Iwai, Kazuo; Mase, Naomichi.

1993-01-01

Collective dose equivalent and population dose from occupational exposures in Japan, 1988 were estimated on the basis of a nationwide survey. The survey was conducted on annual collective dose equivalents by sex, age group and type of radiation work for about 0.21 million workers except for the workers in nuclear power stations. The data on the workers in nuclear power stations were obtained from the official report of the Japan Nuclear Safety Commission. The total number of workers including nuclear power stations was estimated to be about 0.26 million. Radiation works were subdivided as follows: medical works including dental; non-atomic energy industry; research and education; atomic energy industry and nuclear power station. For the determination of effective dose equivalent and population dose, organ or tissue doses were measured with a phantom experiment. The resultant doses were compared with the doses previously calculated using a chord length technique and with data from ICRP publications. The annual collective effective dose equivalent were estimated to be about 21.94 person·Sv for medical workers, 7.73 person·Sv for industrial workers, 0.75 person·Sv for research and educational workers, 2.48 person·Sv for atomic energy industry and 84.4 person ·Sv for workers in nuclear power station. The population doses were calculated to be about 1.07 Sv for genetically significant dose, 0.89 Sv for leukemia significant dose and 0.42 Sv for malignant significant dose. The population risks were estimated using these population doses. (author)

Methods of assessment of individual and collective doses to transport workers and members of the public during the transport of radioactive material

International Nuclear Information System (INIS)

Vohra, K.G.; Subrahmanian, G.; Nandakumar, A.N.; Kher, R.K.; Iyer, S.R.K.

1986-01-01

Transport workers handling radioactive cargoes are generally exposed to the highest dose rates of any population group. Methods of assessment of dose received by transport workers are studied to arrive at a useful method. An empirical model based on a detailed work study of individuals handling radioactive cargoes and the exposure rates at various distances from specific individual packages is developed. The personnel doses thus calculated compared reasonably well with the doses recorded on personnel monitoring badges. The personnel doses were also evaluated with reference to the total transport index handled by the workers, yielding results consistent with those reported elsewhere by earlier researchers. For assessing the collective dose to the public due to urban transport of radioactive material, the space around the vehicle transporting cargo was divided into a number of cells of dimensions 1mx1m. The radiation level in each cell was measured and the pedestrian density along the route was obtained. Using the pedestrian occupancy in the cells and the measured radiation levels, the total dose to the public was assessed. A similar assessment was made with respect to the passengers in the neighbouring vehicles. The suggested method of calculation may aid determination of the route and time of transport and the preferable traffic configuration for the vehicle carrying the radioactive consignments for optimizing the dose to the urban public

Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Sadeghi, Nahid; Ahangari, Rohollah; Kasesaz, Yaser; Noori-kalkhoran, O. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research School

2017-11-15

In the case of Fukushima Daiichi nuclear power plant (FNP) accident, the radioactive material was released from reactor units 1-3 and transported to short and long distances due to the atmospheric pathways-motions. Power sources for monitoring posts were lost due to earthquake and tsunami. Based on air dose rates and other data measured by monitoring cars, the amount of radioactive material released to the atmosphere from the power station was obtained. The atmospheric dispersion and the transport model used in the RASCAL code, estimate the radionuclide concentrations downwind, both in the air and on the ground due to deposition. The calculated concentrations are then used to estimate the projected doses for workers in vicinity of the accident area in the first minutes of accident time. For dose modeling, we assumed that each worker was 15 min in vicinity of FNP in accident situation, once without and once with protective clothes or respirator. According to Tokyo Electric Power Company (TEPCO) report six workers had received doses over 250 mSv (309 to 678 mSv) apparently due to inhaling Iodine-131 fume. In this paper the calculated dose results using RASCAL code shows that, if emergency workers who work in early phase of accident had not used protective equipment, for 15 min, inhalation doses from iodine in their thyroid gland up to 12 March afternoon would have been 520 mSv. A comparison between calculation results and TEPCO report shows that dose calculated virtually is nearly equal to TEPCO measurement results.

Change of annual collective dose equivalent of radiation workers at KURRI

International Nuclear Information System (INIS)

Okamoto, Kenichi

1994-01-01

The change of exposure dose equivalent of radiation workers at KURRI (Kyoto University Research Reactor Institute) in the past 30 years is reported together with the operational accomplishments. The reactor achieved criticality on June 24, 1964 and reached the normal power of 1000 kW on August 17 of the same year, and the normal power was elevated to 5000 kW on July 16, 1968 until today. The change of the annual effective dose equivalent, the collective dose equivalent, the average annual dose equivalent and the maximum dose equivalent are indicated in the table and the figure. The chronological table on the activities of the reactor is added. (T.H.)

Somatic cell genetics of uranium miners and plutonium workers. A biological dose-response indicator

International Nuclear Information System (INIS)

Brandom, W.F.; Bloom, A.D.; Bistline, R.W.; Saccomanno, G.

1978-01-01

Two populations of underground uranium miners and plutonium workers work in the state of Colorado, United States of America. We have explored the prevalence of structural chromosome aberrations in peripheral blood lymphocytes as a possible biological indicator of absorbed radiation late-effects in these populations. The uranium miners are divided into four exposure groups expressed in Working Level Months (WLM), the plutonium workers into six groups with estimated 239 Pu burdens expressed in nCi. Comparison of chromosome aberration frequency data between controls, miners, and plutonium workers demonstrate: (1) a cytogenetic response to occupational ionizing radiation at low estimated doses; and (2) an increasing monotonic dose-response in the prevalence of complex (all exchange) or total aberrations in all exposure groups in these populations. We also compared trends in the prevalence of aberrations per exposure unit (WLM and nCi) in each exposure subgroup for each population. In the uranium miners, the effects per WLM seem to decrease monotonically with increasing dose, whereas in the Pu workers the change per nCi appears abrupt, with all exposure groups over 1.3 nCi (minimum detectable level) having essentially similar rates. The calculations of aberrations per respective current maximum permissible dose (120 WLM and 40 nCi) for the two populations yield 4.8 X 10 -2 /100 cells for uranium miners and 90.6 X 10 -2 /100 cells for Pu workers. Factors which may have influenced this apparent 20-fold increase in the effectiveness of plutonium in the production of complex aberrations (9-fold increase in total aberrations) are discussed. (author)

Determination of the Radiation Cancer Risk for Workers in Some Factories of Building Materials

International Nuclear Information System (INIS)

Madbouly, A.M.; Ibrahim, M.S.E.; Diab, A.M.

2012-01-01

The main aim of this work is to estimate the concentrations of natural radionuclides: 228 U-series, 232 Th-series and 40 k in raw materials of ceramic (zirconium silicate and glaze sample), ceramic tiles, tile, lime stone, granite, marble, gypsum and cement, in order to determine the dose received and health risk of the workers in building materials industries, the specific activities of those radionuclides, in all samples collected were measured. High resolution γ-ray spectroscopy measurements were done using hyper pure germanium (Hp Ge) detector. The measured activity concentrations for these radionuclides were compared with the data of other countries. As a measure of radiation hazard to the workers, the radium equivalent activities, the external hazard index (H e x), internal hazard index (H i n) representative level index (Iγ) and total annual effective dose associated with the radionuclides were estimated. The calculated total annual effective dose and the activity concentration index of all types of building materials were -I and 1 mSv y -I , respectively

Survey of radiation doses and health effects in medical diagnostic X-ray workers in China

International Nuclear Information System (INIS)

Wang Jixian; Zhang Liangan; Liu Jinzhong; Zhang Jingyuan

1984-01-01

The results of a nationwide survey of radiation doses and health effects in 26983 medical diagnostic X-ray workers in 28 provinces of China were reported. The control group was composed of 25785 non-X-ray medical workers in the same hospitals where the investigated X-ray workers worked. Of the radiological workers surveyed 75.3% received cumulative radiation doses below 50 mGy, only 2.7% received doses greater than 500 mGy, the average cumulative dose being 45.0 mGy. The average length of service was 11 years. The main radiation effects relating to radiation doses were the increase of frequencies of both chromosomal aberrations and micronuclei in peripheral blood lymphocytes, which were 0.362% and 0.0358% in the irradiated group, and 0.122% and 0.0138% in the control group, respectively. The incidence and mortality rate of leukemias increased significantly in the irradiated group. The incidence and standardized incidence of leukemias were 9.61 . 10 -5 and 9.67 . 10 -5 in the irradiated group and 2.74 . 10 -5 and 2.77 . 10 -5 in the control group. The leukemia mortality rates in the two groups were 8.60 . 10 -5 and 1.24 . 10 -5 respectively, and the standardized mortality rates were 8.60 . 10 -5 and 1.27 . 10 -5 respectively. (Author)

Chronic low dose radiation exposure and oxidative stress in radiation workers

International Nuclear Information System (INIS)

Ali, S.S.; Bhatt, M.B.; Kulkarni, MM.; Rajan, R.; Singh, B.B.; Venkataraman, G.

1996-01-01

Free radicals have been implicated in the pathogenesis of several human diseases. In this study free radical stress due to low dose chronic radiation exposures of radiation workers was examined as a possible atherogenic risk factor. Data on lipid profiles, lipid peroxidation and reduced glutathione content in blood indicated an absence of correlation with radiation doses up to 125 mSv. (author). 13 refs., 1 fig

Job-related mortality risks of Hanford workers and their relation to cancer effects of measured doses of external radiation

International Nuclear Information System (INIS)

Kneale, G.W.; Mancuso, T.F.; Stewart, A.M.

1983-01-01

If we exclude all persons who were classified as clerical workers we find that over 40% of the Hanford workers had either professional or technical qualifications (professional workers). The ratio of professional to manual workers was equally high for safe and dangerous occupations but during the period 1944-77 professional workers who were doing the most dangerous work had too many deaths by comparison with other persons with similar qualifications, and manual workers doing equally dangerous work had too few deaths by comparison with other manual workers. In practice, this means that in any analysis of dose-related cancer risks of Hanford workers it is essential to control for job-related mortality risks as well as all the usual factors such as sex, dates of birth and hire and duration of employment. The results of including all these factors in a cohort analysis of Hanford data by the method of regression models in life tables are described and also the reasons why it was concluded that the risk per unit dose is increased at low dose levels (i.e. the dose-response curve is curvilinear downwards). (author)

Monitoring and dose recording for the individual

International Nuclear Information System (INIS)

1988-01-01

This document specifies the conditions under which monitoring of individuals is required. For workers identified as Atomic Radiation Workers, determination of dose or exposure must be made. In circumstances where personal monitoring techniques are impractical, doses and exposures may be estimated by non-personal monitoring techniques. For workers not identified as Atomic Radiation Workers, licensees must be able to demonstrate that there is no reasonable potential for accumulating radiation doses or exposures in excess of regulatory limits. (L.L.)

Comparison between the chest dose and the neck dose of workers with protective aprons at PNC plutonium fuel fabrication facilities

Energy Technology Data Exchange (ETDEWEB)

Tsujimura, Norio; Momose, Takumaro; Shinohara, Kunihiko [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

1996-06-01

The dose equivalents recorded by a chest dosemeter under the protective apron and a neck dosemeter above the apron, worn by workers in the fabrication process of MOX fuels at PNC Tokai works, are compared. The ratio of the chest and neck dose equivalent is from 3 to 4. The effective dose equivalent calculated from a weighted combination of the dosemeter readings is about 2 times of the dose under protective aprons. (author)

Comparison between the chest dose and the neck dose of workers with protective aprons at PNC plutonium fuel fabrication facilities

International Nuclear Information System (INIS)

Tsujimura, Norio; Momose, Takumaro; Shinohara, Kunihiko

1996-01-01

The dose equivalents recorded by a chest dosemeter under the protective apron and a neck dosemeter above the apron, worn by workers in the fabrication process of MOX fuels at PNC Tokai works, are compared. The ratio of the chest and neck dose equivalent is from 3 to 4. The effective dose equivalent calculated from a weighted combination of the dosemeter readings is about 2 times of the dose under protective aprons. (author)

A method, using ICRP 26 weighting factors, to determine effective dose equivalent due to nonuniform external exposures

International Nuclear Information System (INIS)

Dyer, S.G.

1993-01-01

Westinghouse Savannah River Company (WSRC) has recently implemented a methodology and supporting procedures to calculate effective dose equivalent for external exposures. The calculations are based on ICRP 26 methodology and are used to evaluate exposures when multibadging is used. The methodology is based upon the concept of open-quotes whole bodyclose quotes compartmentalization (i.e., the whole body is separated into seven specific regions of radiological concern and weighted accordingly). The highest dose measured in each compartment is used to determine the weighted dose to that compartment. Benefits of determining effective dose equivalent are compliance with DOE Orders, more accurate dose assessments, and the opportunity for improved worker protection through new ALARA opportunities

Dose reconstruction for workers of Mayak and for the Techa riverside residents

International Nuclear Information System (INIS)

Wieser, A.; Aragno, D.; Baiankine, S.

2000-01-01

The main objectives of the project were: (a) to contribute to the improvement of the dose assessment for individuals of the cohorts of workers of Mayak and Techa riverside residents which are currently burdened by large uncertainties, (b) to test the capabilities of several methods of dose reconstruction by their applying to the same members of the two cohorts for which independent dose assessments existed and (c) to further develop the methods of dose reconstruction according to the experience gained during the exercise. The applied methods were retrospective dosimetry based on electron paramagnetic resonance (EPR) of teeth, chromosome painting (FISH) in lymphocytes and luminescence techniques applied to building materials. The independent dose estimates were based on film dosimetry for the workers of Mayak and for the Techa riverside residents on measurements of the contamination in the environment, of the external β radiation of teeth and of the Strontium whole body contents. The work in the project was carried out in close collaboration with the project 'Dose Reconstruction' in the nuclear fission safety (NFS) programme (contract FI4PCT950011d). The measurements and evaluations were tasks for which the work was shared by both projects. Most of the method development and FISH analysis was more located in the NFS project and has been described in the final report of that project. (orig.)

Worker doses and potential health effects resulting from the accident at the Fukushima nuclear power plant in 2011.

Science.gov (United States)

Etherington, George; Zhang, Wei; Harrison, John; Walsh, Linda

2014-11-01

The reliability of exposure scenarios used in the World Health Organization's Health Risk Assessment (HRA) for Fukushima workers was examined. HRA risk estimates for cancer incidence in these workers were then reviewed. The HRA constructed four exposure scenarios to estimate worker radiation doses; recent individual dosimetric data were used to assess their reliability. Risks of specified cancer types attributable to radiation exposure were estimated in the HRA by calculating Lifetime Attributable Risks (LAR) for each scenario, and comparisons of LAR are provided. The scenarios were confirmed as reliable for the purposes of the HRA. For the lowest dose scenario (Scenario 1: 69% of the workforce), the HRA found that any elevated cancer risk was insignificant. Significantly elevated cancer risks were, however, found for the three higher dose scenarios. For the highest dose scenario (Scenario 4: 13 workers), LAR values for thyroid cancer up to 3.5% were estimated, but a radiation-related increase in thyroid cancer incidence is unlikely to be observed because of the small number of workers. For the two intermediate dose scenarios, a small number of cancer cases may occur, but these are unlikely to be observed because the variability in baseline rates of cancer incidence is much larger than the predicted radiation-related incidence rates.

Long Term assessment of the dose registered by the Sanitary workers of a mutual

International Nuclear Information System (INIS)

Anies Escartin, J.; Perramon Llado, A.

2004-01-01

The analysis of a long time period of time (about 17 years) of the professional exposure to ionising radiation of the workers of an accidents Mutual, that has its own personal Dosimetry Service, allows to establish a relation between the showed global reduction of the registered doses of the people exposed and the circumstances and actions that did it possible. The fact to carry out a dosimetric control is an essential factor directed to accomplish the objective of holding the doses as low as achievable, joined with the fact of passing more strict law. Those factors that fixed a reduction of the doses inherited by the sanitary exposed workers whose relation are demonstrated in this study. The collective dose inherited by the bunch of people exposed is the parameter suitable to measure and assess the time history at medium and long term of the exposure conditions of the workers, and identify the more relevant characteristics of the risk by ionising radiation at workplace. The conclusion of the time history analysis of the quantity shows that the total collective dose for more than a thousand people group, are strongly affected by the doses corresponding to less than a 1,5 % of the users. The number of people that have a value dose higher that the average, and the high value of the dose in some periods because of their activity lead to changes of the value of the collective doses that can be higher than 100%. This great uncertainty in the measured value needs more than ten months of control to guarantee the lowering of doses received. The decreasing doses observed are strongly related with the reduction of this relative short number of cases with incidences in the doses registered. An important part of the work is related to identifying the incidences registered, noticing the evolution and checking the most suitable actions to lower it. (Author) 4 refs

Influence on dose coefficients for workers of the new metabolic models

International Nuclear Information System (INIS)

Gomez Parada, I.M.; Rojo, A.M.

1998-01-01

The International Commission on Radiological Protection (ICRP) has recently reviewed the biokinetic models used in the internal contamination dose assessment. ICRP has adopted a new model for the human respiratory tract and has updated, in ICRP Publications 56, 67 and 69, some of the biokinetic models of ICRP Publication 30. In this paper, the dose coefficients for some selected radionuclides issued in ICRP Publication 68 are compared with those obtained using the software LUPED (LUng Dose Evaluation Program). The former were calculated using the new systemic models, while the latter are based on the old metabolic models. The aim is to know to what extent the new models for systematic retention influence the dose coefficients for workers. (author) [es

Pocket total dose meter

International Nuclear Information System (INIS)

Brackenbush, L.W.; Endres, G.W.R.

1984-10-01

Laboratory measurements have demonstrated that it is possible to simultaneously measure absorbed dose and dose equivalent using a single tissue equivalent proportional counter. Small, pocket sized instruments are being developed to determine dose equivalent as the worker is exposed to mixed field radiation. This paper describes the electronic circuitry and computer algorithms used to determine dose equivalent in these devices

Health effects of low dose exposures to external ionizing radiation in the French cohort of nuclear workers CEA-AREVA-EDF - 5287

International Nuclear Information System (INIS)

Leuraud, K.; Fournier, L.; Samson, E.; Caer-Lorho, S.; Laurier, D.; Laroche, P.; Le Guen, B.

2015-01-01

Populations of nuclear workers are particularly relevant to study health effects of low dose and low dose-rate exposures to ionizing radiation. In France, a cohort of nuclear workers employed by CEA, AREVA NC, or EDF, and badge-monitored for radiation exposure, has been followed-up. Annual exposure to penetrating photons was reconstructed for each worker. Standardized mortality ratios were calculated using national mortality rates as the reference. Estimates of radiation dose-mortality associations were obtained using a linear excess relative risk (ERR) model. A total of 59,004 workers were followed-up between 1968 and 2004, for an average of 25 years. The mean cumulative photons dose was 16.1 mSv. At the end of the follow-up, workers were 56 years old and 6,310 workers had died. A strong healthy worker effect was observed. Positive but imprecise estimates of ERR/Sv were observed for all solid cancers and leukemia excluding chronic lymphocytic leukemia. A significant ERR/Sv was found for myeloid leukemia. This cohort study is the most informative ever conducted in France among nuclear workers. Results confirmed a healthy worker effect due to selection at hiring and health monitoring from occupational medicine. Observed dose-risk relationships were consistent with risks estimated in other studies, even if they remained associated to a large uncertainty. (authors)

Worker radiation doses in the United States at the dawn of the atomic era (1940--1960)

International Nuclear Information System (INIS)

Strom, D.J.; Smith, M.H.; Swinth, K.L.; Pettengill, H.J.

1994-06-01

Radiation doses to workers at the Manhattan Engineer District (MED) and US Atomic Energy Commission (AEC) sites due to external irradiation during 1940--1960 are reviewed. Categorized radiation dose data were available from AEC annual reports for some years. Annual individual radiation dose data for ten MED/AEC sites for all years were available from the US Department of Energy's (DOE) Comprehensive Epidemiologic Data Resource (CEDR). These data are combined to produce an estimate of external collective dose equivalent to 172,000 person-rems (1720 person-Sv) for 1940--1960. During this period there were 41 overexposures, 19 criticality incidents, and 3 deaths due to acute radiation syndrome among several hundred thousand workers

Estimation of Internal Radiation Dose to Nuclear Medicine Workers at Siriraj Hospital

International Nuclear Information System (INIS)

Asawarattanapakdee, J.; Sritongkul, N.; Chaudakshetrin, P.; Kanchanaphiboon, P.; Tuntawiroon, M.

2012-01-01

Every type of work performed in a nuclear medicine department will make a contribution to both external and internal exposure of the worker. The purpose of this study is to evaluate the potential risks of internal contamination to staff members during nuclear medicine practices and to conclude about the requirement of a routine internal monitoring. Following the method describes in the ICRP Publication 78 and the IAEA Safety Standard Series No. RS- G-1.2, in vivo thyroid bioassays using NaI(Tl) thyroid probe were performed to determine the intake estimates on 7 groups of nuclear medicine personnel working with I-131 and Tc-99m, based on working conditions and amount of radionuclides being handled. Frequency of measurements was between 7 and 14 days. These include (1) physicians and physicists, (2) radiochemists (3) technologists, (4) nurses and assistant nurses, (5) imaging room assistants, (6) hot lab workers and (7) hospital ward housekeepers/cleaners. Among all workers, the intake estimates of I-131 in the thyroid ranged from 0 to 76.7 kBq and of the technetium-99m from 0 to 35.4 MBq. The mean committed effective dose equivalent (CEDE) from both I-131 and Tc-99m were 0.63, 1.44 0.53, 0.57, 0.73, 0.98, and 1.36, mSv, for group 1 through group 7 respectively. However, the highest mean CEDE of 1.44 (max. 1.75) and 1.36 (max. 2.11) mSv observed in groups of radiochemists and hospital ward housekeepers were within the permissible level. Our results showed that CEDE for internal exposure in this study were less than investigate level of 5 mSv according to the ICRP Publication 78 and the IAEA Basic Safety Standards. However, the mean CEDE for radiochemists and hospital ward housekeepers were considered in exceed of the limits of recording level (1 mSv).The increasing use of I-131 and Tc-99m in nuclear medicine poses significant risks of internal exposure to the staff. This study suggests that a routine monitoring program for internal exposures should be implemented for

Do dose area product meter measurements reflect radiation doses ...

African Journals Online (AJOL)

Enrique

SA JOURNAL OF RADIOLOGY • August 2004. Abstract. This study determined the correlation between radiation doses absorbed by health care workers and dose area product meter (DAP) measurements at Universitas Hospital, Bloemfontein. The DAP is an instrument which accurately measures the radiation emitted from ...

Do dose area product meter measurements reflect radiation doses ...

African Journals Online (AJOL)

This study determined the correlation between radiation doses absorbed by health care workers and dose area product meter (DAP) measurements at Universitas Hospital, Bloemfontein. The DAP is an instrument which accurately measures the radiation emitted from the source. The study included the interventional ...

Dose limit for emergency workers. Application of Fukushima-Daiichi NPP accident and problems for the future

International Nuclear Information System (INIS)

Sugai, Kenji

2012-01-01

Described are details of management for workers' personal exposure dose, of problems raised and of their solutions taken under various complicated conditions of Fukushima Daiichi Nuclear Power Plant (NPP) Accident (Mar. 2011). As the entrance/exit (en/ex) for the NPP site with regular control were impossible due to the hydrogen explosion which expanded the control area to 20 km distance from the site, Japan Football Village (J-Village) localizing at the border and Important Anti-seismic Building in the site were defined to be the bases of en/ex and of their control, respectively. Flooded 5,000 alarm pocket dosimeters (APD) by tsunami were not usable and only 320 APD remained available. At the quite early stage of working at the site, one representative worker in a group had only one APD. Management of internal exposure was also difficult essentially because the power source of the whole body counter was unavailable. At an early emergent stage alone, workers with higher dose than the limit (100 mSv for emergency) were observed, but >90% of workers were exposed to <50 mSv (the limit for the radiation worker). Six male Tokyo Electric Power Company (TEPCO) personnel were exposed to 250 mSv (specially defined dose limit) or more with the maximum 678.80 mSv, in whom the internal exposure due to radioiodine largely attributed. They were examined for their health by the expert doctors in National Institute of Radiological Sciences, were found free of abnormality and were to be followed up thereafter. Out of 19 female TEPCO personnel, two had exceeded the dose limit 5 mSv/3 mo and other 2, the annual limit 1 mSv. They received the examination by the industrial doctor, were found free of abnormality, but were decided not to work at the site. Recently, about 5,000 APD have been purchased for personal usage and dose management is conducted by bar-coding of individual workers, and internal exposure is managed with 11 whole body counters by once a month measurement in J

Visualization of a dismantling environment for an evaluation of a worker's dose during the decommissioning of KRR-1 and 2

International Nuclear Information System (INIS)

Park, Hee Seong; Kim, Sung Kyun; Lee, Kune Woo; Jung, Chong Hun; Jin, Seong Il

2008-01-01

The purpose of this paper is to provide a basis for an optimization of a dismantling process of a research reactor and nuclear facility. An optimization of a dismantling process should be at the beginning of a study for an evaluation of the radioactivity inventory and the safety of the workers. Many countries have conducted an optimization to achieve a shortened dismantling schedule, a reduction of the amount of waste, and cut down on the decommissioning by using computer graphics such as animation, simulation, and virtual reality. In the present study, we propose methods for identifying the existence of radioactivity which is contained in the dismantled objects and for evaluating a worker's dose through a simulation. To evaluate a worker's external dose under a virtual dismantling environment generated by computer graphics, the shape of the thermal column horizontal door was created by 3D CAD and the radiation dose surrounding the door was calculated by using MCNP-4C. An animation that can demonstrate a dismantling procedure according to a dismantling scenario was produced. For matching the radiation dose, which was calculated by MCNP-4C with an area where workers are dismantling a door, a simulation module was developed which could show a worker's external dose in real-time. The result from the distribution of the radioactivity enables us to specify where the most contaminated part of the dismantling objects is. In the animation, a virtual worker demonstrated a dismantling activity procedure as a chosen scenario. In the simulation, a worker's exposure dose rate in real-time has been evaluated

The evaluation of radiation level and dose of workers in Guangzhou metro line 1

International Nuclear Information System (INIS)

Zhang Lin; Hu Canyun; Meng Xiaolian; He Zhan

2006-01-01

Objective: To find out the level of radiation and effective dose of workers in Guangzhou Metro line 1. Methods: In metro stations, external Gamma-ray exposure rates were obtained by FD-71A radiance measurer, 222 Rn and 220 Rn concentrations were obtained by using Rn-Tn solid state nuclear track detectors developed by The National Institute for Radiological Protection and Nuclear Safety, Chinese Centre for Disease Control. The annual Effective dose from Gamma, 222 Rn and 220 Rn were calculated. Results: The external Gamma-ray exposure average rate is 17.74 x 10 -8 Gy/h. The average concentration of 222 Rn is 59.8 Bq/m 3 . The average concentration of 220 Rn is 32.1 Bq/m 3 . The total annual effective dose from Gamma, 222 Rn and 220 Rn is 2.878 mSv/a. Conclusion: In the stations of Guangzhou in metro line 1, no more effective radiation dose to the workers has measured. (authors)

Socioeconomic Determinants of Physical Inactivity among Japanese Workers

OpenAIRE

Kumagai, Narimasa

2012-01-01

Background: Half of Japanese workers are physically inactive, but there are no studies on the relation between the leisure-time physical inactivity of Japanese workers and their socioeconomic status. The proportion of female workers who are physically inactive has been larger than that of male workers. Objectives: Using micro-data from nationwide surveys in Japan, this study explored the gender differences in socioeconomic determinants of leisure-time physical inactivity. Methods: We first es...

Verification by the FISH translocation assay of historic doses to Mayak workers from external gamma radiation

Energy Technology Data Exchange (ETDEWEB)

Sotnik, Natalia V.; Azizova, Tamara V. [Southern Urals Biophysics Institute (SUBI), Ozyorsk, Chelyabinsk Region (Russian Federation); Darroudi, Firouz [Leiden University Medical Center, Department of Toxicogenetics, Leiden (Netherlands); College of North Atlantic, Department of Health Science, Centre for Human Safety and Environmental Research, Doha (Qatar); Ainsbury, Elizabeth A.; Moquet, Jayne E.; Lloyd, David C.; Hone, Pat A.; Edwards, Alan A. [Public Health England, Chilton, Oxfordshire (United Kingdom); Fomina, Janna [Leiden University Medical Center, Department of Toxicogenetics, Leiden (Netherlands)

2015-11-15

The aim of this study was to apply the fluorescence in situ hybridization (FISH) translocation assay in combination with chromosome painting of peripheral blood lymphocytes for retrospective biological dosimetry of Mayak nuclear power plant workers exposed chronically to external gamma radiation. These data were compared with physical dose estimates based on monitoring with badge dosimeters throughout each person's working life. Chromosome translocation yields for 94 workers of the Mayak production association were measured in three laboratories: Southern Urals Biophysics Institute, Leiden University Medical Center and the former Health Protection Agency of the UK (hereinafter Public Health England). The results of the study demonstrated that the FISH-based translocation assay in workers with prolonged (chronic) occupational gamma-ray exposure was a reliable biological dosimeter even many years after radiation exposure. Cytogenetic estimates of red bone marrow doses from external gamma rays were reasonably consistent with dose measurements based on film badge readings successfully validated in dosimetry system ''Doses-2005'' by FISH, within the bounds of the associated uncertainties. (orig.)

Study of national registration systems for health records of radiation workers. National radiation dose registration system

International Nuclear Information System (INIS)

Nakagawa, Haruo; Kanda, Keiji

1999-01-01

A national radiation dose registration system is proposed in this paper. In Japan, only one radiation dose registration system is partly effective. It is applied for workers in nuclear power plants which are under control of regulatory laws for nuclear reactors. The total system was proposed previously by the Committee for Compensation Claims of Nuclear Accidents. The reason for the delay in establishing a registration system for all radiation workers is supposedly a lack of effort to adjust differences among items in radiation protection laws and the promotion of public acceptance to atomic power. Items about dose recordings, record keeping and dose-record reporting in all of the radiation regulatory laws are compared to each other, and items were extracted for revision. (author)

Development of site profiles for dose reconstruction used in worker compensation claims.

Science.gov (United States)

Kenoyer, Judson L; Scalsky, Edward D; Taulbee, Timothy D

2008-07-01

For the purpose of dose reconstruction, personal dosimeter data and measured intakes through bioassay analysis (i.e., in-vivo and in-vitro measurements) should be used whenever possible and given precedence over area monitoring data, survey data, or source term data. However, this is not always possible. A worker's exposure record may be incomplete or missing, or, based on directives and guidelines at the time, a worker may not have been monitored during his or her time of employment. In an effort to recognize, analyze, and incorporate all possible considerations of potential exposures, the National Institute for Occupational Safety and Health Radiation Dose Reconstruction Program developed "site profiles" for all of the major U.S. Department of Energy sites and Atomic Weapons Employer sites. Site profiles are technical documents that (1) provide a brief, general overview of the site; (2) identify the facilities on site with a brief description of the processes and radionuclides used in these processes; (3) contain detailed information on the historical detection limits for film, thermoluminescent dosimeter, and bioassay measurements that are used by the dose reconstructor to interpret a worker's available monitoring records; and (4) provide important supporting information for the dose reconstructor to use if the monitoring data are inadequate or unavailable. When a complete set of monitoring data for an individual is unavailable, it is the parameters in the site profile that are of the most use to the dose reconstructor. These parameters include facility monitoring data (by radionuclide, mechanism of intake, year of exposure, location within a facility); occupational medical x rays and techniques used; environmental measurements (by area on site, radiation type, energy range); minimum detectable activities of the types and kinds of instruments used to detect the different radionuclides; specific source terms (quantities of material and their molecular form

Rapid detection of chromosome rearrangement in medical diagnostic X-ray workers by using fluorescence in situ hybridization and study on dose estimation

International Nuclear Information System (INIS)

Wang Zhiquan; Sun Yuanming; Li Jin

1998-01-01

Objective: Biological doses were estimated for medical diagnostic X-ray workers. Methods: Chromosome rearrangements in X-ray workers were analysed by fluorescence in situ hybridization (FISH) with composite whole chromosome paintings number 4 and number 7. Results: The frequency of translocation in medical diagnostic X-ray workers was much higher than that in control group (P<0.01). The biological doses to individual X-ray workers were calculated by their translocation frequency. The translocation frequencies of both FISH and G-banding were in good agreement. Conclusion: The biological doses to X-ray workers are estimated by FISH first when their dosimetry records are not documented

Retrospective Dose Reconstruction for Medical Diagnostic X Ray Workers in China using Stable Chromosome Aberrations

International Nuclear Information System (INIS)

Wang, Q.; Liu, P.; Li, J.; Wang, Q.; Tang, S.; Sun, M.; Wang, L.; Aoyama, T.; Sugahara, T.

1998-01-01

The chromosome rearrangements in medical diagnostic X ray workers were analysed using the G-banding technique and evaluated collectively in accumulated doses. A total of 9102 metaphase spreads from 84 medical diagnostic X ray workers and 17 controls were scored. The results showed that: (1) the frequencies of translocation, stable chromosome aberration and total aberration in X ray workers were significantly higher than those of controls (P < 0.05 γ 0.005), unstable chromosome aberrations (including dicentric and acentric aberration) tended upwards; (2) the main aberration in stable aberrations was reciprocal translocation; (3) the stable aberration predominated strikingly in total aberrations. The medical diagnostic X ray workers were divided into three groups according to calendar year of entry. The data showed that the frequencies of translocation, stable aberration and total aberration increased with earlier year of entry, especially in two groups who started working before 1970. According to the equation recommended by Straume et al, linear coefficient (α) in the linear quadratic model provided by Fernandez's experiment, their collective accumulation doses calculated were 0.53, 0.26 and 0.06 Gy for calendar year of entry before 1960, 1960-1969, and after 1970, in X ray workers, respectively. (author)

Estimation of the effects of a lead vest on dose reduction for radiation workers using Monte Carlo calculations

International Nuclear Information System (INIS)

Young-khi, Lim; Byoung-il, Lee; Jeong-in, Kim

2008-01-01

Full text: In the field of medical diagnosis or treatments using radiations, lead vests or aprons are widely used to protect the patients or workers from unwanted irradiation. Also, in nuclear power plants, it is recommended that the workers should wear a lead vest to reduce the dose for working in high radiation area. Generally, personal dosimeters were used to estimate the doses of workers but these cannot give the absolute values. So, measured values should be modified by comparing the reference conditions with conversion factors. Many trials to estimate the doses of workers with lead shield using two or more dosimeters at different locations were done but these had limitations. Through this study the personal dose with/without a lead vest and the effectiveness were evaluated by Monte Carlo methods. A lead vest which had been used at several nuclear sites was modelled with MIRD-V and typical Korean voxel phantom using MCNP-5 transport code. Organ doses were calculated in AP, PA, RLAT, LLAT irradiation geometry for several parallel photon beams. Also irradiation experiments were carried out using real typical Korean phantom with the lead vest and the results were compared with those calculated by simulations. In most cases, the lead vest decreases the organ doses about 30%. For low energy, the lead vest is very effective to reduce the dose but it is not so good for high energy photon shielding. For thyroids, the doses to high energy photons increased by 5% on the contrary. This study may be applied to the better design of personal shielding and dose estimation procedures for practical use. (author)

Service worker dose reduction: whose job is it?

International Nuclear Information System (INIS)

Eaton, J.F.

1993-01-01

Nuclear utilities around the world are scrambling to change radiation protection programmes. In the US there are two reasons: Revised government regulatory requirements lowering radiation dose go into effect in January 1994 with an option for implementation in January 1993. The International Commission on Radiation Protection has recommended not allowing any person to receive greater than 10rem over a five year period. These changes create big challenges not only for the utilities but also for the service companies who receive the bulk of outage radiation exposure. Service companies should anticipate that customer administrative dose limits will be lowered significantly with a goal of 2rem/y or less. Improved worker efficiency, improved equipment reliability, better housekeeping and improved outage planning and management come from more effective field service training and ''as low as reasonably achievable'' ALARA programmes. Service companies should seriously consider expanding and improving these programmes. (Author)

Personal radiation monitoring and assessment of doses received by radiation workers (1996)

International Nuclear Information System (INIS)

Morris, N.D.

1996-12-01

Since late 1986, all persons monitored by the Australian Radiation Laboratory have been registered on a data base which maintains records of the doses received by each individual wearer. At present, the Service regularly monitors approximately 30,000 persons, which is roughly 90 percent of those monitored in Australia, and maintains dose histories of over 75,000 people. The skin dose for occupationally exposed workers can be measured by using one of the five types of monitor issued by the Service: Thermoluminescent Dosemeter (TLD monitor), Finger TLD 3, Neutron Monitor, Special TLD and Environmental monitor. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 5 figs

Estimation of radiation dose received by the radiation worker during 18F FDG injection process

International Nuclear Information System (INIS)

Jha, Ashish Kumar; Zade, Anand; Rangarajan, Venkatesh

2011-01-01

The radiation dosimetric literature concerning the medical and non-medical personnel working in nuclear medicine departments are limited, particularly radiation doses received by radiation worker in nuclear medicine department during positron emission tomography (PET) radiopharmaceutical injection process. This is of interest and concern for the personnel. To measure the radiation dose received by the staff involved in injection process of Fluorine-18 Fluorodeoxyglucose (FDG). The effective whole body doses to the radiation workers involved in injections of 1511 patients over a period of 10 weeks were evaluated using pocket dosimeter. Each patient was injected with 5 MBq/kg of 18 F FDG. The 18 F-FDG injection protocol followed in our department is as follows. The technologist dispenses the dose to be injected and records the pre-injection activity. The nursing staff members then secure an intravenous catheter. The nuclear medicine physicians/residents inject the dose on a rotation basis in accordance with ALARA principle. After the injection of the tracer, the nursing staff members flush the intravenous catheter. The person who injected the tracer then measures the post-injection residual dose in the syringe. The mean effective whole body doses per injection for the staff were the following: Nurses received 1.44 ± 0.22 μSv/injection (3.71 ± 0.48 nSv/MBq), for doctors the dose values were 2.44 ± 0.25 μSv/injection (6.29 ± 0.49 nSv/MBq) and for technologists the doses were 0.61 ± 0.10 μSv/injection (1.58 ± 0.21 nSv/MBq). It was seen that the mean effective whole body dose per injection of our positron emission tomography/computed tomography (PET/CT) staff who were involved in the 18 F-FDG injection process was maximum for doctors (54.34% differential doses), followed by nurses (32.02% differential doses) and technologist (13.64% differential doses). This study confirms that low levels of radiation dose are received by staff during 18 F-FDG injection and

Calculation methods for determining dose equivalent

International Nuclear Information System (INIS)

Endres, G.W.R.; Tanner, J.E.; Scherpelz, R.I.; Hadlock, D.E.

1987-11-01

A series of calculations of neutron fluence as a function of energy in an anthropomorphic phantom was performed to develop a system for determining effective dose equivalent for external radiation sources. Critical organ dose equivalents are calculated and effective dose equivalents are determined using ICRP-26 [1] methods. Quality factors based on both present definitions and ICRP-40 definitions are used in the analysis. The results of these calculations are presented and discussed. The effective dose equivalent determined using ICRP-26 methods is significantly smaller than the dose equivalent determined by traditional methods. No existing personnel dosimeter or health physics instrument can determine effective dose equivalent. At the present time, the conversion of dosimeter response to dose equivalent is based on calculations for maximal or ''cap'' values using homogeneous spherical or cylindrical phantoms. The evaluated dose equivalent is, therefore, a poor approximation of the effective dose equivalent as defined by ICRP Publication 26. 3 refs., 2 figs., 1 tab

Mortality from solid cancers other than lung, liver, and bone in relation to external dose among plutonium and non-plutonium workers in the Mayak Worker Cohort

Energy Technology Data Exchange (ETDEWEB)

Sokolnikov, Mikhail [Southern Urals Biophysics Institute, Ozyorsk (Russian Federation); Preston, Dale [Hirosoft International Corporation, Eureka, CA (United States); Stram, Daniel O. [University of Southern California, Keck School of Medicine, Los Angeles, CA (United States)

2017-03-15

Exposure to ionizing radiation has well-documented long-term effects on cancer rates and other health outcomes in humans. While in vitro experimental studies had demonstrated that the nature of some radiation effects depend on both total dose of the radiation and the dose rate (i.e., the pattern of dose distribution over time), the question of whether or not the carcinogenic effect of radiation exposure depends on the dose rate remains unanswered. Another issue of interest concerns whether or not concomitant exposure to external gamma rays and inhaled plutonium aerosols has any effect on the external exposure effects. The analyses of the present paper focus on the risk of solid cancers at sites other than lung, liver, and bone in Mayak workers. Recent findings are reviewed indicating that there is no evidence of plutonium dose response for these cancers in the Mayak worker cohort. Then the evidence for differences in the external dose effects among workers with and without the potential for exposure to alpha particles from inhaled plutonium is examined. It is found that there is no evidence that exposure to plutonium aerosols significantly affects the risk associated with external exposure. While the Mayak external dose risk estimate of an excess relative risk of 0.16 per Gy is somewhat lower than an appropriately normalized risk estimate from the Life Span Study of Japanese atomic bomb survivors, the uncertainties in these estimates preclude concluding that the external dose excess relative risks of this group of solid cancers differ in the two cohorts. (orig.)

Mortality from solid cancers other than lung, liver, and bone in relation to external dose among plutonium and non-plutonium workers in the Mayak Worker Cohort

International Nuclear Information System (INIS)

Sokolnikov, Mikhail; Preston, Dale; Stram, Daniel O.

2017-01-01

Exposure to ionizing radiation has well-documented long-term effects on cancer rates and other health outcomes in humans. While in vitro experimental studies had demonstrated that the nature of some radiation effects depend on both total dose of the radiation and the dose rate (i.e., the pattern of dose distribution over time), the question of whether or not the carcinogenic effect of radiation exposure depends on the dose rate remains unanswered. Another issue of interest concerns whether or not concomitant exposure to external gamma rays and inhaled plutonium aerosols has any effect on the external exposure effects. The analyses of the present paper focus on the risk of solid cancers at sites other than lung, liver, and bone in Mayak workers. Recent findings are reviewed indicating that there is no evidence of plutonium dose response for these cancers in the Mayak worker cohort. Then the evidence for differences in the external dose effects among workers with and without the potential for exposure to alpha particles from inhaled plutonium is examined. It is found that there is no evidence that exposure to plutonium aerosols significantly affects the risk associated with external exposure. While the Mayak external dose risk estimate of an excess relative risk of 0.16 per Gy is somewhat lower than an appropriately normalized risk estimate from the Life Span Study of Japanese atomic bomb survivors, the uncertainties in these estimates preclude concluding that the external dose excess relative risks of this group of solid cancers differ in the two cohorts. (orig.)

Collective dose of egyptian atomic energy workers during the period 1991-1995

Energy Technology Data Exchange (ETDEWEB)

Gomaa, M A; Youssef, S K [Reactor Division, and Radiation Protect. Dept., Nuclear Reseach Center Atomic Energy Authority, Cairo (Egypt)

1997-12-31

The collective dose to egyptian atomic energy authority workers during the period from 1991 - 1995 were statistically evaluated. The personnel dosimetry in use since 1957 for evaluating external exposure doses was mainly the Harwell blue badge and kodak radiation monitoring film for X and Gamma photons. The calibration sensitivity of the badge system was evaluated under the `AL` and/or `Pb/Sn alloy` filters. The results of calibration showed 15% errors in the predicted values for whole body effective doses. The statistical survey showed that the annual collective dose ranged between 0.83-1.54 man Sv. The annual limit of exposure presented 25-58% of the recommended annual limit by ICRP- 60 (1991). Details of the study will be considered in the text. 4 tabs.

A 10-year review of the dose history of radiation workers in the University of Surrey

International Nuclear Information System (INIS)

Parami, V.K.

1991-09-01

This thesis presents data on internally and externally received doses for radiation workers whose records are kept at the Safety Office of the University of Surrey for the period 1981-1990. The distribution of doses by range is presented and analysed. The patterns of the collective equivalent dose (CED) and the average individual equivalent dose (IED) over the 10-year period are presented. The annual CED is very low, so that even the total for the 10-year period is less than 1 man-Sv. Likewise, the annual average IED is extremely low, well below the average annual dose to the U.K. population from overall sources of ionising radiation. Some relevant aspects of the 1990 ICRP Recommendations are examined and the impact of these to the 'practices' and sources of ionising radiation in the University is given consideration. The results of the 10-year review provide more evidence of over designation of radiation workers in the University. A recommendation is made to reduce the number of workers who are routinely monitored and justification and options are presented. This study is viewed as a useful database which could be of particular importance in the procedure of optimisation of radiation protection in the University of Surrey and U.K. establishments for higher education as a whole. (author)

Determination of absorbed dose in reactors

International Nuclear Information System (INIS)

1971-01-01

There are many areas in the use and operation of research reactors where the absorbed dose and the neutron fluence are required. These include work on the determination of the radiolytic stability of the coolant and moderator and on the determination of radiation damage in structural materials, and reactor experiments involving radiation chemistry and radiation biology. The requirements range from rough estimates of the total heating due to radiation to precise values specifying the contributions of gamma rays, thermal neutrons and fast neutrons. To meet all these requirements a variety of experimental measurements and calculations as well as a knowledge of reactor radiations and their interactions is necessary. Realizing the complexity and importance of this field, its development at widely separated laboratories and the need to bring the experts in this work together, the IAEA has convened three panel meetings. These were: 'In-pile dosimetry', held in July 1964 (published by the Agency as Technical Reports Series No. 46); 'Neutron fluence measurements', in October 1965; and 'In-pile dosimetry', in November 1966. The recommendations of these three panels led the Agency to form a Working Group on Reactor Radiation Measurements and to commission the writing of this book and a book on Neutron Fluence Measurements. The latter was published in May 1970 (Technical Reports Series No. 107). The material on neutron fluence and absorbed dose measurements is widely scattered in reports and reviews. It was considered that it was time for all relevant information to be evaluated and put together in the form of a practical guide that would be valuable both to experienced workers and beginners in the field

Assessing Health Workers Knowledge on the Determinants of ...

African Journals Online (AJOL)

The participants were interviewed with a structured questionnaire used to elicit the knowledge of health workers on health determinants. Results: When individual factors were considered, a greater percentage of health workers, believed that safe drinking water (98.9%), where a person lives (96.6%) and a balanced diet, ...

Evolution of radiation doses received by workers and the public during the transportation of radioactive materials in France

International Nuclear Information System (INIS)

Hamard, J.; Fignon, M.; Mauny, G.; Bernard, H.; Morin, J.

1989-01-01

This study makes an inventory of external irradiation dose equivalents and collective dose equivalents received by workers and the public during the transportation of radioactive materials in France between 1982 and 1988 (in the following, the authors use only the term dose). It deals with the transport of radiopharmaceuticals, irradiated fuels, wastes and other various radioactive materials. The evolution of the doses is referred to the variation of the number of packages, the mass on the volume transported for these main categories of materials. The transportation of radioactive materials uses various transport means: road, rail, air, and implies the intervention of various societies. Most of them have taken part in this study. Most societies involved in the transport carry out an individual dosimetry of the workers. But the decisions to carry such a dosimetry depends on the appreciation of the employer in relation with the more or less evident level of risk resulting from the transport and handling of the radioactive materials. The relatively low level of risk in current situations could incite some carriers not to carry out individual dosimetry. Thus the knowledge of individual doses essentially variables with the workers would therefore be difficult

Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources

International Nuclear Information System (INIS)

Gerulis, Eduardo

2006-01-01

With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

Root cause analysis of the radiation workers (radiography) in excess doses of NBD (case study: PT. XYZ)

International Nuclear Information System (INIS)

Arifin M Wibowo; Fajariadi; Aditia Anamta

2013-01-01

Negligence and non-compliance is the main factor of causing an incident in radiography. It shown as the result of TLD evaluation of PT. XYZ workers exceeding the dose limit (NBD). Root cause analysis stage begin in collecting data such as license, workers permit, dose, and incident sequence report. Causal chart is a tool to identification root cause to make easier of the analysis. Results of collecting data are to be clarified in BAPETEN investigation and then there are some a recommendation to facility. (author)

Determination of beta radiation doses received by personnel involved in the mitigation of the Chernobyl accident

International Nuclear Information System (INIS)

Osanov, D.P.; Krjuchkov, V.P.; Shaks, A.I.

1993-01-01

During the accident at the Chernobyl nuclear power plant on April 26, 1986, and in the post-accident period, workers were exposed to beta and low-energy-photon radiation. This paper describes a method of retrospective estimation of skin doses from these radiations by correlating known doses from gamma radiation. Dose distributions of beta and gamma radiation in tissue-equivalent materials were both calculated and measured using multilayer thermoluminescent dosimeters placed at different site locations. It was determined that the doses to the skin from beta radiation exceeded the maximum doses to the whole-body from gamma radiation by 1 or even 2 orders of magnitude. It is concluded that nuclear power plants should be equipped with multilayer skin dosimeters in order to ensure accurate skin dosimetry. 16 refs., 13 figs., 3 tabs

Radiation monitoring and dose distribution of medical workers in A.P. state 1999-2000

International Nuclear Information System (INIS)

Singh, D.R.; Reddy, K.S.; Kamble, M.K.; Roy, Madhumita

2001-01-01

Individual monitoring for external ionizing radiation is being conducted for all radiation workers in Andhra Pradesh State by TLD Unit located in Nuclear Fuel Complex, Hyderabad.The Unit comes under Personnel Monitoring Section of Bhabha Atomic Research Center, Mumbai. The aim of monitoring is to confirm that the radiation safety standards are strictly adhered in the institutions and also to investigate excessive exposures, if any. Personnel monitoring also provides data for epidemiological studies. In view of ICRP/AERB recommendations of 100 mSv dose limit for the five years block of 1994-98, the dose distribution among radiation workers in Andhra Pradesh State is analyzed for the period 1994-98. In continuation of above work, we have analyzed the data for the year 1999-2000 for various medical diagnostic procedures and these are presented

Exposure dose evaluation of worker at radioactive waste incineration facility on KAERI

International Nuclear Information System (INIS)

Park, Sang Kyu; Jeon, Jong Seon; Kim, Youn Hwa; Lee, Jae Min; Lee, Gi Won

2011-01-01

An incineration treatment of inflammable radioactive wastes leads to have a reduction effect of disposal cost and also to contribute an enhancement of safety at a disposal site by taking the advantage of stabilization of the wastes which is accomplished by converting organic materials into inorganic materials. As it was required for an incineration technology, KAERI (Korea Atomic Energy Research Institute) has developed a pilot incineration process and then constructed a demonstration incineration facility having based on the operating experiences of the pilot process. In this study, worker exposure doses were evaluated to confirm safety of workers before the demonstration incineration facility will commence a commercial. (author)

Issues in environmental control data used in DD ampersand ER worker dose exposures

International Nuclear Information System (INIS)

White, M.G.

1995-01-01

Sites for decontamination and decommissioning (DD) or environmental remediation (ER) are often from US DOE operations that began during and shortly after World War II. This paper discusses selected problems in the use of environmental data for DD and ER worker dose exposure calculations

Low dose ionizing radiation exposure and cardiovascular disease mortality: cohort study based on Canadian national dose registry of radiation workers

International Nuclear Information System (INIS)

Zielinski, J. M.; Band, P. R.; Ashmore, P. J.; Jiang, H.; Shilnikova, N. S.; Tait, V. K.; Krewski, D.

2009-01-01

The purpose of our study was to assess the risk of cardiovascular disease (CVD) mortality in a Canadian cohort of 337 397 individuals (169 256 men and 168 141 women) occupationally exposed to ionizing radiation and included in the National Dose Registry (NDR) of Canada. Material and Methods: Exposure to high doses of ionizing radiation, such as those received during radiotherapy, leads to increased risk of cardiovascular diseases. The emerging evidence of excess risk of CVDs after exposure to doses well below those previously considered as safe warrants epidemiological studies of populations exposed to low levels of ionizing radiation. In the present study, the cohort consisted of employees at nuclear power stations (nuclear workers) as well as medical, dental and industrial workers. The mean whole body radiation dose was 8.6 mSv for men and 1.2 mSv for women. Results: During the study period (1951 - 1995), as many as 3 533 deaths from cardiovascular diseases have been identified (3 018 among men and 515 among women). In the cohort, CVD mortality was significantly lower than in the general population of Canada. The cohort showed a significant dose response both among men and women. Risk estimates of CVD mortality in the NDR cohort, when expressed as excess relative risk per unit dose, were higher than those in most other occupational cohorts and higher than in the studies of Japanese atomic bomb survivors. Conclusions: The study has demonstrated a strong positive association between radiation dose and the risk of CVD mortality. Caution needs to be exercised when interpreting these results, due to the potential bias introduced by dosimetry uncertainties, the possible record linkage errors, and especially by the lack of adjustment for non-radiation risk factors. (authors)

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

International Nuclear Information System (INIS)

WEISS, E.V.

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

CERN Document Server

Weiss, E V

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

Age and dose as determinants of times of appearance of radium-induced osteosarcomas in humans

International Nuclear Information System (INIS)

Stebbings, J.H.; Lucas, H.F.

1983-01-01

Determinants of time-until-tumor for bone sarcomas in US radium cases have been reevaluated. For the 57 measured female bone sarcoma cases exposed to 226 Ra and/or 228 Ra, ages at appearance of tumor are more strongly correlated with radium intake doses than are latency periods. Ages at appearance of tumor increase as initial radium intakes decrease. As many lower dose cases were iatrogenic cases exposed in mid-adult life, rather than about age 22 as for the dial worker cases, these results may be artifactual, resulting from an increased susceptability to sarcoma induction at older ages. Alternatively the time of appearance of a sarcoma may be in part directly determined by age. Both explanations find support in the literature. These results suggest that 226 228 Ra-induced bone sarcomas do have an expression period. The downturn in sarcoma incidence at very high doses may result from truncation of the expression period on its early side by the minimum induction period

Hand exposure of nuclear medicine workers

International Nuclear Information System (INIS)

Jankowski, J.; Wrzesien, M.; Olszewski, J.

2007-01-01

Full text: Workers of Nuclear Medicine units labelling radiopharmaceuticals with technetium 99mTc are exposed to gamma radiation. The general opinion that individual dosimetry, with the aid of personal dose meters worn on the radiopharmacists' body, reflects true exposure of that occupational group is false. The use of ring dose meters worn on the fingers does not provide a true indication of the exposure of the radiopharmacists' hands. Measurements performed in 2001 - 2005 by the Institute of Occupational Medicine, with the use of dose meters placed on radiopharmacists' fingers, revealed that the equivalent dose to the hands ranged from 5.5 mSv to 95 mSv. Mean annual dose was 29 mSv. The finger dose meter is usually worn at the base of the middle finger, even if it is the fingertips that are most exposed to the radiation. In 2004-2005, we determined the distributions of the doses to the radiopharmacists' hands. The determinations were performed during one working day. During those determinations, thermo luminescence detectors were placed at 19 locations on the left and right hands. The subjects were 13 workers of 5 nuclear medicine units. The recorded doses ranged from 0.02 to 28 mSv for the left hand, and from 0.01 to 18 mSv for the right hand. The results show that the tips of the thumb, index finger and middle finger were the most exposed areas. The chances that the skin of those three fingertips receives yearly doses in excess of the current limit of 500 mSv are fairly high. It is recommended, therefore, to use annual dose constraints for the dose recorded by the ring dose meter at the level of 100 mSv per year as a safe limit to protect workers from the risk of exceeding the limit value for the dermal exposure. Whenever the dose value approaches 100 mSv/u, where u is the number of determinations of the partial doses performed during the period of one year, steps must be undertaken to explain the reasons why such a level has been reached and suitable

Calculation of Water Levels in Spent Fuel Pool and Effective Dose Followed by the Worker Geometrically Exposed to Radiation using Gamma-ray Source

International Nuclear Information System (INIS)

Lee, Donghee; Park, Kwangheon; Yoon, Hyoungju

2013-01-01

If the total effective dose value is lower than the surface dose rate of the water, the worker is able to work in a safe environment. In the case that the level of spent fuel pool is up to 550cm, there exists the limitation for workers to access to the storage pool because the result value is about 8 times higher than surface dose rate. In the case that the level of spent fuel pool is higher than 600cm, however, it can be safe work environment because the result value is lower than surface dose rate. Therefore, in the case of ISO geometry which is the same with practical situation, when considering Gamma-ray emission from spent fuel, effective dose is much higher than surface dose rate when the level of storage pool is lower than the height of fuel, 452.8cm. On the other hand, the level of effective dose decreases rapidly when the level of storage pool is higher than the level of the fuel. This means that it is not the safe environment when the level of fuel below 140cm is lower than surface dose rate. That is why the access of workers should be limited. Whereas, in the case of the level of storage pool above 600cm which is about 140cm higher than the level of the fuel, it is the safe environment for workers because the result value becomes lower than surface dose rate As a result, the level of wet storage of spent fuel should be at least 600cm for workers to work in safe environment because lower dose than surface dose rate makes less radiation exposure

Radon Concentration in Caves of Croatia - Assesing Effective Radon Doses for Occupational Workers and Visitors

International Nuclear Information System (INIS)

Radolic, V.; Miklavcic, I.; Poje, M.; Stanic, D.; Vukovic, B.; Paar, D.

2011-01-01

Radon monitoring at potentially highly radioactive location such as caves is important to assess the radiological hazards to occupational workers and occasional visitors. In its Publication 65 the ICRP has produced recommendations dealing with exposure to elevated background radiation, in particular, the risk associated with the inhalation of radon and radon progeny. Recommended annual effective dose from radon 222Rn and its short-lived progeny for workers should not exceed 20 mSv and for occasional users (visitors) the same recommendation is 1 mSv. Measurements were performed with series of track etched detectors (LR115 - type II) in several caves in Croatia. The obtained values for the radon concentration ranged from ambient values up to several thousand Bq m -3 . Radon concentration was measured in about 20 caves of Velebit and Zumberak mountains and the highest radon concentration was in Lubuska jama (3.8 kBq m -3 ) and cave Dolaca (21.8 kBq m -3 ), respectively. Djurovica cave is especially interesting because of its huge tourist potential due to its location bellow Dubrovnik airport. Its mean annual radon concentration of 17.6 kBq m -3 classifies Djurovica cave among caves with high radon concentration. A visitor during half an hour visit at summer time would receive an effective dose of 30.6 μSv. Calculated mean dose rate of 44 μSv/h means that workers (mainly tourist guides) should limit their time inside cave to 454 hours per year. Manita pec is the only cave open for tourists on the territory of Paklenica National Park. The preliminary radon measurements performed during summer 2010, gave an average radon concentration of 1.1 kBq m -3 . An exposure to average dose rate of 3.7 μSv/h means that the tourist guides would receive an effective dose of 0.42 mSv during summer period according to their working schedule. A visitor during half an hour visits would receive an effective dose of 1.86 μSv. (author)

Occupational exposure of phosphate mine workers: airborne radioactivity measurements and dose assessment

International Nuclear Information System (INIS)

Khater, Ashraf E.; Hussein, M.A.; Hussein, Mohamed I.

2004-01-01

Under the Egyptian program for radiation safety and control, airborne radioactivity measurements and radiological dose assessment were conducted in some phosphate and uranium mines. Abu-Tartor mine is one of the biggest underground phosphate mines in Egypt. Airborne radioactivity, radon ( 222 Rn) and its short-lived decay products (progenies) and thoron ( 220 Rn), were measured in selected locations along the mine. The environmental gamma and workers dose equivalent rate (mSv/y) were measured inside and outside the mine using thermo-luminescence dosimeters (TLD). The results were presented and discussed. The calculated annual effective dose due to airborne radioactivity is the main source of occupational exposure and exceeding the maximum recommended level by ICRP-60 inside the mine tunnels. A number of recommendations are suggested to control the occupational exposures

Thyroid measurements of Iodine-125 workers

International Nuclear Information System (INIS)

Burns, P.A.; Peggie, J.R.

1979-02-01

The accumulation of 125 I in the thyroid presents real hazards to workers who use this radionuclide. Recent assessments of the maximum permissible thyroid burden for 125 I have tended to be lower than those previously adopted. Workers using 125 I may receive small doses to a film badge monitor from external radiation while accumulating significant doses to the thyroid from internal contamination. It is therefore necessary to perform some form of thyroid monitoring on such workers. In the past two years the Australian Radiation Laboratory has monitored 125 I workers from six different institutations in the Melbourne area to determine the activity of 125 I in their thyroids. Most of the levels monitored were less than one tenth of the most recently recommended thyroid burden of 400 nanocurie. The highest levels were measured in workers who actually perform iodinations. Workers who handle the iodinate generally had lower levels than those performing the iodinations. Only a very small number of the workers measured were below the detectable limit of the system indicating that even when low activities of 125 I are handled in relatively stable forms it is still possible to accumulate 125 I in the thyroid

Dose determination in computed tomography

International Nuclear Information System (INIS)

Descamps, C.; Garrigo, E.; Venencia, D.; Gonzalez, M.; Germanier, A.

2011-10-01

In the last years the methodologies to determine the dose in computed tomography have been revised. In this work was realized a dosimetric study about the exploration protocols used for simulation of radiotherapy treatments. The methodology described in the Report No. 111 of the American Association of Medical Physiques on a computed tomograph of two cuts was applied. A cylindrical phantom of water was used with dimensions: 30 cm of diameter and 50 cm of longitude that simulates the absorption and dispersion conditions of a mature body of size average. The doses were determined with ionization chamber and thermoluminescent dosimetry. The results indicate that the dose information that provides the tomograph underestimates the dose between 32 and 35%.

Survivor shielding. Part A. Nagasaki factory worker shielding

International Nuclear Information System (INIS)

Santoro, Robert T.; Barnes, John M.; Azmy, Yousry Y.; Kerr, George D.; Egbert, Stephen D.; Cullings, Harry M.

2005-01-01

Recent investigations based on conventional chromosome aberration data by the RERF suggest that the DS86 doses received by many Nagasaki factory workers may have been overestimated by as much as 40% relative to those for other survivors in Japanese-type houses and other shielding configurations (Kodama et al. 2001). Since the factory workers represent about 25% of the Nagasaki survivors with DS86 doses in excess of 0.5 Gy (50 rad), systematic errors in their dose estimates can have a major impact on the risk coefficients from RERF studies. The factory worker doses may have been overestimated for a number of reasons. The calculation techniques, including the factory building modeling, weapon source spectra and cross-section data used in the DS86 shielding calculations were not detailed enough to replicate actual conditions. The models used did not take into account local shielding provided by machinery, tools, and the internal structure in the buildings. In addition, changes in the disposition of shielding following collapse of the building by the blast wave were not considered. The location of large factory complexes may be uncertain, causing large numbers of factory survivors, correctly located relative to each other, to be uniformly too close to the hypocenter. Any or all of these reasons are sufficient to result in an overestimate of the factory worker doses. During the DS02 studies, factory worker doses have been reassessed by more carefully modeling the factory buildings, incorporating improved radiation transport methods and cross-section data and using the most recent bomb leakage spectra (Chapter 2). Two-dimensional discrete ordinates calculations were carried out initially to estimate the effects of workbenches and tools on worker doses to determine if the inclusion of these components would, in fact, reduce the dose by amounts consistent with the RERF observations (Kodama et al. 2001). (author)

Radiation doses and cause-specific mortality among workers at a nuclear materials fabrication plant

International Nuclear Information System (INIS)

Checkoway, H.; Pearce, N.; Crawford-Brown, D.J.; Cragle, D.L.

1988-01-01

A historical cohort mortality study was conducted among 6781 white male employees from a nuclear weapons materials fabrication plant for the years 1947-1979. Exposures of greatest concern are alpha and gamma radiation emanating primarily from insoluble uranium compounds. Among monitored workers, the mean cumulative alpha radiation dose to the lung was 8.21 rem, and the mean cumulative external whole body penetrating dose from gamma radiation was 0.96 rem. Relative to US white males, the cohort experienced mortality deficits from all causes combined, cardiovascular diseases, and from most site-specific cancers. Mortality excesses of lung and brain and central nervous system cancers were seen from comparisons with national and state rates. Dose-response trends were detected for lung cancer mortality with respect to cumulative alpha and gamma radiation, with the most pronounced trend occurring for gamma radiation among workers who received greater than or equal to 5 rem of alpha radiation. These trends diminished in magnitude when a 10-year latency assumption was applied. Under a zero-year latency assumption, the rate ratio for lung cancer mortality associated with joint exposure of greater than or equal to 5 versus less than 1 rem of both types of radiation is 4.60 (95% confidence limits (CL) 0.91, 23.35), while the corresponding result, assuming a 10-year latency, is 3.05 (95% CL 0.37, 24.83). While these rate ratios, which are based on three and one death, respectively, lack statistical precision, the observed dose-response trends indicate potential carcinogenic effects to the lung of relatively low-dose radiation. There are no dose-response trends for mortality from brain and central nervous system cancers

An overview of equivalent doses in eye lens of occupational radiation workers in medical, industrial and nuclear areas

International Nuclear Information System (INIS)

Lima, A.R.; Silva, F.C.A. da; Hunt, J.G.

2013-01-01

Some epidemiological evidences were recently reviewed by the ICRP and it was suggested that, for the eye lens, the absorbed dose threshold for induction of late detriments is about 0.5 Gy. On this basis, on 2011, the ICRP has recommended changes to the occupational dose limit in planned exposure situations, reducing the eye lens dose equivalent limit of 150 mSv to 20 mSv per year, on average, during the period of 5 years, with exposure not exceeding 50 mSv in a single year. Following the ICRP recommendation, the Brazilian Commission of Nuclear Energy (CNEN) adopted immediately the new limit to the eyes lens. This study aimed to show an overview about the doses in eye lens of occupational radiation workers in situations of planned exposures in the medical, industrial and nuclear areas, emphasizing the greatest radiological risks applications. It was observed that there are some limitations, such as example, to use individual monitor calibrated on Hp(3), to assess the equivalent dose in the eye lens. This limitation obstructs some experimental studies and monitoring of the levels of radiation received in the eye lens of radiation workers. Recent studies have showed that the lenses of eyes monitoring of workers, mainly in the planned exposure, must be follow-up. However, such researches were obtained only in medical exposures, mainly in interventional medicine procedures. Studies with planned exposure on nuclear and industrial areas are really needed and will be very important due to the new recommended by ICRP dose limits. (author)

Evaluation of the space scattered dose according to the position of the radiation workers in mammography room

Energy Technology Data Exchange (ETDEWEB)

Lee, Dong Yeon [Dept. of Radiation Oncology, Dongnam Inst. of Radiological and Medical Science, Busan (Korea, Republic of); Lee, Jin Soo [Dept. of Radiology, Inje University Heaundae Paik Hospital, Busan (Korea, Republic of)

2016-09-15

This study was conducted to evaluate the dose of the space to the controller located within the mammography room conducted a research on ways to the reduction exposure to the radiation workers. Results, the dose of 6.18 mGy/year was measured when there is no difference in the hilar area of the controller position, the dose of 2.35E-11 mGy/year was measured when installing the Shielding door. In addition, when the direction of the X-ray tube anode be heading this direction controller, low average level measured was 0.30 mGy/year. Based on this study, the mammography should be considered when installing the anode and cathod directions. And, by installing the shielding door, it must be able to completely separate shooting space and control room. This is the best way radiation protection method in radiation workers.

Calculation methods for determining dose equivalent

International Nuclear Information System (INIS)

Endres, G.W.R.; Tanner, J.E.; Scherpelz, R.I.; Hadlock, D.E.

1988-01-01

A series of calculations of neutron fluence as a function of energy in an anthropomorphic phantom was performed to develop a system for determining effective dose equivalent for external radiation sources. critical organ dose equivalents are calculated and effective dose equivalents are determined using ICRP-26 methods. Quality factors based on both present definitions and ICRP-40 definitions are used in the analysis. The results of these calculations are presented and discussed

New dose limits and distribution of annual doses for controlled groups

International Nuclear Information System (INIS)

Vukcevic, M.; Stankovic, S.; Kovacevic, M.

1993-01-01

The new calculations of neutron doses received by the population of Hiroshima and Nagasaki, as well as the epidemiological data on the incidence of fatal cancers in the survivors, had led to the conclusion that the risk estimates should be raised by the factor 2 or 3. In this work, the distribution of monthly doses for occupationals was analysed in order to determine the percent of workers who might be considered as overexposed, on the basis of the new dose limits. (author)

Contribution to optimization of individual doses of workers in shipment of generator technetium-99m

International Nuclear Information System (INIS)

Fonseca, Lizandra Pereira de Souza

2010-01-01

The Instituto de Pesquisas Energeticas e Nucleares, IPEN, radiopharmaceuticals research and produce that are distributed throughout Brazil, currently the radiopharmaceutical with the largest number of packaged shipped per year and with the highest total activity is the 99m technetium generator. To reduce individual doses for workers involved in the production of radiopharmaceuticals was performed a study of radiological protection optimization in the shipment process of technetium generator, using the techniques: differential cost-benefit analysis, integral cost-benefit analysis, multi-attribute utility analysis and multi-criteria outranking analysis. With changes in the configuration of packed for generator dispatch and with the acquirement of a mat transporter it was possible establish 4 protection options. The attributes considered were the protection cost, collective dose, individual dose and physical effort by worker to move the package without the mat. To assess the robustness of analytical solutions found with the techniques used in the optimization we performed a sensitivity study and found that option 3 is more robust than option 1, which is no longer the analytical solution with an increase of R$ 20.000,00 the cost of protection. (author)

Dose evaluation in occupationally exposed workers through dosimeters ring and wrist type with an anthropomorphic phantom

International Nuclear Information System (INIS)

Palma, R.; Gastelo, E.; Paucar, R.; Tolentino, D.; Herrera, J.; Armas, D.

2014-08-01

In the Nuclear Medicine service of the Clinica San Pablo (Peru), the occupationally exposed workers carried out the preparation and administration of radiopharmaceuticals to patients, so it is vital to measure the equivalent dose to the hands during the procedures in order to optimize the exposure to the ionizing radiation and execute the Radiological Safety Regulation (D.S. No. 009-97-Em) and the standard IR 002.2012 of radiation protection and safety in nuclear medicine. In this paper was designed and built a hand anthropomorphic phantom made of paraffin following the description given for the standard man, later were placed dosimeters ring and wrist type UD-807 model, Panasonic brand. Then we proceeded to irradiate using vial containers of Tc-99 and I-131. The obtained results showed the difference between the equivalent dose obtained among the ring and wrist dosimeter also getting a dose of 153 mSv /year when working with 99m Tc and of 61 mSv /year when working with iodine-131. Was also demonstrated that the ring dosimeter shows the average dose received in the hand with less dispersion. It was found that under the national regulation on Requirements of Radiation Protection and Nuclear Safety in Medicine article 63, indicates that higher doses of 150 mSv /year the occupationally exposed workers should have hand dosimetry. Finally the individual dose limit of 500 mSv /year in extremities can be overcome if adequate radiation protection standards do not apply. (author)

Outbreaks where food workers have been implicated in the spread of foodborne disease. Part 4. Infective doses and pathogen carriage.

Science.gov (United States)

Todd, Ewen C D; Greig, Judy D; Bartleson, Charles A; Michaels, Barry S

2008-11-01

In this article, the fourth in a series reviewing the role of food workers in foodborne outbreaks, background information on the presence of enteric pathogens in the community, the numbers of organisms required to initiate an infection, and the length of carriage are presented. Although workers have been implicated in outbreaks, they were not always aware of their infections, either because they were in the prodromic phase before symptoms began or because they were asymptomatic carriers. Pathogens of fecal, nose or throat, and skin origin are most likely to be transmitted by the hands, highlighting the need for effective hand hygiene and other barriers to pathogen contamination, such as no bare hand contact with ready-to-eat food. The pathogens most likely to be transmitted by food workers are norovirus, hepatitis A virus, Salmonella, Shigella, and Staphylococcus aureus. However, other pathogens have been implicated in worker-associated outbreaks or have the potential to be implicated. In this study, the likelihood of pathogen involvement in foodborne outbreaks where infected workers have been implicated was examined, based on infectious dose, carriage rate in the community, duration of illness, and length of pathogen excretion. Infectious dose estimates are based on volunteer studies (mostly early experiments) or data from outbreaks. Although there is considerable uncertainty associated with these data, some pathogens appear to be able to infect at doses as low as 1 to 100 units, including viruses, parasites, and some bacteria. Lengthy postsymptomatic shedding periods and excretion by asymptomatic individuals of many enteric pathogens is an important issue for the hygienic management of food workers.

Measurements of 222Rn and its daughters and estimation of internal doses to workers in underground buildings

International Nuclear Information System (INIS)

Cao Jianping; Lu Zhizhao; Li Yuanshan

1993-03-01

The results of concentration measuring of 222 Ru and its daughters and estimation of internal doses to workers in the underground buildings at Nanjing city are presented. The double filtering membrane method and Thomas method were used in the monitoring of 222 Rn and its daughters, and the dose conversion factor was taken from the latest UNSCEAR report. Concentration distributions of 222 Rn and its daughters were approximately log-normal. The geometric means for 222 Rn was 40.5 Bq · m -3 and for its daughters was 1.4 x 10 -7 J · m -3 . The equilibrium factor was 0.63. The radioactive equilibrium ratio between short-lived 222 Rn daughters was 1:0.57:0.49. The estimation value of annual effective dose equivalent from 222 Rn daughters to workers working at underground sites was 1.3 mSv, which was 86% higher than that of those working on ground sites

[Risk of deterministic effects after exposure to low doses of ionizing radiation: retrospective study among health workers in view of a new publication of International Commission on Radiological Protection].

Science.gov (United States)

Negrone, Mario; Di Lascio, Doriana

2016-01-01

The new recommended equivalent (publication n. 118 of International Commission on Radiological Protection) dose limit for occupational exposure of the lens of the eye is based on prevention of radiogenic cataracts, with the underlying assumption of a nominal threshold which has been adjusted from 2,5 Gy to 0.5 Gy for acute or protracted exposure. The study aim was to determine the prevalence of ocular lens opacity among healthcare workers (radiologic technologists, physicians, physician assistants) with respect to occupational exposures to ionizing radiations. Therefore, we conducted another retrospective study to explore the relationship between occupational exposure to radiation and opacity lens increase. Healthcare data (current occupational dosimetry, occupational history) are used to investigate risk of increase of opacity lens of eye. The sample of this study consisted of 148 health-workers (64 M and 84 W) aged from 28 to 66 years coming from different hospitals of the ASL of Potenza (clinic, hospital and institute with scientific feature). On the basis of the evaluation of the dosimetric history of the workers (global and effective dose) we agreed to ascribe the group of exposed subjects in cat A (equivalent dose > 2 mSV) and the group of non exposed subjects in cat B (workers with annual absorbed level of dose near 0 mSv). The analisys was conducted using SPSS 15.0 (Statistical Package for Social Science). A trend of increased ocular lens opacity was found with increasing number for workers in highest category of exposure (cat. A, Yates' chi-squared test = 13,7 p = 0,0002); variable significantly related to opacity lens results job: nurse (Χ(2)Y = 14,3 p = 0,0002) physician (Χ(2)Y = 2.2 p = 0,1360) and radiologic technologists (Χ(2)Y = 0,1 p = 0,6691). In conclusion our provides evidence that exposure to relatively low doses of ionizing radiation may be harmful to the lens of the eye and may increase a long-term risk of cataract formation; similary

Spectrum of chromosomal aberrations in peripheral lymphocytes of hospital workers occupationally exposed to low doses of ionizing radiation

International Nuclear Information System (INIS)

Maffei, Francesca; Angelini, Sabrina; Forti, Giorgio Cantelli; Violante, Francesco S.; Lodi, Vittorio; Mattioli, Stefano; Hrelia, Patrizia

2004-01-01

Chromosome aberrations frequency was estimated in peripheral lymphocytes from hospital workers occupationally exposed to low levels of ionizing radiation and controls. Chromosome aberrations yield was analyzed by considering the effects of dose equivalent of ionizing radiation over time, and of confounding factors, such as age, gender and smoking status. Frequencies of aberrant cells and chromosome breaks were higher in exposed workers than in controls (P=0.007, and P=0.001, respectively). Seven dicentric aberrations were detected in the exposed group and only three in controls, but the mean frequencies were not significantly different. The dose equivalent to whole body of ionizing radiation (Hwb) did appear to influence the spectrum of chromosomal aberrations when the exposed workers were subdivided by a cut off at 50 mSv. The frequencies of chromosome breaks in both subgroups of workers were significantly higher than in controls (≤50 mSv, P=0.041; >50 mSv, P=0.018). On the other hand, the frequency of chromatid breaks observed in workers with Hwb >50 mSv was significantly higher than in controls (P=0.015) or workers with Hwb ≤50 mSv (P=0.046). Regarding the influence of confounding factors on genetic damage, smoking status and female gender seem to influence the increase in chromosome aberration frequencies in the study population. Overall, these results suggested that chromosome breaks might provide a good marker for assessing genetic damage in populations exposed to low levels of ionizing radiation

Labour cost of radiation dose

International Nuclear Information System (INIS)

Cook, A.; Lockett, L.E.

1978-01-01

In order to optimise capital expenditure on measures to protect workers against radiation it would be useful to have a means to measure radiation dose in money terms. Because labour has to be employed to perform radiation work there must be some relationship between the wages paid and the doses received. Where the next increment of radiation dose requires additional labour to be recruited the cost will at least equal the cost of the extra labour employed. This paper examines some of the factors which affect the variability of the labour cost of radiation dose and notes that for 'in-plant' exposures the current cost per rem appears to be significantly higher than values quoted in ICRP Publication 22. An example is given showing how this concept may be used to determine the capital it is worth spending on installed plant to prevent regular increments of radiation dose to workers. (author)

External radiation dose and cancer mortality among French nuclear workers: considering potential confounding by internal radiation exposure.

Science.gov (United States)

Fournier, L; Laurent, O; Samson, E; Caër-Lorho, S; Laroche, P; Le Guen, B; Laurier, D; Leuraud, K

2016-11-01

French nuclear workers have detailed records of their occupational exposure to external radiation that have been used to examine associations with subsequent cancer mortality. However, some workers were also exposed to internal contamination by radionuclides. This study aims to assess the potential for bias due to confounding by internal contamination of estimates of associations between external radiation exposure and cancer mortality. A cohort of 59,004 workers employed for at least 1 year between 1950 and 1994 by CEA (Commissariat à l'Energie Atomique), AREVA NC, or EDF (Electricité de France) and badge-monitored for external radiation exposure were followed through 2004 to assess vital status and cause of death. A flag based on a workstation-exposure matrix defined four levels of potential for internal contamination. Standardized mortality ratios were assessed for each level of the internal contamination indicator. Poisson regression was used to quantify associations between external radiation exposure and cancer mortality, adjusting for potential internal contamination. For solid cancer, the mortality deficit tended to decrease as the levels of potential for internal contamination increased. For solid cancer and leukemia excluding chronic lymphocytic leukemia, adjusting the dose-response analysis on the internal contamination indicator did not markedly change the excess relative risk per Sievert of external radiation dose. This study suggests that in this cohort, neglecting information on internal dosimetry while studying the association between external dose and cancer mortality does not generate a substantial bias. To investigate more specifically the health effects of internal contamination, an effort is underway to estimate organ doses due to internal contamination.

External radiation dose and cancer mortality among French nuclear workers. Considering potential confounding by internal radiation exposure

Energy Technology Data Exchange (ETDEWEB)

Fournier, L.; Laurent, O.; Samson, E.; Caer-Lorho, S.; Laurier, D.; Leuraud, K. [Institute for Radiological Protection and Nuclear Safety, Fontenay aux Roses (France). Ionizing Radiation Epidemiology Lab.; Laroche, P. [AREVA, Paris (France); Le Guen, B. [EDF, Saint Denis (France)

2016-11-15

French nuclear workers have detailed records of their occupational exposure to external radiation that have been used to examine associations with subsequent cancer mortality. However, some workers were also exposed to internal contamination by radionuclides. This study aims to assess the potential for bias due to confounding by internal contamination of estimates of associations between external radiation exposure and cancer mortality. A cohort of 59,004 workers employed for at least 1 year between 1950 and 1994 by CEA (Commissariat a l'Energie Atomique), AREVA NC, or EDF (Electricite de France) and badge-monitored for external radiation exposure were followed through 2004 to assess vital status and cause of death. A flag based on a workstation-exposure matrix defined four levels of potential for internal contamination. Standardized mortality ratios were assessed for each level of the internal contamination indicator. Poisson regression was used to quantify associations between external radiation exposure and cancer mortality, adjusting for potential internal contamination. For solid cancer, the mortality deficit tended to decrease as the levels of potential for internal contamination increased. For solid cancer and leukemia excluding chronic lymphocytic leukemia, adjusting the dose-response analysis on the internal contamination indicator did not markedly change the excess relative risk per Sievert of external radiation dose. This study suggests that in this cohort, neglecting information on internal dosimetry while studying the association between external dose and cancer mortality does not generate a substantial bias. To investigate more specifically the health effects of internal contamination, an effort is underway to estimate organ doses due to internal contamination.

The Evaluation of personnel radiation dose and society radiation on RSG-GAS around as proposal determination of ALARA value

International Nuclear Information System (INIS)

Pande Made Udiyani; Puradwi IW

2007-01-01

Each nuclear installation to achieve radiation safety has to meet the ALARA concepts. The ALARA value of a nuclear installation should be enacted by regulator body. ALARA value can be determined by evaluation radiation exposure and dose acceptance of nuclear installation operation. As case study in Indonesia, ALARA assessment in nuclear installation is done at RSG-GAS reactor. Intention of this research is to determine gyration reference assess ALARA by evaluate radiation dose acceptance by RSG-GAS radiation personnel and the influence of RSG-GAS operation to presentation of radiation accepted by society which living around its. ALARA of RSG-GAS determined based on evaluation of measurement data of the radiation doses which is accepted by personnel radiation. While evaluation of radiation doses which is accepted by society in the radius 5 km of the RSG-GAS conducted to data result of calculation using program package of CAP-88 and measurement result with method of carborne survey. Result of radiation dose evaluation obtained which not pass dose definition for the radiation worker that is 50 mSv/year, and for society around RSG-GAS that is 5 mSv/year. Based on the result of evaluation hence obtained value of ALARA for RSG-GAS in value of gyration 17 - 50 mSv/year. (author)

Sensitivity analysis on the priority order of the radiological worker allocation model using goal programming

International Nuclear Information System (INIS)

Jung, Hae Yong; Lee, Kun Jai

1998-01-01

In nuclear power plant, it has been the important object to reduce the occupational radiation exposure (ORE). Recently, the optimization concept of management science has been studied to reduce the ORE in nuclear power plant. In optimization of the worker allocation, the collective dose, working time, individual dose, and total number of worker must be considered and their priority orders must be thought because the main constraint is necessary for determining the constraints variable of the radiological worker allocation problem. The ultimate object of this study is to look into the change of the optimal allocation of the radiological worker as priority order changes. In this study, the priority order is the characteristic of goal programming that is a kind of multi-objective linear programming. From a result of study using goal programming, the total number of worker and collective dose of worker have changed as the priority order has changed and the collective dose limit have played an important role in reducing the ORE

Determination of organ doses and effective doses in radiooncology

International Nuclear Information System (INIS)

Roth, J.; Martinez, A.E.

2007-01-01

Background and Purpose: With an increasing chance of success in radiooncology, it is necessary to estimate the risk from radiation scatter to areas outside the target volume. The cancer risk from a radiation treatment can be estimated from the organ doses, allowing a somewhat limited effective dose to be estimated and compared. Material and Methods: The doses of the radiation-sensitive organs outside the target volume can be estimated with the aid of the PC program PERIDOSE developed by van der Giessen. The effective doses are determined according to the concept of ICRP, whereby the target volume and the associated organs related to it are not taken into consideration. Results: Organ doses outside the target volume are generally < 1% of the dose in the target volume. In some cases, however, they can be as high as 3%. The effective doses during radiotherapy are between 60 and 900 mSv, depending upon the specific target volume, the applied treatment technique, and the given dose in the ICRU point. Conclusion: For the estimation of the radiation risk, organ doses in radiooncology can be calculated with the aid of the PC program PERIDOSE. While evaluating the radiation risk after ICRP, for the calculation of the effective dose, the advanced age of many patients has to be considered to prevent that, e.g., the high gonad doses do not overestimate the effective dose. (orig.)

Estimation of staff doses in complex radiological examinations using a Monte Carlo computer code

International Nuclear Information System (INIS)

Vanhavere, F.

2007-01-01

The protection of medical personnel in interventional radiology is an important issue of radiological protection. The irradiation of the worker is largely non-uniform, and a large part of his body is shielded by a lead apron. The estimation of effective dose (E) under these conditions is difficult and several approaches are used to estimate effective dose involving such a protective apron. This study presents a summary from an extensive series of simulations to determine scatter-dose distribution around the patient and staff effective dose from personal dosimeter readings. The influence of different parameters (like beam energy and size, patient size, irradiated region, worker position and orientation) on the staff doses has been determined. Published algorithms that combine readings of an unshielded and a shielded dosimeter to estimate effective dose have been applied and a new algorithm, that gives more accurate dose estimates for a wide range of situations was proposed. A computational approach was used to determine the dose distribution in the worker's body. The radiation transport and energy deposition was simulated using the MCNP4B code. The human bodies of the patient and radiologist were generated with the Body Builder anthropomorphic model-generating tool. The radiologist is protected with a lead apron (0.5 mm lead equivalent in the front and 0.25 mm lead equivalent in the back and sides) and a thyroid collar (0.35 mm lead equivalent). The lower-arms of the worker were folded to simulate the arms position during clinical examinations. This realistic situation of the folded arms affects the effective dose to the worker. Depending on the worker position and orientation (and of course the beam energy), the difference can go up to 25 percent. A total of 12 Hp(10) dosimeters were positioned above and under the lead apron at the neck, chest and waist levels. Extra dosimeters for the skin dose were positioned at the forehead, the forearms and the front surface of

Film badge personnel monitoring and dose distribution of industrial and medical workers in the country (1994-1998)

International Nuclear Information System (INIS)

Mittal, Hariom; Pandey, R.L.; Massand, O.P.

2001-03-01

Personnel Monitoring Section, Bhabha Atomic Research Centre, Mumbai, is entrusted with the responsibility of providing a countrywide personnel monitoring to radiation workers using extemal radiation like X, beta, gamma and neutron. As per Radiation Protection Rules (RPR) of 1971 promulgated by the competent authority the personnel monitoring service is mandatory for all the workers working with radiation. The radiation exposures received by them should be within the limits stipulated by AERB. Nearly 43,000 radiation workers in about 3000 DAE and non DAE institutions using radiation and radioisotopes are monitored, using both the Film Badges and the Thermoluminescent dosimeters. This report presents various aspects of film dosimetry which was introduced more than four decades ago in the country and also analysis of doses received by the radiation workers in the five year block 1994-1998 covered by film badge service. (author)

Chromosome intra- and inter-changes determined by G-banding in radiation workers with in vivo exposure to plutonium

International Nuclear Information System (INIS)

Tawn, E Janet; Whitehouse, Caroline A

2005-01-01

Suggestions that exposure to intakes of alpha-emitting radionuclides such as plutonium could result in a specific profile of chromosome damage distinguishable from that of low LET irradiation have led to the re-analysis of the different types of chromosome aberrations in peripheral blood lymphocytes determined by G-banding in a group of 20 plutonium workers from the British Nuclear Fuels plc facility at Sellafield, UK. Comparisons were made with a group of workers with negligible plutonium intakes but similar external gamma doses and with an unexposed control group. Examination of simple translocation frequencies in the three groups indicated a significant difference (P = 0.033), with the higher frequency in the plutonium workers indicating that exposure from plutonium was contributing to the aberration yield. Slightly raised frequencies of both intra-chromosomal and complex aberrations were observed in the plutonium workers in comparison with the comparable external exposure group and the control group but the difference did not reach significance at the P = 0.05 level and there was no variation in the relative frequencies of the different aberration types between the three groups. There was, therefore, no firm indication from this study that either intra-chromosomal or complex aberrations could be used as a specific marker of high LET exposure in workers with historical intakes of plutonium

Job Satisfaction and Its Determinants among Health Workers in ...

African Journals Online (AJOL)

Job Satisfaction and Its Determinants among Health Workers in Jimma University ... insufficient training opportunities and inadequate number of human resources. ... salary increment, establishing good administration management system and ...

Epidemiological studies on radiation workers in Korea

International Nuclear Information System (INIS)

Soo Yong Choi; Hai Won Chung

2007-01-01

Complete text of publication follows. Objectives: The aim of this study is to analyze the occupational exposure for external radiation and to evaluate radiation effects on Korean radiation workers. Methods: The National Dose Registry contains radiation exposure records for all monitored radiation workers since its creation in 1983. We are carrying out epidemiological survey for radiation workers. The items of information included personal identification, employment and dose data. The frequencies of various types of chromosome aberrations in radiation workers were compared with controls. The data were analyzed according to year, sex, age, duration of occupation, exposure dose, etc. using SPSS statistical package(version 15.0). The goodness-of-fit test for Poisson assumption and dispersion test for detecting heterogeneity for Poisson distribution were done with chromosomal aberrations among study subjects. Results: The total number of workers registered from 1983 to 2005 was 61,610. The number of workers steadily increased and the accumulated dose somewhat increased. The collective annual dose of radiation workers was 345.823 man Sv and the mean annual dose was 1.34mSv. The frequencies of chromosome aberrations in 102 workers were compared with those in 42 controls. The frequencies of all types of chromosome aberrations in the exposed subjects were higher than those in the control group. Poisson regression analysis showed that there was significant association of chromosome aberrations with radiation dose, duration of work, age and alcohol intake. We started to survey radiation workers in order to evaluate radiation effects, collected epidemiological data for 9,157 workers at present and analyzed their lifetime radiation exposure doses. Follow-up is carrying out using the Korean Mortality Data, Cancer Registry and individual investigation. Among study patients, 11 of 38 deaths were identified with cancer. Conclusions: The data on occupational doses shows that

Area Factor Determinations for an Industrial Worker Exposed to a Concrete Slab End-State

International Nuclear Information System (INIS)

Jannik, G. Timothy; Lee, Patricia L.; Farfan, Eduardo B.; Roach, Jesse L.

2008-01-01

The U.S. Department of Energy's (DOE) Savannah River Site (SRS) is decommissioning many of its excess facilities through removal of the facility structures leaving only the concrete-slab foundations in place. Site-specific, risk-based derived concentration guideline levels (DCGLs) for radionuclides have been determined for a future industrial worker potentially exposed to residual contamination on these concrete slabs as described in Jannik. These risk-based DCGLs were estimated for an exposure area of 100 m 2 . During deactivation and decommissioning (D and D) operations at SRS, the need for area factors for larger and smaller contaminated areas arose. This paper compares the area factors determined for an industrial worker exposed to a concrete slab end-state for several radionuclides of concern at SRS with 1) the illustrative area factors provided in MARSSIM, 2) the area correction factors provided in the U.S. Environmental Protection Agency's (EPA) Soil Screening Guidance, and 3) the hot spot criterion for field application provided in the RESRAD User's Manual. The purpose of this site-specific assessment is to determine if any of the recommended area factors provided in the guidance documents could be utilized at SRS for field applications of the industrial worker DCGLs. Results show the area factors that were determined for an SRS industrial worker exposed to concrete slab end-states for the common radionuclides provided in the referenced guidance documents. In addition to the SRS site-specific area factors, the following area factors are provided for comparison: - Illustrative examples of outdoor area dose factors (MARSSIM); - Area correction factors as a function of source area (Soil Screening Guidance). Note: the area correction factors were inverted to correspond to a DCGL area factor. - Recommended area correction factors as a function of source area (Soil Screening Guidance); - Ranges for hot spot multiplication factors (RESRAD). As it can be seen

Effective dose evaluation for workers assisting new-borns in nuclear medicine procedures

International Nuclear Information System (INIS)

Falivene, A.; Gori, C.; Mazzocchi, S.; Targetti, S.; Zatelli, G.

2002-01-01

Renal scintigraphy is a very frequent nuclear medicine procedure for new-borns when deemed necessary after prenatal ultrasounds investigation. The procedure requires the physical proximity of workers to the patient, particularly during the examination of new-borns, in order to keep the young patients still. The irradiation of nurses during kidney examination of new-borns has been measured by simulating the examination procedure with an Alderson Rando phantom stuffed with thermoluminescent detectors, positioned near a radioactive source obtained with a tank filled with a 9 9mT c solution. Measurements have been carried out both with and without radiation protection devices positioned on the Rando phantom. Different organ doses have been evaluated. The aim of this analysis is to evaluate the amount of dose reduction that can be achieved by utilising lead aprons, glasses and thyroid collars

Risk of occupational radiation-induced cataract in medical workers

International Nuclear Information System (INIS)

Snezana, Milacic

2008-01-01

The objective of this study was determination of criteria for recognition of a pre senile cataract as a professional disease in health care personnel exposed to small doses of ionizing radiation. Method: The study included 3240 health workers in medical centers of Serbia in the period 1992-2002. A total of 1560 workers were employed in the zone (group A) and 1680 out of ionizing radiation zone (group B). Among group A, two groups had been selected: 1. Group A-1: Health workers in the ionizing radiation zone who contracted lens cataract during their years of service while dosimetry could not reveal higher absorbed dose (A-1=115); 2. Group A-2: Health workers in the ionizing radiation zone with higher incidence of chromosomal aberrations and without cataract (A-2=100). Results: More significant incidence of cataract was found in group A, χ 2 =65.92; p<0.01. Radiation risk was higher in health workers in radiation zone than in others, relative risk is 4, 6. Elevated blood sugar level was found in higher percentage with health workers working in radiation zone who developed cataract. Conclusion: Low doses of radiation are not the cause of occupational cataract as individual occupational disease. X-ray radiation may be a significant cofactor of cataract in radiological technicians. (author)

Shared dosimetry error in epidemiological dose-response analyses

International Nuclear Information System (INIS)

Stram, Daniel O.; Preston, Dale L.; Sokolnikov, Mikhail; Napier, Bruce; Kopecky, Kenneth J.; Boice, John; Beck, Harold; Till, John; Bouville, Andre; Zeeb, Hajo

2015-01-01

Radiation dose reconstruction systems for large-scale epidemiological studies are sophisticated both in providing estimates of dose and in representing dosimetry uncertainty. For example, a computer program was used by the Hanford Thyroid Disease Study to provide 100 realizations of possible dose to study participants. The variation in realizations reflected the range of possible dose for each cohort member consistent with the data on dose determinates in the cohort. Another example is the Mayak Worker Dosimetry System 2013 which estimates both external and internal exposures and provides multiple realizations of 'possible' dose history to workers given dose determinants. This paper takes up the problem of dealing with complex dosimetry systems that provide multiple realizations of dose in an epidemiologic analysis. In this paper we derive expected scores and the information matrix for a model used widely in radiation epidemiology, namely the linear excess relative risk (ERR) model that allows for a linear dose response (risk in relation to radiation) and distinguishes between modifiers of background rates and of the excess risk due to exposure. We show that treating the mean dose for each individual (calculated by averaging over the realizations) as if it was true dose (ignoring both shared and unshared dosimetry errors) gives asymptotically unbiased estimates (i.e. the score has expectation zero) and valid tests of the null hypothesis that the ERR slope β is zero. Although the score is unbiased the information matrix (and hence the standard errors of the estimate of β) is biased for β≠0 when ignoring errors in dose estimates, and we show how to adjust the information matrix to remove this bias, using the multiple realizations of dose. The use of these methods in the context of several studies including, the Mayak Worker Cohort, and the U.S. Atomic Veterans Study, is discussed

The distribution of committed dose equivalents to workers exposed to tritium in the luminising industry in the United Kingdom

International Nuclear Information System (INIS)

Hipkin, J.

1977-01-01

In the United Kingdom tritium has become almost the only radionuclide that is used in luminising. Two distinct methods of luminising are used, one involving the use of tritium gas and the other involving the use of tritium activated luminous paint. All major luminisers have voluntarily taken part in urine monitoring programmes. The analyses have been carried out by the National Radiological Protection Board and estimates of committed dose equivalent have been made from the results. The work presented is an analysis of the committed dose equivalents received by all the individuals monitored in the years 1974, 1975 and 1976. It is shown that doses follow, in general, a lognormal distribution modified only at the high dose end by what must be described as dose management. Further evidence for dose management is seen when the pattern of dose versus time are analysed for selected individuals. It is shown that the maximum permissible dose as recommended by the International Commission on Radiological Protection, is only rarely exceeded. It is also shown that there is a substantial difference in the degree of exposure between workers involved in gaseous tritium luminising and workers using paint luminising. A comparison is made between exposure in gaseous tritium luminising and exposure in another common use of gaseous tritium, ie. the filling of electronic devices with tritium gas. It is shown that exposure is very much less in the electronic device work

Occupational radiation doses in Portugal from 1994 to 1998

International Nuclear Information System (INIS)

Alves, J.G.; Martins, M.B.; Amaral, E.M.

2000-01-01

This work reports on the occupational radiation doses for external radiation received in 1994-1998 by the radiation workers monitored by the Radiological Protection and Nuclear Safety Department (DPRSN) in Portugal. Individual monitoring for external radiation is carried out in Portugal by DPRSN since the 60s, and the workers are monitored on a monthly or quarterly bases. In 1995 DPRSN monitored approximately 8000 people and was the only laboratory carrying out this sort of activity in Portugal. In 1998 the number of monitored people increased to nearly 8500 from 860 facilities, which leads us to state that the results shown in this work are well representative of the universe of radiation workers in Portugal. Until 1996, the dose measurement procedure was based only on film dosimetry and the results reported for the 1994-1995 period were obtained with this methodology. Since 1996, thermoluminescent dosimetry (TLD) was gradually introduced and since then an effort has been made to transfer the monitored workers from film to TLD. In 1998, both film and TLD dosimetry systems were running simultaneously, with average numbers of 4500 workers monitored with film dosimetry, while 4000 were monitored with TLD. The data presented from 1996 to 1998 were obtained with both methodologies. This work reports the annual mean effective doses received from external radiation, for the monitored and exposed workers in the different fields of activity, namely, industry, research laboratories, health and mining. The distribution of the annual effective dose by dose intervals is also reported. The collective annual dose by field of activity is estimated and the contribution to the total annual collective dose is determined. The collective dose estimates for the period 1994 to 1998 demonstrated that the health sector is the most representative exposed group in Portugal. (author)

Dose-response relationships for female radium dial workers: A new look

International Nuclear Information System (INIS)

Rowland, R.E.

1994-01-01

The values of initial systemic intake and of skeletal dose for all of the U.S. radium cases have recently been revised. This revision was required following the demonstrations by Rundo and by Keane that humans who were exposed to radium as adults lost radium at a rate that depended on the quantity of radium originally deposited within their bodies. These new values have been used to define new dose-response relationships for both the bone sarcomas and the carcinomas arising in the paranasal sinuses and mastoid air cells induced by internally deposited radium. The population examined was employed in the U.S. dial painting industry prior to 1950 and consisted of 1530 female dial workers for whom radium body burden measurements were available. By the end of 1990, 46 cases of bone sarcomas and 19 cases of head carcinomas had been diagnosed in this cohort. The head carcinoma incidence can be adequately fitted by a simple linear function, as was found in previous analyses. The bone sarcoma cases were previously fitted by a dose-squared-exponential function. With the revised values of systemic intake, the sarcoma results could not be satisfactorily fitted with this expression. When the exponent on D was increased to larger values, excellent fits were obtained

The "toxic dose" of system problems: why some injured workers don't return to work as expected.

Science.gov (United States)

MacEachen, Ellen; Kosny, Agnieszka; Ferrier, Sue; Chambers, Lori

2010-09-01

Introduction Most workers who incur an injury on the job follow a relatively straightforward path through a workers' compensation claim, recovery and return to work. However, a minority of compensation claims is prolonged and can be disproportionately costly. We conducted this qualitative study in order to gain an understanding of systemic, process-related problems affecting injured workers who had failed to return to work as expected. Method A total of 69 in-depth interviews were conducted with injured workers with complex and extended workers' compensation claims and with return-to-work (RTW) providers such as health care providers, insurers, legal advisors, and workplaces. The study was based in Ontario, Canada. A modified grounded theory analysis led to the identification of common mechanisms in RTW problems. Results We identify problems with return to work and extended workers' compensation claims in dysfunctions in organizational dynamics across RTW systems including the workplace, healthcare, vocational rehabilitation and workers' compensation. These system problems are difficult to identify because they appear as relatively mundane and bureaucratic. These appeared to have damaging effects on workers in the form of a 'toxic dose' affecting the worker beyond the initial injury. Conclusions Worker's problems with extended claims were linked to RTW policies that did not easily accommodate conflict or power imbalances among RTW parties and by social relations and processes that impeded communication about RTW situations and problems. Avenues for intervention are located in a shift to a critical lens to RTW process that addresses differences of knowledge, resources, and interests among different parties.

Determination of the dose and dose distribution in radiation-linked polyolefins

International Nuclear Information System (INIS)

Andress, B.; Fischer, P.; Repp, H.H.; Roehl, P.

1984-01-01

The method serves the determination of the radiation dose and dose distribution in polyolefins cross-linked by electron beams; the cross-linking takes place in the presence of an additive which is inserted in the polyolefin by radiation. After the cross-linking the fraction of the additive which is not inserted will be extracted from the polyolefin and afterwards the total extinction of the polyolefin will be determined by photometry. This process allows in particular the determination of the quality of the irradiation conditions for the electron-beam cross-linking of medium-voltage cables insulated by polyolefins. (orig.) [de

Actions taken in order to reduce doses to workers in PWR power plants

International Nuclear Information System (INIS)

Jeanson, P.

1978-01-01

The dose limitation for workers in nuclear power plants is a permanent aim of Electricite de France. Many ways are followed at the same time to reach it, some of them in collaboration with C.E.A. Theoretical studies concern mostly sources and transfers of corrosion and fission products in the primary circuit of pressurized water reactors as well as the means for reducing the deposited activity. Practical studies concern design problems for equipment and buildings. They try to specify rules for these purposes. They also concern maintenance conditions of all components: for the most important components, special tools are designed. At last, studies and experimentation of daily dosimetry should bring a better knowledge of the distribution of collective doses and, subsequently, should give a better idea of the actions to be undertaken [fr

Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Hoover, M.D.; Farrell, R.F. [DOE, Carlsbad, NM (United States); Newton, G.J.

1995-12-01

The recent 1995 WIPP Safety Analysis Report (SAR) Update provided detailed analyses of potential radiation doses to members of the public at the site boundary during postulated accident scenarios at the U.S. Department of Energy`s Waste Isolation Pilot Plant (WIPP). The SAR Update addressed the complete spectrum of potential accidents associated with handling and emplacing transuranic waste at WIPP, including damage to waste drums from fires, punctures, drops, and other disruptions. The report focused on the adequacy of the multiple layers of safety practice ({open_quotes}defense-in-depth{close_quotes}) at WIPP, which are designed to (1) reduce the likelihood of accidents and (2) limit the consequences of those accidents. The safeguards which contribute to defense-in-depth at WIPP include a substantial array of inherent design features, engineered controls, and administrative procedures. The SAR Update confirmed that the defense-in-depth at WIPP is adequate to assure the protection of the public and environment. As a supplement to the 1995 SAR Update, we have conducted additional analyses to confirm that these controls will also provide adequate protection to workers at the WIPP. The approaches and results of the worker dose assessment are summarized here. In conformance with the guidance of DOE Standard 3009-94, we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposures under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR Update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, members of the public, and the environment.

Influences of mechanical exposure biographies on physical capabilities of workers from automotive industry - a study on possible dose-response relationships and consequences for short and long term job rotation.

Science.gov (United States)

Rademacher, Holger; Bruder, Ralph; Sinn-Behrendt, Andrea; Landau, Kurt

2012-01-01

This paper describes a field study in production areas of a vehicle manufacturing plant, where 106 male workers (aged from 20 to 63 years) were examined and interviewed by the authors. Aim of study was to identify relationships between specific physical worker capabilities and doses of mechanical exposures using self-developed standardized questionnaires as well as a battery of work-specific tests. The dependent variables are different "physical capabilities", classified using a five-point rating scale with regard to the grade of limitation of the respective capability. Independent variables are "age" and specific "mechanical exposures". Several exposures were combined and multiplied with their respective durations in order to determine doses on three different body regions - back, shoulder-neck and upper limbs. There are significant positive correlations between "age" and "dose of mechanical exposure on back/shoulder-neck/upper limbs region". The analysis of the relationship between dose of exposure and different capabilities to lift or reposition loads (with variable weight) shows weak significant correlations for all three body regions. Data analysis shows no significant correlations between any dose of mechanical exposure and capabilities to work in awkward body postures.These results should be considered in age management programs when scheduling future employee assignments to workplaces, especially for production systems where manual handling tasks are dominant.

Determination of albumin adducts of 4,4'-methylenediphenyl diisocyanate after specific inhalative challenge tests in workers.

Science.gov (United States)

Sabbioni, Gabriele; Dongari, Nagaraju; Kumar, Anoop; Baur, Xaver

2016-10-17

4,4'-Methylenediphenyl diisocyanate (MDI) is the most important isocyanate used in the industry. Lung sensitization with bronchial asthma is the main disorder in exposed workers. Albumin adducts of MDI might be involved in specific immunological reactions. MDI adducts with lysine (MDI-Lys) of albumin have been found in MDI-workers and construction workers. MDI-Lys is an isocyanate-specific adduct of MDI with albumin. In the present study, we report MDI-adducts in workers undergoing diagnostic MDI challenge tests. The workers were exposed for 2h to 5ppb of MDI. The adduct levels increase significantly after the exposure to MDI in the challenge chamber. About 0.6% of the dose was bound to albumin. So far, only urinary metabolites of MDI were measured to monitor isocyanate workers. However, such urinary metabolites are not isocyanate specific. Therefore, we propose to measure albumin adducts for monitoring MDI exposed subjects. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Study of radiation dose from radioactive shipments to cargo handlers at O'Hare Field

International Nuclear Information System (INIS)

1975-06-01

The relationship between the amount of radioactive materials that pass through the cargo areas at O'Hare Field, Chicago, and the resulting radiation dose to the workers handling the packages was determined. Measurements of radiation exposure rates at various distances from the radioactive packages were made. Handling or exposure times for personnel during several unit operations were measured with a watch. These data were used to determine the body dose from the unit operation. In randomly selected cases workers were assigned TLD dosimeters in the form of a ring to be worn on the hand or in the form of a clip to be attached to the clothing for measurement of the hand or body dose from a unit operation. During each survey, several workers were given TLDs that were worn for the duration of the shift, and some workers, in addition, were given dosimeters to be worn for the duration of the study. Results showed that the workers who handled the radioactive packages did not receive any significant radiation exposure. (U.S.)

MONITORING OF INDIVIDUAL DOSES FOR MEDICAL WORKERS OF DENTAL POLYCLINIC’S X-RAY ROOMS IN DUSHANBE, THE REPUBLIC OF TADJIKISTAN

Directory of Open Access Journals (Sweden)

N. U. Hakimova

2016-01-01

Full Text Available The article presents the data and analyses of personnel’s average annual external exposure doses monitoring via the thermoluminescent dosimetry method used for X-ray radiological personnel in dental polyclinics of Dushanbe, Tadjikistan Republic over a 5-year period ( 2010–2014 . Out of 42 registered medical institutions dental polyclinics amounted up to only just 14%. For this work thermoluminescent dosimeters were used ( with LiF: Mg, Ti with the thermoluminescent dosimetric installation “ Harshaw – 4500” as the reader device. Monitoring results comparison of individual dose equivalent Hp ( 10 values was conducted for two groups of medical workers: medical doctors and X-ray lab technicians. It is demonstrated that radiological technicians’ professional exposure doses are on the average by 23% higher than those for medical doctors.The average individual exposure doses over the above indicated period amount to 0,93 mSv and 1,3 mSv for doctors and X-ray lab technicians, respectively, and are in the range from 0,45 mSv to 2,39 mSv. The doses include contribution from the natural background. The values of doses recorded for the personnel in dental polyclinic correspond to those recorded for the workers in the routine X-ray rooms.

A trial of a job-specific workers' health surveillance program for construction workers: study protocol.

Science.gov (United States)

Boschman, Julitta S; van der Molen, Henk F; van Duivenbooden, Cor; Sluiter, Judith K; Frings-Dresen, Monique H W

2011-09-29

Dutch construction workers are offered periodic health examinations. This care can be improved by tailoring this workers health surveillance (WHS) to the demands of the job and adjust the preventive actions to the specific health risks of a worker in a particular job. To improve the quality of the WHS for construction workers and stimulate relevant job-specific preventive actions by the occupational physician, we have developed a job-specific WHS. The job-specific WHS consists of modules assessing both physical and psychological requirements. The selected measurement instruments chosen, are based on their appropriateness to measure the workers' capacity and health requirements. They include a questionnaire and biometrical tests, and physical performance tests that measure physical functional capabilities. Furthermore, our job-specific WHS provides occupational physicians with a protocol to increase the worker-behavioural effectiveness of their counselling and to stimulate job-specific preventive actions. The objective of this paper is to describe and clarify our study to evaluate the behavioural effects of this job-specific WHS on workers and occupational physicians. The ongoing study of bricklayers and supervisors is a nonrandomised trial to compare the outcome of an intervention (job-specific WHS) group (n = 206) with that of a control (WHS) group (n = 206). The study includes a three-month follow-up. The primary outcome measure is the proportion of participants who have undertaken one or more of the preventive actions advised by their occupational physician in the three months after attending the WHS. A process evaluation will be carried out to determine context, reach, dose delivered, dose received, fidelity, and satisfaction. The present study is in accordance with the TREND Statement. This study will allow an evaluation of the behaviour of both the workers and occupational physician regarding the preventive actions undertaken by them within the scope of a job

Outlines of a study of some indicators of exposure of underground workers to radon in Slovakia

Energy Technology Data Exchange (ETDEWEB)

Beno, M; Nikodemova, D; Vladar, M; Fueloep, M; Vicanova, M [Inst. of Preventive and Clinical Medicine, Bratislava (Slovakia)

1996-12-31

In this paper some indicators of exposure of underground workers to radon in Slovakia which will be used for determination of miners radiation burden and for the radon dose estimate was explained. The projected study has a dose-effect scaffold and its projected goals are on the side of dose assessment: 1) to determine the professional exposure of underground workers to radon by personal dosimetry and to establish a database of integrated personal doses for future epidemiological studies; 2) to introduce the method of counting the radionuclide {sup 210}Pb in the bones and skulls of underground workers. On the side of effect assessment the goals are: 1) to find out if a dependence of the number of chromosomal aberrations (CA) and micronuclei in the lymphocytes from radon dose exists. The measurements of radon in mines, preferentially those by personal dosimeters as well as an existing database of radon concentration measurements in dwellings and caves will serve for the radon dose estimate; 2) to compare the DNA-repair rate in the lymphocytes of people professionally exposed to radon in Slovak caves with the same rate as assessed in unexposed people; 3) to find out the proportional role of confounding factors such as smoking, alcohol abuse, exposure to dust etc., which might influence upon the interpretation of the dose from radon to health response relationship; 4) to establish a central database of lung cancer cases in professionally exposed underground workers for future epidemiological studies. The direct method will rely upon determination of miners radiation burden based on the {sup 210}Pb activity deposited in skeleton. The experimental design to assess the effects will have three main methodological parts: 1) determination of the count of chromosomal aberrations and micronuclei using classical methods; 2) determination of the chromosomal changes using the fluorescent in situ hybridization method; 3) determination of the DNA-repair rate. (J.K.) 8 refs.

Determinants and consequences of health worker motivation in hospitals in Jordan and Georgia.

Science.gov (United States)

Franco, Lynne Miller; Bennett, Sara; Kanfer, Ruth; Stubblebine, Patrick

2004-01-01

Health worker motivation reflects the interactions between workers and their work environment. Because of the interactive nature of motivation, local organizational and broader sector policies have the potential to affect motivation of health workers, either positively or negatively, and as such to influence health system performance. Yet little is known about the key determinants and outcomes of motivation in developing and transition countries. This exploratory research, unique in its broader study of a whole range of motivational determinants and outcomes, was conducted in two hospitals in Jordan and two in Georgia. Three complementary approaches to data collection were used: (1) a contextual analysis; (2) a qualitative 360-degree assessment; and (3) a quantitative in-depth analysis focused on the individual determinants and outcomes of the worker's motivational process. A wide range of psychometric scales was used to assess personality differences, perceived contextual factors and motivational outcomes (feelings, thoughts and behaviors) on close to 500 employees in each country. Although Jordan and Georgia have very different cultural and socio-economic environments, the results from these two countries exhibited many similarities among key determinants: self-efficacy, pride, management openness, job properties, and values had significant effects on motivational outcomes in both countries. Where results were divergent, differences between the two countries highlight the importance of local culture on motivational issues, and the need to tailor motivational interventions to the specific issues related to particular professional or other groupings in the workforce. While workers themselves state that financial reward is critical for their work satisfaction, the data suggest a number of non-financial interventions that may be more effective means to improve worker motivation. This research highlights the complexity of worker motivation, and the need for a more

Response of human lymphocytes to low gamma ray doses

International Nuclear Information System (INIS)

Vega Carrillo, HR; Banuelos Valenzuela, R; Manzanares Acuna, E; Sanchez-Rodriguez, S.H

2001-01-01

Radiation and non-radiation workers lymphocytes were exposed to a low strength gamma-ray field to determine heat shock protein expression in function of radiation dose. Protein identification was carried out using mAb raised against Hsp25, Hsp60, Hsp70 and Hsp90; from these, only Hsp70 protein was detected before and after lymphocyte irradiation. In all cases, an increasing trend of relative amounts of Hsp70 in function to irradiation time was observed. After 70.5 mGy gamma-ray dose, radiation worker's lymphocytes expressed more Hsp70 protein, than non-radiation workers' lymphocytes, indicating a larger tolerance to gamma rays (gamma tolerance), due to an adaptation process developed by their labor condition (Au)

Analysis of female radiation workers dose records in the DAE Units of Andhra Pradesh

International Nuclear Information System (INIS)

Padma Savitri, P.; Kamble, M.K.; Reddy, K.S.

2010-01-01

Basis for control of occupational exposures of women is same as that of men except for pregnant women. Percentage of women working in radiation areas of DAE has marginally increased in the last three decades. This paper analysed the data on the externally received personal dose equivalent for female radiation workers who have been exposed ti ionizing radiation in different occupations of DAE units in Andhra Pradesh. From this study we can say confidently that it is equally safe for women to work in radiation areas as long as they follow radiation protection principles. Hence, women in India should be made aware that it is safe to work in radiation areas and DAE is taking their care by periodical medical checkups, maintaining dose records, etc

World Council of Nuclear Workers (WONUC). Report of the 1st international Conference

International Nuclear Information System (INIS)

Domel, R.

1999-08-01

This, the first conference organised by WONUC, attracted papers dealing with many aspects of low and very low doses of ionising radiation, including molecular and genetic aspects and epidemiological studies. There was a lively debate on the 'linear no threshold' model and on whether Hiroshima/Nagasaki data should still be used to determine dose limits for workers and the general public. The conference highlighted the growing scientific understanding and debate of effects of low and very low doses of ionising radiation and it is important that workers in Australia should have first-hand access to this information. Indeed, if in years to come radiation hormesis is demonstrated, workers should be made aware of that possibility and the fact that their place of employment may hold an additional health benefit rather than a reputed health risk. I believe that such a positive attitudinal shift would certainly help nuclear workers to counter the ever-present negative sentiments of the anti-nuclear lobby groups

Occupational Doses and the Contribution to the Population Dose in Korea

Energy Technology Data Exchange (ETDEWEB)

Han, Seung Jae; Kyu, Hwan Jeong [KINS, Daejeon (Korea, Republic of)

2016-05-15

The purpose of this study is to evaluate the occupational exposure records in terms of the control of exposure for radiation workers and dose reduction. The study includes the estimates of the number of people exposed occupationally, the effective collective doses and mean doses to those exposed. In addition, the study includes an estimate of the contribution of occupational exposure to the Korean population dose. The exposure of radiation workers in occupational field includes medical radiology, industrial applications such as radiography, nuclear power, and some research activities. Occupational exposure from medical radiology practices includes the contributions from diagnostic x-ray procedures, dental radiography, nuclear medicine and radiation therapy. The control of exposure for radiation workers, and the measures necessary to maintain radiation exposure as low as reasonably achievable (ALARA) are specified in Subparagraph 3 and Subparagraph 4 of Article 91 (1) of the Korea Nuclear Safety Act (KNSA), respectively. Therefore, from a regulatory perspective, the exposure data of the workers are primarily for verification of the adequacy of the control of exposure, radiation protection and implementation of ALARA. The number of people exposed occupationally, the effective collective doses and mean doses to those exposed, and average effective doses from occupational exposure during the period of 2009 to 2013 have been evaluated. In general, radiation workers were increasing in number annually, but the mean doses for those exposed each year showed the control of exposures were mostly considered met within the dose limit in KNSA. Nevertheless, it was shown that the continuous efforts would be needed to reduce doses and thus to implement ALARA regulatory requirements. In radiation occupations, the application of ICRP radiation protection principles will ensure good practice and decreasing exposures. Over the period of 5 years, the contributions of the annual

Occupational Doses and the Contribution to the Population Dose in Korea

International Nuclear Information System (INIS)

Han, Seung Jae; Kyu, Hwan Jeong

2016-01-01

The purpose of this study is to evaluate the occupational exposure records in terms of the control of exposure for radiation workers and dose reduction. The study includes the estimates of the number of people exposed occupationally, the effective collective doses and mean doses to those exposed. In addition, the study includes an estimate of the contribution of occupational exposure to the Korean population dose. The exposure of radiation workers in occupational field includes medical radiology, industrial applications such as radiography, nuclear power, and some research activities. Occupational exposure from medical radiology practices includes the contributions from diagnostic x-ray procedures, dental radiography, nuclear medicine and radiation therapy. The control of exposure for radiation workers, and the measures necessary to maintain radiation exposure as low as reasonably achievable (ALARA) are specified in Subparagraph 3 and Subparagraph 4 of Article 91 (1) of the Korea Nuclear Safety Act (KNSA), respectively. Therefore, from a regulatory perspective, the exposure data of the workers are primarily for verification of the adequacy of the control of exposure, radiation protection and implementation of ALARA. The number of people exposed occupationally, the effective collective doses and mean doses to those exposed, and average effective doses from occupational exposure during the period of 2009 to 2013 have been evaluated. In general, radiation workers were increasing in number annually, but the mean doses for those exposed each year showed the control of exposures were mostly considered met within the dose limit in KNSA. Nevertheless, it was shown that the continuous efforts would be needed to reduce doses and thus to implement ALARA regulatory requirements. In radiation occupations, the application of ICRP radiation protection principles will ensure good practice and decreasing exposures. Over the period of 5 years, the contributions of the annual

Wide-range neutron dose determination with CR-39

International Nuclear Information System (INIS)

Arneja, A.R.; Waker, A.J.

1995-01-01

Optical density measurements of CR-30 irradiated with 252 Cf neutrons and chemically etched with 6.5 N KOH solution have been used to determine neutron absorbed doses between 0.1 and 10 Gy. Optimum etching conditions will depend upon the absorbed dose. Since it is not always possible to know the range of absorbed dose on a CR-39 dosemeter collected from personnel and area monitor stations in a criticality accident situation, a three-step two-hour chemical etch at 60 o C has been found to be appropriate. If after a total of six hours of chemical etching the optical density is found to be below 0.04 for 500 nm light (transmission > 90%) then further treatment in the form of electrochemical etching can be carried out to determine the lower absorbed dose. In this manner, absorbed doses below 0.1 Gy can be determined by counting tracks over a unit area. (author)

Dose-rate determination by radiochemical analysis

International Nuclear Information System (INIS)

Mangini, A.; Pernicka, E.; Wagner, G.A.

1983-01-01

At the previous TL Specialist Seminr we had suggested that α-counting is an unsuitable technique for dose-rate determination due to overcounting effects. This is confirmed by combining α-counting, neutron activation analysis, fission track counting, α-spectrometry on various pottery samples. One result of this study is that disequilibrium in the uranium decay chain alone cannot account for the observed discrepancies between α-counting and chemical analysis. Therefore we propose for routine dose-rate determination in TL dating to apply chemical analysis of the radioactive elements supplemented by an α-spectrometric equilibrium check. (author)

Determination of dose equivalent and risk in thorium cycle

International Nuclear Information System (INIS)

Ney, C.L.V.N.

1988-01-01

In these report are presented the calculations of dose equivalent and risk, utilizing the dosimetric model described in publication 30 of the International Comission on Radiological Protection. This information was obtained by the workers of the thorium cycle, employed at the Praia and Santo Amaro Facilities, by assessing the quantity and concentration of thorium in the air. The samples and the number of measurements were established through design of experiments techniques, and the results were evaluated with the aid of variance analysis. The estimater of dose equivalent for internal and external radiation exposure and risk associated were compared with the maximum recommended limits. The results indicate the existence of operation areas whose values were above those limits, requiring so an improvement in the procedures and services in order to meet the requirements of the radiological protetion. (author) [pt

Identification and analysis of main radionuclides that potentially contribute to the internal dose for workers at radiopharmacy facilities

International Nuclear Information System (INIS)

Sanches, Matias Puga

2004-01-01

The optimization principle in radiation protection means that there is a reasonable balance between resources used to monitor exposures and the benefits due to the monitoring program. Programs for the monitoring of workers handling radioactive materials are influenced by numerous factors. Estimation of internal doses due to inhalation or ingestion of radioactive materials is often based on measurements of the activity in the tissues of the body and in excreta, following a given intake. In order to enable dose estimations using the biokinetic models recommended by the ICRP and laboratory data, it is proposed to carry out comprehensive study to identify the main radionuclides that potentially contribute to the internal dose of workers at radiopharmacy facilities. The applied methodology for identification of these radionuclides takes into account criteria set out by the ICRP and IAEA. The practical purpose to set up this study was to establish a consistent approach to ensure that the dose assessments are as simple as possible and guarantee the necessary quality standards. The result of this study has indicated the requirement of routine measurements for seven radionuclides over all range of radioactive material compounds, handled at the radiopharmacy plant of IPEN, avoiding unjustifiable work concerning activity levels that are not relevant for the health of the occupationally exposed persons. The main intake pathways, the appropriate monitoring frequencies and derived reference level have also been identified. (author)

Ionizing radiation dose control for workers in a nuclear plant working with unsealed sources; Controle da dose de radiacao ionizante para trabalhadores em uma instalacao radiativa com fontes nao seladas

Energy Technology Data Exchange (ETDEWEB)

Gerulis, Eduardo

2006-07-01

With the liberation of the use of the nuclear energy for peaceful applications, International Commission Radiological Protection, ICRP, founded in 1928, created a system of protection of the undesirable doses of ionizing radiation in 1958. This has been received by workers, members of the public and environment and hence it became possible for the introduction of these applications. This protection system is adopted by the International Agency of Energy Atomic, IAEA, that publishes recommendations in safety series, 88 and by the Comissao Nacional de Energia Nuclear, CNEN, which publishes these regulations. The international recommendations and national regulations were adapted and they need to be applied in this way. The present paper uses recommendations of the publication 75 from ICRP, of the publication 115 from 88 and regulations of the regulation NN 3.01 from CNEN to present, through radiological protection measures, the ionizing radiation dose control for workers in a nuclear plant that works in the research, production, division and packing of unsealed sources to be used in clinical applications. In that way it is possible to prevent appropriately the undesirable doses and to confirm the received doses. (author)

76 FR 35476 - Notice of Determinations Regarding Eligibility To Apply for Worker Adjustment Assistance and...

Science.gov (United States)

2011-06-17

...' industry (i.e., conditions within the industry are adverse). Affirmative Determinations for Worker...' industry are not adverse. None. Negative Determinations for Worker Adjustment Assistance and Alternative...,095; 6ixSigma Apparel Network, LLC, New York, NY. The investigation revealed that criteria of Section...

Determination of isocyanate specific albumin-adducts in workers exposed to toluene diisocyanates.

Science.gov (United States)

Sabbioni, Gabriele; Gu, Qi; Vanimireddy, Lakshiminiranjan Reddy

2012-03-01

Toluene diisocyanates (2,4-TDI and 2,6-TDI) are important intermediates in the chemical industry. Among the main damages after low levels of TDI exposure are lung sensitization and asthma. It is therefore necessary to have sensitive and specific methods to monitor isocyanate exposure of workers. Urinary metabolites or protein adducts have been used as biomarkers in workers exposed to TDI. However, with these methods it was not possible to determine if the biomarkers result from exposure to TDI or to the corresponding toluene diamines (TDA). This work presents a new procedure for the determination of isocyanate-specific albumin adducts. Isotope dilution mass spectrometry was used to measure the adducts in albumin present in workers exposed to TDI. 2,4-TDI and 2,6-TDI formed adducts with lysine: N(ϵ)-[({3-amino-4-methylphenyl}amino)carbonyl]-lysine, N(ϵ)-[({5-amino-2-methylphenyl}amino)carbonyl]-lysine, and N(ϵ)- [({3-amino-2-methylphenyl}amino)carbonyl]-lysine. In future studies, this new method can be applied to measure TDI-exposures in workers.

Determinants of Chronic Respiratory Symptoms among Pharmaceutical Factory Workers

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Sahle Asfaw

2018-01-01

Full Text Available Background. Chronic respiratory symptoms including chronic cough, chronic phlegm, wheezing, shortness of breath, and chest pain are manifestations of respiratory problems which are mainly evolved as a result of occupational exposures. This study aims to assess determinants of chronic respiratory symptoms among pharmaceutical factory workers. Methods. A case control study was carried out among 453 pharmaceutical factory workers with 151 cases and 302 controls. Data was collected using pretested and structured questionnaire. The data was analyzed using descriptive statistics and bivariate and multivariate analysis. Result. Previous history of chronic respiratory diseases (AOR = 3.36, 95% CI = 1.85–6.12, family history of chronic respiratory diseases (AOR = 2.55, 95% CI = 1.51–4.32, previous dusty working environment (AOR = 2.26, 95% CI = 1.07–4.78, ever smoking (AOR = 3.66, 95% CI = 1.05–12.72, and service years (AOR = 1.86, 95% CI = 1.16–2.99 showed statistically significant association with chronic respiratory symptoms. Conclusion. Previous history of respiratory diseases, family history of chronic respiratory diseases, previous dusty working environment, smoking, and service years were determinants of chronic respiratory symptoms. Public health endeavors to prevent the burden of chronic respiratory symptoms among pharmaceutical factory workers should target the reduction of adverse workplace exposures and discouragement of smoking.

Threat of Deportation as Proximal Social Determinant of Mental Health Amongst Migrant Workers.

Science.gov (United States)

Harrigan, Nicholas M; Koh, Chiu Yee; Amirrudin, Amirah

2017-06-01

While migration health studies traditionally focused on socioeconomic determinants of health, an emerging body of literature is exploring migration status as a proximate cause of health outcomes. Study 1 is a path analysis of the predictors of mental health amongst 582 documented migrant workers in Singapore, and shows that threat of deportation is one of the most important proximate social determinants of predicted mental illness, and a mediator of the impact of workplace conflict on mental health. Study 2 is a qualitative study of the narratives of 149 migrant workers who were in workplace conflict with their employers, and demonstrates that workers believed threats were used as a negotiating strategy during workplace conflicts. Findings suggest that migration status places workers who come into workplace conflict with their employers at heightened risk of mental illness because migration status can be used as a tool by employers in workplace negotiations.

Determinants Of Job Satisfaction Of Field Extension Workers In ...

African Journals Online (AJOL)

Factor analysis was used to isolate the determinants of job satisfaction of field extension workers in Enugu State Agricultural Development Programme. Data was collected from 42 randomly selected respondents with the aid of structured questionnaire. Findings of the study showed that majority (about 58%) of the ...

Determination of effective dose of antimalarial from Cassia ...

African Journals Online (AJOL)

However, further investigation is required to determine an effective dose of the administered extract for a higher inhibitory effect and increasing effectiveness of the extract. Material and Methods: To determine the effective dose of ethanol extract of C. spectabilis leaves, a "4-day suppressive test"of Peter was performed with ...

Identification of occupational mortality risks for Hanford workers

International Nuclear Information System (INIS)

Kneale, G.W.; Mancuso, T.F.; Stewart, A.M.

1984-01-01

Though most of the production work at Hanford is done by manual workers, 46% of the most dangerous jobs are performed by people who have professional or technical qualifications. For these privileged workers occupational mortality risks are positively correlated with radiation doses but for manual workers, who have relatively high death rates, there is an inverse relation with dose. The high ratio of professional to manual workers is clearly the reason for the industry having fewer observed than expected deaths and the inverse relation with dose for less privileged workers is probably a sign that there has been selective recruitment of the most highly paid manual workers-that is, skilled craftsmen into the more dangerous occupations. Evidence of this selective recruitment was obtained by equating danger levels with levels of monitoring for internal radiation. Therefore, there should be some control for these levels in any analysis of cancer effects of the measured dose of radiation. (author)

Air contamination measurements for the evaluation of internal dose to workers in nuclear medicine departments

Science.gov (United States)

De Massimi, B.; Bianchini, D.; Sarnelli, A.; D'Errico, V.; Marcocci, F.; Mezzenga, E.; Mostacci, D.

2017-11-01

Radionuclides handled in nuclear medicine departments are often characterized by high volatility and short half-life. It is generally difficult to monitor directly the intake of these short-lived radionuclides in hospital staff: this makes measuring air contamination of utmost interest. The aim of the present work is to provide a method for the evaluation of internal doses to workers in nuclear medicine, by means of an air activity sampling detector, to ensure that the limits prescribed by the relevant legislation are respected. A continuous air sampling system measures isotope concentration with a Nal(TI) detector. Energy efficiency of the system was assessed with GEANT4 and with known activities of 18F. Air is sampled in a number of areas of the nuclear medicine department of the IRST-IRCCS hospital (Meldola- Italy). To evaluate committed doses to hospital staff involved (doctors, technicians, nurses) different exposure situations (rooms, times, radionuclides etc) were considered. After estimating the intake, the committed effective dose has been evaluated, for the different radionuclides, using the dose coefficients mandated by the Italian legislation. Error propagation for the estimated intake and personal dose has been evaluated, starting from measurement statistics.

Determination of sterilizing dose of lincocine drug

International Nuclear Information System (INIS)

Adawi, M.A.; Shamma, M.; Al-Mousa, A.

1998-01-01

There are too many antibiotics that have been studied on their dry solid state to determine their safe sterilizing dose by decreasing their bio burden in order to reach the sterility assurance level (SAL) needed. The sterilizing radiating dose of lincocine was determined according to information about their bio burden and radiating sensitivity at the sterility assurance level 10-6. The study of bio burden has shown that the contamination was fungal (Pemicillium sp.) and by applying the same tests to the raw materials of lincocine it came out that the cause of contamination was bad storage and that the radiating dose required to decrease the bio burden was 5.5 kGy. (author)

An influence of occupational exposure on level of chromosome aberrations in nuclear power plant workers

International Nuclear Information System (INIS)

Birute Griciene; Grazina Slapsyte

2007-01-01

analyzed for chromosome aberrations. Results. Chromosome aberration analyses revealed significant increase in the total chromosome aberration frequency for the radiation workers with internal exposure (2.42±0.40 CA/100 cells, P=0.01) and for those with additional neutron exposure (2.63±0.40 CA/100 cells, P=0.01). However, no significant differences between the workers with external gamma radiation exposure and the controls (1.62±0.25 vs. 1.65±0.15 CA/100 cells, P=0.83) was observed. There was no correlation between the chromosome aberration frequency and the cumulative dose, mean annual doses averaged over the last 3-years or the last year before the blood sampling. The confounding effects of internal and neutron exposure on the frequency of chromosome aberrations was determined. The impact of other factors (smoking habits, age, duration of employment, cumulative dose) was found to be not significant. Conclusion. Though no increase in chromosome aberration frequency was determined in workers exposed to external gamma radiation only, the demonstration of the elevated levels of chromosome aberrations in the workers with incorporated radionuclides and neutron exposure indicates their more hazardous work activities with consequential risk to health.

Individual doses' register of occupationally exposed persons in the Republic of Moldova

International Nuclear Information System (INIS)

Hustuc, A.; Chiruta, Iu.

2009-01-01

The storage and processing of the data acquired through different monitoring techniques are of vital importance for controlling the individual doses of the occupationally exposed workers facilitating the determination of exposure pathway and furthering the policy of radiological protection. The use of the data bases for the evidence of the individual doses of the occupationally exposed workers to the ionizing radiation is useful in studies of risks and potential exposure, and in future epidemiological studies. (authors)

Impact of social determinants on well-being of urban construction workers of Hyderabad.

Science.gov (United States)

Bala, Sudha; Valsangkar, Sameer; Lakshman Rao, Reshaboyina Lakshmi Narayana; Surya Prabha, Manem Lakshmi

2016-01-01

Hyderabad has witnessed one of the largest labor immigration in recent years and these construction workers are highly vulnerable in terms of health. Social determinants of health (SDH) arise from conditions in which they live and these factors interact with each other to produce direct impact on health. (1) To evaluate the sociodemographic and job characteristics of the construction workers. (2) To assess the impact of social determinants on well-being. A sample size of 135 construction workers working at three sites of HITEC city were interviewed using semi-structured questionnaire. Health perception and the impact on well-being was measured using the Healthy Days Module and Kessler's Psychological Distress Scale. SDH were measured on a 27-item questionnaire with responses on a Likert scale ranging from 0 to 4. Proportions, percentages, P values, and mean scores were obtained. The mean age of the sample was 35.4 ± 11.94 years. Seventeen (12.6%) of the workers reported a high risk score on the Kessler's Psychological Distress Scale. Binary logistic regression analysis was used to identify significant domains of social determinants independently associated with the well being of construction workers and significant among the nine domains of social determinants were addiction score domain with odds of 2.259 and a P value of 0.015 and the distress domain with odds of 1.108 and a P < 0.001. There is a significant impairment of physical and mental health due to various factors including SDH, such as addictive habits and psychological distress, which are amenable to prevention.

The consequences of a reduction in the administratively applied maximum annual dose equivalent level for an individual in a group of occupationally exposed workers

International Nuclear Information System (INIS)

Harrison, N.T.

1980-02-01

An analysis is described for predicting the consequences of a reduction in the administratively applied maximum dose equivalent level to individuals in a group of workers occupationally exposed to ionising radiations, for the situation in which no changes are made to the working environment. This limitation of the maximum individual dose equivalent is accommodated by allowing the number of individuals in the working group to increase. The derivation of the analysis is given, together with worked examples, which highlight the important assumptions that have been made and the conclusions that can be drawn. The results are obtained in the form of the capacity of the particular working environment to accommodate the limitation of the maximum individual dose equivalent, the increase in the number of workers required to carry out the productive work and any consequent increase in the occupational collective dose equivalent. (author)

A trial of a job-specific workers' health surveillance program for construction workers: study protocol

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Sluiter Judith K

2011-09-01

Full Text Available Abstract Background Dutch construction workers are offered periodic health examinations. This care can be improved by tailoring this workers health surveillance (WHS to the demands of the job and adjust the preventive actions to the specific health risks of a worker in a particular job. To improve the quality of the WHS for construction workers and stimulate relevant job-specific preventive actions by the occupational physician, we have developed a job-specific WHS. The job-specific WHS consists of modules assessing both physical and psychological requirements. The selected measurement instruments chosen, are based on their appropriateness to measure the workers' capacity and health requirements. They include a questionnaire and biometrical tests, and physical performance tests that measure physical functional capabilities. Furthermore, our job-specific WHS provides occupational physicians with a protocol to increase the worker-behavioural effectiveness of their counselling and to stimulate job-specific preventive actions. The objective of this paper is to describe and clarify our study to evaluate the behavioural effects of this job-specific WHS on workers and occupational physicians. Methods/Design The ongoing study of bricklayers and supervisors is a nonrandomised trial to compare the outcome of an intervention (job-specific WHS group (n = 206 with that of a control (WHS group (n = 206. The study includes a three-month follow-up. The primary outcome measure is the proportion of participants who have undertaken one or more of the preventive actions advised by their occupational physician in the three months after attending the WHS. A process evaluation will be carried out to determine context, reach, dose delivered, dose received, fidelity, and satisfaction. The present study is in accordance with the TREND Statement. Discussion This study will allow an evaluation of the behaviour of both the workers and occupational physician regarding the

Analysis of the external doses received by workers involved in the mitigation of the Goiania radiological accident

Energy Technology Data Exchange (ETDEWEB)

Mauricio, C.L.P., E-mail: claudia@ird.gov.br [Instituto de Radioproteção e Dosimetria, Rio de Janeiro, RJ (Brazil). Div. de Dosimetria

2017-07-01

In 1987, after identification that a stolen head of a Cs-137 radiotherapy irradiator was violated, it starts, in Goiania, the screening of the involved persons, the decontamination and the collection of the radiative waste. The contaminated areas were isolated and the professionals who worked within these areas received individual film monitors and TLD rings, provided by the Instituto de Radioproteção e Dosimetria (IRD), to evaluate their external dose. The aim of this paper is to present a statistical analysis of the external occupational doses received by this intervention staff. The used data were extracted from the Goiania accident database, maintained by IRD. A total of 1091 workers were monitored, some for only a few days and others for almost one year. All the total external occupational doses, received during these works, including the management of the radiative waste, were lower than the individual annual dose limit of 50 mSv for practices. Only one dose exceeded the value of 20 mSv. Their estimated mean effective doses were about 1.0 mSv, which is the annual dose limit for public exposure. About 80% of the doses were lower than this value. (author)

Determination of the dose equivalent Hp(0.07) in hands of occupationally exposed personnel in the practice of proton emission tomography (PET/CT)

International Nuclear Information System (INIS)

Lea, D.; Ruiz, N.; Esteves, L.

2006-01-01

In Venezuela recently it was implanted the Positron Emission Tomography technique (PET) with the perspective of implanting it at national level. Even when in our country practices it of nuclear medicine it exists from early of 70, there is not experience in the determination of the occupational doses by exposure to the external radiation in hands. By this reason, a concern exists in the workers of the centers of nuclear medicine where it is practiced the Positron Emission Tomography technique. In absence of the TLD dosimetry to measure dose in hands in our country, measurements of the dose equivalent of the workers of the PET national reference center were made, using a detector of hands type diode. It was determined the dose in hands in terms of dose equivalent Hp(0.07) in two work positions, that is: the corresponding to the transfer of the receiving vial of ( 18 F) FDG to the shield, quality control and uni doses division. The second work position corresponds the person in charge of administering, via intravenous, the ( 18 F) FDG. In this work it realizes the dose equivalent in hands Hp(0.07) measures in each one of the work positions before described by daily production. The informed doses correspond to a total average produced activity of 20.4 GBq (550 mCi). The results of the measurements in terms of dose equivalent in hands Hp(0.07) correspond to 2.1 ± 20% mSv in the work position of division and 0.4 ± 10% mSv in the position of injection of the radioactive material. At short term this foreseen until 4 productions per week, what means an annual dose equivalent Hp(0.07) in hands of 400 mSv approximately, without taking into account abnormal situations as its are spills of the ( 18 F) FDG in the work place. This work is the starting point so that the regulatory authority settles down, in Venezuela, dose restrictions in the PET practices and implant, in the centers of nuclear medicine, an optimization politics of this practice in conformity with the ALARA

Estimation of the individual and collective doses received by workers and the public during the transport of radioactive materials in france between 1981 and 1990

International Nuclear Information System (INIS)

Hamard, J.; Ringot, C.; Bernard, H.; Connat, R.; Lecoq, P.; Morin, P.

1993-01-01

The monitoring of the exposure of workers and the public during the transport of radioactive materials is complicated by the mobile nature of the sources and by the fact that, up to now, a large proportion of workers have not been considered to be at risk and their exposure has therefore not been the subject of surveillance. Likewise, in the case of the public, the mobile nature of the sources makes it difficult to define a critical group which could be the subject of dose evaluation. For this reason, the IAEA transport regulations recommend periodic evaluations of exposure to verify that it remains below an acceptable level, in accordance with the principle of optimization and to ensure that dose limits are complied with. In France, an inquiry covering the workers of the main companies engaged in the transport of radioactive materials has been conducted on a two-yearly basis since 1980, and the results have been published at each PATRAM meeting. This inquiry now spans a period of ten years (1980 to 1990) and it is possible to see how exposure has evolved as a function of the development of the French nuclear power programme and the consequent increase in a number of transport operations. As concerns the public, a comparison is made between the exposure levels estimated in the study and the exposure levels calculated by application of the RADTRAN model developed for the purpose by the IAEA. The results show the evolution of the maximum annual doses, the average doses and the collective doses received by workers during the transport of different radio-pharmaceutical and fuel cycle products, as well as the collective dose for the public during the period covered. (author)

CY 1995 radiation dose reconciliation report and resulting CY 1996 dose estimate for the 324 nuclear facility

International Nuclear Information System (INIS)

Landsman, S.D.; Thornhill, R.E.; Peterson, C.A.

1996-04-01

In this report, the dose estimate for CY 1995 is reconciled by month wih actual doses received. Results of the reconciliation were used to revise estimates of worker dose for CY 1996. Resulting dose estimate for the facility is also included. Support for two major programs (B-Cell Cleanout and Surveillance and Maintenance) accounts for most of the exposure received by workers in the faility. Most of the expousre received by workers comes from work in the Radiochemical Engineering Complex airlock. In spite of schedule and work scope changes during CY 1995, dose estimates were close to actual exposures received. A number of ALARA measures were taken throughout the year; exposure reduction due to those was 20.6 Man-Rem, a 28% reduction from the CY 1995 estimate. Baseline estimates for various tasks in the facility were used to compile the CY 1996 dose estimate of 45.4 Man-Rem; facility goal for CY 1996 is to reduce worker dose by 20%, to 36.3 Man-Rem

Computer-assisted resilience training to prepare healthcare workers for pandemic influenza: a randomized trial of the optimal dose of training

Directory of Open Access Journals (Sweden)

Vincent Leslie

2010-03-01

Full Text Available Abstract Background Working in a hospital during an extraordinary infectious disease outbreak can cause significant stress and contribute to healthcare workers choosing to reduce patient contact. Psychological training of healthcare workers prior to an influenza pandemic may reduce stress-related absenteeism, however, established training methods that change behavior and attitudes are too resource-intensive for widespread use. This study tests the feasibility and effectiveness of a less expensive alternative - an interactive, computer-assisted training course designed to build resilience to the stresses of working during a pandemic. Methods A "dose-finding" study compared pre-post changes in three different durations of training. We measured variables that are likely to mediate stress-responses in a pandemic before and after training: confidence in support and training, pandemic-related self-efficacy, coping style and interpersonal problems. Results 158 hospital workers took the course and were randomly assigned to the short (7 sessions, median cumulative duration 111 minutes, medium (12 sessions, 158 minutes or long (17 sessions, 223 minutes version. Using an intention-to-treat analysis, the course was associated with significant improvements in confidence in support and training, pandemic self-efficacy and interpersonal problems. Participants who under-utilized coping via problem-solving or seeking support or over-utilized escape-avoidance experienced improved coping. Comparison of doses showed improved interpersonal problems in the medium and long course but not in the short course. There was a trend towards higher drop-out rates with longer duration of training. Conclusions Computer-assisted resilience training in healthcare workers appears to be of significant benefit and merits further study under pandemic conditions. Comparing three "doses" of the course suggested that the medium course was optimal.

Determination of uranium in soil with emphasis on dose assessment

International Nuclear Information System (INIS)

Vidic, A.; Ilic, Z.; Deljkic, D.; Repinc, U.; Benedik, Lj.; Maric, S.

2005-01-01

Uranium is present naturally in the earth crust and has three isotopes with long half-lives. These isotopes are 2 38U (99.27% natural abundance), 2 35U (0.72% natural abundance) and 2 34U (0.006% natural abundance). Isotope 2 35U is a valuable fuel for nuclear power plants. During the manufacture of nuclear fuel the concentration of 2 35U is increased. Depleted uranium (DU) is a waste product of this enrichment process and typically contains about 99.8% 2 38U , 0.2% 2 35U and 0.0006% 2 34U in mass. Due to its high density and other physical properties, DU is used in munitions designed to penetrate armour plate. DU weapons were used during the Balkan war in Bosnia and Herzegovina. It was estimated, that nearly 10,000 projectiles were fired or 3 tonnes of DU used in BandH. The aim of this work was to determine uranium radioisotopes in soil and air collected in Hadzici (near Sarajevo). The investigated area is a former military base used for the production and maintenance of tanks and other heavy military vehicles. During a NATO attack in 1995, about 1,500 rounds were fired at the site. The specific activities of 2 38U found in soil ranged from 28 Bq/kg to 55 Bq/kg. We found higher specific activities in some foci, in the range from 143 Bq/kg to 810 Bq/kg. The specific activities of uranium isotopes in the air were determined using simple dust loading approach. The results served to calculate the annual effective dose that could be received by individual workers at the site and by general population from the surrounding area. Radioactivity measurements in the environment of Hadzici showed that the annual effective dose for general population was less than 20 micro Sv.(author)

Cytogenetic analysis for radiation dose assessment in the medical nuclear workers

International Nuclear Information System (INIS)

Milacic, S.; Jovicic, D.; Rakic, B.; Djokovic, J.

2009-01-01

Radionuclide is used in medicine for laboratory research, laboratory testing for enzymes, hormones, medicines in vitro and in vivo in nuclear medicine (NM) for the diagnosis and treatment of diseases. Commissioners, who performed the application radionuclide (RN), are nuclear medicine specialists, senior medical and radiological technicians, nurses and laboratory technicians. They are daily exposed to ionizing irradiations, from outside sources, as well as inside if they were to contamination. Medical nuclear workers (MNW) are exposed to ionizing irradiation, working with radio nuclides. MNW are periodically reviewed for contamination verified. Cytogenetic analysis of peripheral-blood lymphocytes (Ly) is the most sensitive tests for detecting a clinical biologic response to ionizing radiation. The frequency of chromosomal aberrations (f ca) in peripheral circulating lymphocytes (Ly) correlates with the dose received. (author) [sr

External effective radiation dose to workers in the restricted area of the Fukushima Daiichi Nuclear Power Plant during the third year after the Great East Japan Earthquake

International Nuclear Information System (INIS)

Sakumi, Akira; Miyagawa, Ryu; Tamari, Yuki; Nawa, Kanabu; Sakura, Osamu; Nakagawa, Keiichi

2016-01-01

Since the Great East Japan Earthquake on 11 March 2011, Iitate Village has continued to be classified as a deliberate evacuation area, in which residents are estimated to receive an annual additional effective radiation dose of >20 mSv. Some companies still operate in Iitate Village, with a special permit from the Cabinet Office Team in Charge of Assisting the Lives of Disaster Victims. In this study, we measured the annual effective radiation dose to workers in Iitate Village from 15 January to 13 December 2013. The workers stayed in Iitate for 10 h and left the village for the remaining 14 h each working day. They worked for 5 days each week in Iitate Village, but stayed outside of the village for the remaining 2 days each week. We found that the effective radiation dose of 70% of the workers was <2 mSv, including natural radiation; the maximum dose was 3.6 mSv. We estimated the potential annual additional effective radiation dose if people returned full-time to Iitate. Our analysis supports the plan for people to return to their home village at the end of 2017

Second analysis of mortality of nuclear industry workers in Japan

International Nuclear Information System (INIS)

Murata, Motoi; Ohshima, Sumio; Kudo, Shin-ichi

2002-01-01

A cohort study of nuclear industry workers was begun in 1990 to determine the possible health effect of low dose radiation exposure. A follow-up study of about 244,000 male workers was conducted using residence registration records. About 176,000 subjects were successfully followed up, and 5,527 deaths were ascertained during the period of observation 1986 through 1997. Underlying causes of death were identified by record linkage with magnetic tape records of national vital statistics data. The standardized mortality ratio (SMR) was calculated with Japanese males in general as the reference population. Tests for trends in death rates were made against cumulative radiation dose. The SMR (and its 95% confidence interval) was 0.90 (0.87-0.92) for all causes, 0.80 (0.77-0.84) for non-neoplastic diseases and 0.94 (0.90-0.98) for all cancer, respectively. The lower SMR was ascribed to possible healthy worker effects, etc. In the trend analyses, the death rate for neither all cancers sites nor leukemia showed any positive correlation with radiation dose, while significantly positive correlations were found for cancers of the esophagus (p<0.001), stomach (p<0.05) and rectum (p<0.05), and also for external causes (p<0.001). In lifestyle survey studies of 49,000 workers, both smoking and drinking habits were positively correlated with radiation dose. These lifestyle characteristics may have been important factors affecting the present results

Uncertainties on lung doses from inhaled plutonium.

Science.gov (United States)

Puncher, Matthew; Birchall, Alan; Bull, Richard K

2011-10-01

In a recent epidemiological study, Bayesian uncertainties on lung doses have been calculated to determine lung cancer risk from occupational exposures to plutonium. These calculations used a revised version of the Human Respiratory Tract Model (HRTM) published by the ICRP. In addition to the Bayesian analyses, which give probability distributions of doses, point estimates of doses (single estimates without uncertainty) were also provided for that study using the existing HRTM as it is described in ICRP Publication 66; these are to be used in a preliminary analysis of risk. To infer the differences between the point estimates and Bayesian uncertainty analyses, this paper applies the methodology to former workers of the United Kingdom Atomic Energy Authority (UKAEA), who constituted a subset of the study cohort. The resulting probability distributions of lung doses are compared with the point estimates obtained for each worker. It is shown that mean posterior lung doses are around two- to fourfold higher than point estimates and that uncertainties on doses vary over a wide range, greater than two orders of magnitude for some lung tissues. In addition, we demonstrate that uncertainties on the parameter values, rather than the model structure, are largely responsible for these effects. Of these it appears to be the parameters describing absorption from the lungs to blood that have the greatest impact on estimates of lung doses from urine bioassay. Therefore, accurate determination of the chemical form of inhaled plutonium and the absorption parameter values for these materials is important for obtaining reliable estimates of lung doses and hence risk from occupational exposures to plutonium.

Results of comparative assessment of US and foreign nuclear power plant dose experience and dose reduction programs

International Nuclear Information System (INIS)

Baum, J.W.; Horan, J.R.; Dionne, B.J.

1985-01-01

The objectives of this study were to determine how collective dose equivalents at US nuclear power plants compare to those of other technically advanced countries, and to evaluate factors that contribute to the differences. Fifty Health Physicists and nuclear engineers from 10 countries met at BNL May 29 - June 1, 1984 to exchange information and hold discussions on ''Historical Dose Experience and Dose Reduction (ALARA) at Nuclear Power Plants''. Results of evaluation of data from this meeting and other data from recent publications are summarized. Based on data evaluated to date it is clear that US plants have higher collective dose equivalents per reactor and per MW-yr generated than most other countries. Factors which contribute to low doses include: 1) minimization of cobalt in primary system components exposed to water, 2) careful control of primary system oxygen and pH, 3) good primary system water purity to minimize corrosion product formation, 4) careful plant design, layout and component segregation and shielding, 5) management interest and commitment, 6) minimum number of workers and in-depth worker training, 7) use of special tools, and 8) plant standardization

Chromosome aberrations in workers of ignalina nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Griciene, B.; Januskeviciute, I.; Mierauskiene, J.; Slapsyte, G. [Vilnius Univ. (Lithuania)

2006-07-01

Full text of publication follows: The Ignalina Nuclear Power Plant (I.N.P.P.) workers and outside workers including visitors constitute the largest occupational group exposed to low doses of ionizing radiation in Lithuania. In 2004, the annual collective dose to these workers (4392 persons) was 6,83 man Sv. The maximum annual individual dose of I.N.P.P. workers was 19,16 mSv, and of outside workers was 29,41 mSv. However, according to calculations performed by the Lithuanian Radiation Protection Centre, the decommissioning of I.N.P.P. (the I.N.P.P. is to be shut down by 2009) will result in collective dose of 35 man Sv. Therefore, a special attention should be given to implementation of radiation protection programme. The importance of cytogenetic studies in the medical surveillance of radiation-exposed persons is generally acknowledged. The aim of the present study was to analyse chromosome aberration frequencies in lymphocytes of I.N.P.P. workers. The blood sampling of 27 male workers was performed in October 2004, after planned outage of I.N.P.P.. It was estimated that outages of I.N.P.P. Units contributed 84% to all annual occupational collective dose. Average cumulative dose of 18 workers was 290,7 mSv (group A), and of 9 workers - 71,7 mSv (group B). The mean annual doses averaged over the three-year-period were 15,2 mSv and 0,76 mSv, respectively. None of the exposed workers had ever exceeded the permissible dose limit. The average age of group A workers was 45,2 years, and group B 48,2 years. A questionnaire form with details on age, occupational history, smoking habit and alcohol intake, medication, history of recent illness was completed for each person at the time of blood collection. 64 non-exposed male donors approximately matched by age were used as controls (group C). Heparinized venous blood samples were taken and cultures were initiated within 24 h according to the standard procedures. At least 500 first cycle metaphases were analysed from each

Chromosome aberrations in workers of ignalina nuclear power plant

International Nuclear Information System (INIS)

Griciene, B.; Januskeviciute, I.; Mierauskiene, J.; Slapsyte, G.

2006-01-01

Full text of publication follows: The Ignalina Nuclear Power Plant (I.N.P.P.) workers and outside workers including visitors constitute the largest occupational group exposed to low doses of ionizing radiation in Lithuania. In 2004, the annual collective dose to these workers (4392 persons) was 6,83 man Sv. The maximum annual individual dose of I.N.P.P. workers was 19,16 mSv, and of outside workers was 29,41 mSv. However, according to calculations performed by the Lithuanian Radiation Protection Centre, the decommissioning of I.N.P.P. (the I.N.P.P. is to be shut down by 2009) will result in collective dose of 35 man Sv. Therefore, a special attention should be given to implementation of radiation protection programme. The importance of cytogenetic studies in the medical surveillance of radiation-exposed persons is generally acknowledged. The aim of the present study was to analyse chromosome aberration frequencies in lymphocytes of I.N.P.P. workers. The blood sampling of 27 male workers was performed in October 2004, after planned outage of I.N.P.P.. It was estimated that outages of I.N.P.P. Units contributed 84% to all annual occupational collective dose. Average cumulative dose of 18 workers was 290,7 mSv (group A), and of 9 workers - 71,7 mSv (group B). The mean annual doses averaged over the three-year-period were 15,2 mSv and 0,76 mSv, respectively. None of the exposed workers had ever exceeded the permissible dose limit. The average age of group A workers was 45,2 years, and group B 48,2 years. A questionnaire form with details on age, occupational history, smoking habit and alcohol intake, medication, history of recent illness was completed for each person at the time of blood collection. 64 non-exposed male donors approximately matched by age were used as controls (group C). Heparinized venous blood samples were taken and cultures were initiated within 24 h according to the standard procedures. At least 500 first cycle metaphases were analysed from each

Radiation dose to construction workers at operating nuclear power plant sites. Volume 2. Appendices A--F. Final report, September 1975--September 1978

International Nuclear Information System (INIS)

Endres, G.W.R.; Shipler, D.B.

1978-12-01

These appendices contain the dosimetry procedures and details of the personnel and environmental dosimeters used for the Radiation Dose to Construction Workers at Operating Nuclear Power Plant Sites Study. A printout of the computer codes used to analyze dosimeter data is included along with all the raw data obtained. Appendices C through F contain computer output and log-normal plots of dosimetry data for environmental location and construction worker groups

Publication of new results from the INWORKS epidemiological study about the risk of cancer among nuclear industry workers chronically exposed to low ionizing radiation doses

International Nuclear Information System (INIS)

2015-01-01

In this cohort study, 308297 workers in the nuclear industry from France, the United Kingdom, and the United States with detailed monitoring data for external exposure to ionising radiation were linked to death registries. Excess relative rate per Gy of radiation dose for mortality from cancer was estimated. Follow-up encompassed 8.2 million person years. Of 66632 known deaths by the end of follow-up, 17?957 were due to solid cancers. Results suggest a linear increase in the rate of cancer with increasing radiation exposure. The average cumulative colon dose estimated among exposed workers was 20.9 mGy (median 4.1 mGy). The estimated rate of mortality from all cancers excluding leukaemia increased with cumulative dose by 48% per Gy (90% confidence interval 20% to 79%), lagged by 10 years. Similar associations were seen for mortality from all solid cancers (47% (18% to 79%)), and within each country. The estimated association over the dose range of 0-100 mGy was similar in magnitude to that obtained over the entire dose range but less precise. Smoking and occupational asbestos exposure are potential confounders; however, exclusion of deaths from lung cancer and pleural cancer did not affect the estimated association. Despite substantial efforts to characterise the performance of the radiation dosimeters used, the possibility of measurement error remains. The study provides a direct estimate of the association between protracted low dose exposure to ionising radiation and solid cancer mortality. Although high dose rate exposures are thought to be more dangerous than low dose rate exposures, the risk per unit of radiation dose for cancer among radiation workers was similar to estimates derived from studies of Japanese atomic bomb survivors. Quantifying the cancer risks associated with protracted radiation exposures can help strengthen the foundation for radiation protection standards

High-dose "1"3"1I-MIBG therapies in children: feasibility, patient dosimetry and radiation exposure to workers and family caregivers

International Nuclear Information System (INIS)

Cougnenc, Olivier; Defachelles, Anne-Sophie; Lervat, Cyril; Carpentier, Philippe; Oudoux, Aurore; Kolesnikov-Gauthier, Helene; Clisant, Stephanie

2017-01-01

The objective of the present multi-centric phase II study (MIITOP) was to determine the response rate, survival and toxicity of tandem infusions of "1"3"1I-meta-iodobenzylguanidine (mIBG) and topotecan in children with relapsed/refractory neuroblastoma. High-dose "1"3"1I-mIBG therapy programme requires a deal of planning, availability of hospital resources and the commitment of individuals with training and expertise in multiple disciplines. Here in the present study, procedures and the results of patient's dosimetry, as well as family and worker's exposures, were reported for the patients treated in Lille. A total of 15 children were treated with "1"3"1I-mIBG between 2009 and 2011 according to the MIITOP protocol. High activity of "1"3"1I-mIBG (444 MBq kg"-"1) was administered on Day 0. In vivo dosimetry was used to calculate a second activity, to be given on Day 21, to obtain a total whole body absorbed dose of 4 Gy. Family and worker's exposures were performed too. The injected activity by treatment was from 703 to 11470 MBq. Total whole body absorbed dose by patient ranged from 2.74 to 5.2 Gy. Concerning relatives, whole body exposure ranged from 0.018 to 2.8 mSv. The mean whole body exposure of the radio-pharmacist was 4.4 nSv MBq"-"1, and the mean exposure of fingers ranged from 0.18 to 0.24 μSv MBq"-"1 according to each finger. The mean whole body exposure was 33.6 and 20.2 μSv d"-"1 per person, for night nurses and day nurses, respectively. Exposure of doctors was less than 5 μSv d"-"1. Under strict radiation protection precautions, this study shows the feasibility of high-activity "1"3"1I-mIBG therapy in France. (authors)

Determinants of times of appearance of radium-induced osteosarcomas in humans: age at appearance and dose

International Nuclear Information System (INIS)

Stebbings, J.H.; Lucas, H.F.

1983-01-01

Determinants of time-until-tumor for osteosarcoma in US radium cases have been reevaluated. Classically, a minimum induction period (latency period) of about five years has been recognized, but not an expression period. Lack of long induction periods at igh doses has been ascribed to scarcity of subjects at risk. Recent experiments have suggested that induction periods are directly lengthened as doses decrease. Reanalyses of time-until-tumor data for 57 measured female osteosarcoma cases exposed to 226 Ra and /or 228 Ra support new interpretations: time-until-tumor for osteosarcomas is best described by age at tumor appearance, not by induction period; age at diagnosis increases as estimated initial radium intake decreases; and, there exists an expression period which can be truncated at the low end by the minimum induction period (or by age at exposure). The downturn in sarcoma incidence at very high doses is describable as the truncation of the expression period on its early side by the minimum induction period. These results depend strongly on the assumption of homogeneity of time-until-tumor processes in diial workers and in iatrogenic radium exposure cases

The monetary value of the collective dose equivalent unit (person-rem)

International Nuclear Information System (INIS)

Rodgers, Reginald C.

1978-01-01

In the design and operation of nuclear power reactor facilities, it is recommended that radiation exposures to the workers and the general public be kept as 'low as reasonably achievable' (ALARA). In the process of implementing this principle cost-benefit evaluations are part of the decision making process. For this reason a monetary value has to be assigned to the collective dose equivalent unit (person-rem). The various factors such as medical health care, societal penalty and manpower replacement/saving are essential ingredients to determine a monetary value for the person-rem. These factors and their dependence on the level of risk (or exposure level) are evaluated. Monetary values of well under $100 are determined for the public dose equivalent unit. The occupational worker person-rem value is determined to be in the range of $500 to about $5000 depending on the exposure level and the type of worker and his affiliation, i.e., temporary or permanent. A discussion of the variability and the range of the monetary values will be presented. (author)

Assessment of internal dose caused by uranium isotopes for workers in the phosphatic industry using alpha spectrometry

International Nuclear Information System (INIS)

Kharita, M. H.; Sakhita, Kh.; Al-Dallal, Z.

2007-04-01

There is probability of exposure to uranium for workers in the phosphate industry (Internal exposure) by inhalation, and the deposition of this uranium in organs and tissues, and the consequence excretion out of the body by perspiration or urine. This study focuses on the determination of uranium in urine samples of workers .some results seem to be higher than the detection limit of the method, therefore routine monitoring is required for those workers.(Author)

Malignant pleural mesothelioma risk among nuclear workers: a review

International Nuclear Information System (INIS)

Metz-Flamant, C; Guseva Canu, I; Laurier, D

2011-01-01

Exposure to ionising radiation has been suggested as a causal risk factor for malignant pleural mesothelioma (MPM). Studies of patients treated by radiotherapy for primary cancers have suggested that radiation contributes to the development of secondary MPM. Here we examined the risk to nuclear workers of MPM related to exposure to low doses of occupational radiation at low dose rates. All results concerning MPM risk in published studies of nuclear workers were examined for their association with radiation exposure and potential confounders. We found 19 relevant studies. Elevated risks of pleural cancer were reported in most (15/17) of these studies. Eight reported risks higher for radiation monitored workers than for other workers. However, of 12 studies that looked at associations with ionising radiation, only one reported a significant dose-risk association. Asbestos was an important confounder in most studies. We conclude that studies of nuclear workers have not detected an association between ionising radiation exposure and MPM. Further investigations should improve the consideration of asbestos exposure at the same time as they address the risk of MPM related to occupational exposure of nuclear workers to low doses of ionising radiation at low dose rates. (review)

Malignant pleural mesothelioma risk among nuclear workers: a review

Energy Technology Data Exchange (ETDEWEB)

Metz-Flamant, C; Guseva Canu, I; Laurier, D, E-mail: camille.metz@irsn.fr [Laboratory of Epidemiology, Institute of Radiological Protection and Nuclear Safety (IRSN), Fontenay-aux-Roses (France)

2011-03-01

Exposure to ionising radiation has been suggested as a causal risk factor for malignant pleural mesothelioma (MPM). Studies of patients treated by radiotherapy for primary cancers have suggested that radiation contributes to the development of secondary MPM. Here we examined the risk to nuclear workers of MPM related to exposure to low doses of occupational radiation at low dose rates. All results concerning MPM risk in published studies of nuclear workers were examined for their association with radiation exposure and potential confounders. We found 19 relevant studies. Elevated risks of pleural cancer were reported in most (15/17) of these studies. Eight reported risks higher for radiation monitored workers than for other workers. However, of 12 studies that looked at associations with ionising radiation, only one reported a significant dose-risk association. Asbestos was an important confounder in most studies. We conclude that studies of nuclear workers have not detected an association between ionising radiation exposure and MPM. Further investigations should improve the consideration of asbestos exposure at the same time as they address the risk of MPM related to occupational exposure of nuclear workers to low doses of ionising radiation at low dose rates. (review)

Estimated routine radiation doses to transportation workers in alternative spent-fuel transportation systems

International Nuclear Information System (INIS)

Schneider, K.J.; Smith, R.I.; Daling, P.M.; Ross, W.A.; McNair, G.W.

1988-01-01

The federal system for the management of spent fuel and high-level radioactive waste includes the acceptance by the US Department of Energy (DOE) of the spent fuel or waste loaded in casks at the reactor or other waste generators, its transportation to a repository, and its handling and final emplacement in the repository. The DOE plans to implement a transportation system that is safe, secure, efficient, and cost-effective and will meet applicable regulatory safety and security requirements. The DOE commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the routine radiation doses that would result from the operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in the higher fraction of doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. The study is one of a series used in making overall system design and operational decisions in the development of the DOE's spent-fuel/high-level waste transportation system. This paper contains the highlights from the PNL study of the estimated radiation doses to the transportation workers in a postulated reference transportation system and potential alternatives to that system

Organ doses and effective doses in some medical and industrial applications

International Nuclear Information System (INIS)

Keshavkumar, Biju

2000-01-01

The ICRP recommends radiation protection standards for the safe use of radiation and also prescribes the radiation protection quantities and periodically reviews them. In this context, the quantities like organ doses and effective doses are defined by ICRP. In this work we calculate these quantities and hence the conversion functions for the industrial radiation sources and those for CT and diagnostic X-ray exposures. Workers who are occupationally exposed to radiation are regularly monitored to evaluate the radiation dose received by them. It is quite possible that in an accident situation, the worker involved in the accident might not have worn a personal monitor, popularly known as the monitoring badge. In addition, even some non radiation workers (who are obviously not monitored) may also have received exposure. Under these circumstances, the persons involved are interviewed, the accident site inspected, and on the basis of realistic assumptions, the likely doses received by the exposed persons are estimated

Assessment of lung cancer risks for some categories of underground workers

International Nuclear Information System (INIS)

Dimitrov, M.

1975-01-01

In radioactive mines as well as in hardrock mines, tunnels under construction, and other underground workings, increased atmospheric levels of radioactive-gas daughter products are associated with a potential hazard of inhalation overexposure to workers. Absorbed dose from the alpha-activity component of deposition occurring in the process of breathing manifests a maximum in the area of secondary to quarternary bronchi. In this critical tissue, radiation exposure, along with other deleterious factors, produces conditions favourable to initiation of lung cancer, with a frequency of the latter proportional to cumulative dose. An assessment was made of absolute radiation risk to workers inhaling a radon-daughter contaminated atmosphere, on the basis of an estimated cumulative dose and a dose-response relation arrived at from epidemiological studies by other authors. For a range with a lower limit representing the product of maximum permissible concentration and half of the underground experience assigned to first category labor, and an upper limit determined by the product of maximum ''hidden'' alpha-decay energy measured and a full underground experience (180 months), cumulative exposures were found to vary from 90 to 8100 WLM. Rough estimates of corresponding lung cancer incidence ranged from 2 to 150 cases per year per 10,000 workers, versus 2-5 cases per year per 10,000 members of the general male population of the country. Results, obtained from a reconnaissance statistical study on a sample of 230 underground workers, with suitable working experiences and personal cumulative exposures, indicated a predicted frequency of lung cancer development of 0.43 cases per year, leading to an estimate of 19 cases per year per 10,000 workers. Such a magnitude of risk clearly shows an urgent need for introducing effective measures to improve radiological conditions in the occupational environment for a large proportion of the underground workers. (author)

Cytogenetic monitoring of nuclear workers occupationally exposed to ionising radiation

International Nuclear Information System (INIS)

Griciene, B.; Slapsyte, G.; Mierauskiene, J.

2014-01-01

Chromosome aberration (CA) analysis using Giemsa techniques was performed in blood lymphocytes of 84 nuclear workers with cumulative doses of 1-632 mSv during employment periods of 1-25 y. The control group comprised 82 healthy male donors. An estimated CA frequency in the total radiation-exposed group was significantly higher when compared with the controls (2.27 vs. 1.76 CA/100 cells, p 0.05). However, significant increase in the total CA frequency was determined in workers with additional internal exposure (2.54 CA/100 cells, p < 0.05) and those with registered neutron doses (2.95 CA/100 cells, p < 0.01). No correlation was found between CA frequency and occupational exposure dose. Borderline significant correlation was found between duration of employment and total CA (r = 0.218, p = 0.046, Fig. 2) and chromosome-type aberration (r = 0.265, p = 0.015) frequency. (authors)

Radiation Doses to Hanford Workers from Natural Potassium-40

Energy Technology Data Exchange (ETDEWEB)

Strom, Daniel J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lynch, Timothy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Weier, Dennis R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2009-02-01

The chemical element potassium is an essential mineral in people and is subject to homeostatic regulation. Natural potassium comprises three isotopes, ³⁹K, ⁴⁰K, and ⁴¹K. Potassium-40 is radioactive, with a half life of 1.248 billion years. In most transitions, it emits a β particle with a maximum energy of 0.560 MeV, and sometimes a gamma photon of 1.461 MeV. Because it is ubiquitous, ⁴⁰K produces radiation dose to all human beings. This report contains the results of new measurements of ⁴⁰K in 248 adult females and 2,037 adult males performed at the Department of Energy Hanford Site in 2006 and 2007. Potassium concentrations diminish with age, are generally lower in women than in men, and decrease with body mass index (BMI). The average annual effective dose from ⁴⁰K in the body is 0.149 mSv y^-1 for men and 0.123 mSv y^-1 women respectively. Averaged over both men and women, the average effective dose per year is 0.136 mSv y^-1. Calculated effective doses range from 0.069 to 0.243 mSv y^-1 for adult males, and 0.067 to 0.203 mSv y^-1 for adult females, a roughly three-fold variation for each gender. The need for dosimetric phantoms with a greater variety of BMI values should be investigated. From our data, it cannot be determined whether the potassium concentration in muscle in people with large BMI values differs from that in people with small BMI values. Similarly, it would be important to know the potassium concentration in other soft tissues, since much of the radiation dose is due to beta radiation, in which the source and target tissues are the same. These uncertainties should be evaluated to determine their consequences for dosimetry.

Determinants of Sunburn and Sun Protection of Agricultural Workers During Occupational and Recreational Activities.

Science.gov (United States)

Backes, Claudine; Milon, Antoine; Koechlin, Alice; Vernez, David; Bulliard, Jean-Luc

2017-11-01

The aim of this study was to identify determinants of occupational sunburn in agricultural workers and assess their occupational and recreational sun protection habits. Specific surveys of agricultural workers in Switzerland and France were conducted (N = 1538). Multivariate logistic regressions identified occupational sunburn determinants. Occupational and recreational sun protection habits were estimated and correlated. One-year occupational and recreational sunburn prevalences were 19.8% and 11.5%, respectively. Occupational sunburn increased with having a recent recreational sunburn, highly sensitive skin, young age, high perceived skin cancer risk, using sunscreen, and not wearing a hat. Correlation between protection habits during work and leisure was substantial (rs 0.5 to 0.7). Skin health knowledge was high and pro-tanning attitude moderate. Potentially modifiable sunburn determinants and suboptimal recreational and occupational sun protection practices were identified in agricultural workers. Refining and tailoring sun protection messages targeting the agricultural sector are needed.

Proceedings of an international workshop on historic dose experience and dose reduction (ALARA) at nuclear power plants

International Nuclear Information System (INIS)

Horan, J.R.; Baum, J.W.; Dionne, B.J.

1985-06-01

Dose reduction data and experience from 28 foreign and 10 US nuclear power plants was examined to determine causes for the wide variations in occupational dose from country to country. Major topics discussed were: steam generator and refueling maintenance problems; utility and supplier ALARA programs; effectiveness of dose-reduction modifications; attitudes and training; current and future dose-reduction research. While many parameters contribute to differences of occupational doses between plants from different nations, it is clear that most US plants have higher collective dose equivalent per reactor per megawatt-year than most other countries, even for plants of similar size and age. Worldwide, Finnish and Swedish plants, both PWR and BWR, have achieved the lowest values. Major factors which contribute to low doses include: (1) minimization of cobalt in primary system components exposed to water; (2) careful plant design, layout and component segregation and shielding; (3) plant standardization; (4) selection of components and systems for increased reliability; (5) management interest and commitment; (6) minimum number of workers and in-depth worker training; (7) careful control of primary system oxygen and pH; (8) good primary system water purity to minimize corrosion product formation; (9) use of special tools and robotics; (10) decontamination and passivation of primary systems and components; and (11) extent of backfitting and mandated inspections

Studies of absorbed dose determinations and spatial dose distributions for high energy proton beams

International Nuclear Information System (INIS)

Hiraoka, Takeshi

1982-01-01

Absolute dose determinations were made with three types of ionization chamber and a Faraday cup. Methane based tissue equivalent (TE) gas, nitrogen, carbon dioxide, air were used as an ionizing gas with flow rate of 10 ml per minute. Measurements were made at the entrance position of unmodulated beams and for a beam of a spread out Bragg peak at a depth of 17.3 mm in water. For both positions, the mean value of dose determined by the ionization chambers was 0.993 +- 0.014 cGy for which the value of TE gas was taken as unity. The agreement between the doses estimated by the ionization chambers and the Faraday cup was within 5%. Total uncertainty estimated in the ionization chamber and the Faraday cup determinations is 6 and 4%, respectively. Common sources of error in calculating the dose from ionization chamber measurements are depend on the factors of ion recombination, W value, and mass stopping power ratio. These factors were studied by both experimentally and theoretically. The observed values for the factors show a good agreement to the predicted one. Proton beam dosimetry intercomparison between Japan and the United States was held. Good agreement was obtained with standard deviation of 1.6%. The value of the TE calorimeter is close to the mean value of all. In the proton spot scanning system, lateral dose distributions at any depth for one spot beam can be simulated by the Gaussian distribution. From the Gaussian distributions and the central axis depth doses for one spot beam, it is easy to calculate isodose distributions in the desired field by superposition of dose distribution for one spot beam. Calculated and observed isodose curves were agreed within 1 mm at any dose levels. (J.P.N.)

75 FR 70699 - Notice of Determinations Regarding Eligibility To Apply for Worker Adjustment Assistance

Science.gov (United States)

2010-11-18

... sales of the workers' firm; or (B) A loss of business by the workers' firm with the firm described in... certifications have been issued. The date following the company name and location of each determination... Akron, OH International, Commercial Highway, Inc. 73,764 Amazon.com , Amazon Seattle, WA........ Mobile...

Social determinants of workers' health in Central America.

Science.gov (United States)

Aragón, Aurora; Partanen, Timo; Felknor, Sarah; Corriols, Marianela

2011-01-01

This communication summarizes the available data on work-related determinants of health in Central America. The Central American working population is young and moving from agriculture toward industry and services. Ethnicity, gender, migration, subemployment and precarious work, informality, rural conditions, low-level educational, poverty, ubiquitous worksite health hazards, insufficient occupational health services, low labor inspection density, and weak unions define the constellation of social determinants of workers' health in Central America. Data are, however, scanty both for hazards and work-related illnesses and injuries. Governments and industries have the responsibility of opening decent work opportunities, especially for those facing multiple inequalities in social determinants of health. A first step would be the ratification and implementation of the ILO Convention (187) on occupational safety and health by the seven national governments of the region.

Individual internal monitoring of workers of Fabrica de Combustivel Nuclear - FCN

International Nuclear Information System (INIS)

Castro, Marcelo X.

2005-01-01

In nuclear fuel fabrication facilities, workers are exposed to different compounds of enriched uranium. Due to the high cost of the individual monitoring programme for internal dose assessment in the routine monitoring programmes, usually only one type of measurement is assigned. In complex situations like the one described in this paper, where several parameters can compromise the accuracy of the bioassay interpretation it is need to have a combination of techniques to evaluate the internal dose. According to ICRP 78 (1997), the general order of preference in terms of accuracy of interpretation is: body activity measurement, excreta analysis and personal air sampling. A group of fifteen workers from controlled area of the fuel fabrication facility was selected to evaluate the internal dose using all different available techniques during a certain period. The workers were monitored for determination of uranium content in the daily urinary excretion, faecal excretion, chest counting and personal air sampling (PAS). The results have shown that at least two types of sensitivity techniques must be used, since there are some sources of uncertainties on the bioassay interpretation, like mixture of uranium compounds intake and different routes of intake. The combination of urine and faeces analysis has shown be the more appropriate methodology for assessing internal dose in this situation. (author)

Health of radiation workers

International Nuclear Information System (INIS)

Myers, D.K.

1979-11-01

Radiation workers are healthier than the average person in the general population and appear to be as healthy as workers in other ΣsafeΣ industries. It is, however, assumed that there is no safe dose of radiation and that any exposure to radiation will cause a small increase in the incidence of cancer, this increase being directly proportional to the total radiation dose. On the basis of the risk estimates given by ICRP, radiation exposures up to 1 rem per year for 47 years are predicted to cause fewer work-related deaths than expected for the average worker in Canadian industry. Radiation exposures of 5 rem per year from age 18 to 65 would result in predicted risk which is about four times higher than that for most workers in Canada and might increase the chances of death before age 75 to nearly the same level as for the average member of the general public. (auth)

Epidemiologic Study of One Million U.S. Radiation Workers and Veterans

Energy Technology Data Exchange (ETDEWEB)

Boice, John D. [National Council on Radiation Protection and Measurements, Bethesda, MD (United States)

2017-12-14

The single most important question in radiation epidemiology is determining the level of health risks associated with radiation exposures that occur gradually over time. The study of one million early U.S. radiation workers and veterans has been designed to provide information on risk following chronic exposures by focusing on occupational groups with differing radiation exposure patterns, including intakes of radionuclides. The cost-efficient study builds on the investments made and foundations laid by investigators and government agencies over the past 30-40 years, which have established early worker cohorts that can now provide answers to questions on the lifetime human health risks associated with low-level radiation exposures. Within the overall goal of the epidemiologic study of one million U.S. radiation workers and veterans, this project had a total of nine specific aims which included studies of six populations for multiple endpoints including cancer overall mortality, leukemia and non-cancer mortality. The six populations included: Mound, Ohio, workers exposed to polonium, tritium and plutonium; nuclear power plant workers within the Landauer dosimetry and Nuclear Regulatory Commission data files; industrial radiographers; Mallinckrodt uranium workers; uranium workers who linked with the US Renal Data System; and nuclear weapons test participants. Over 400,000 workers and atomic veterans are included in these populations, with vital status being determined and analyses of all causes of death undertaken. A critical, integral component of the studies has been comprehensive evaluations of dosimetry involving, in many cases, complex dose reconstructions, and assessments of uncertainties. The work has also involved development of state-of-the art statistical approaches and modeling. All nine aims were accomplished successfully, resulting in publication of two NCRP documents, 13 literature papers, numerous Boice Reports in Health Physics News and many

Predicting Worker Exposure from a Glovebox Leak

International Nuclear Information System (INIS)

Jordan, H.; Gordon, D. J.; Whicker, J. J.; Wannigman, D. L.

2001-01-01

It is difficult to predict immediate worker radiological consequences from a hypothetical accident. This is recognized in DOE safety analysis guidance and the reason such guidance does not call for quantitative determinations of such consequences. However, it would be useful to at least have a means of systematically and formally quantifying worker dose to be able to identify the relative risks of various processes and to provide an order-of-magnitude impression of absolute consequences. In this report, we present such a means in the form of a simple calculation model that is easily applied and generates reasonable, qualitative dose predictions. The model contains a scaling parameter whose value was deduced from extensive laboratory ventilation flow rate measurements performed at Los Alamos National Laboratory (LANL) over the last several years and from recent indoor radioactive contamination dispersion measurements, also at LANL. Application of the model is illustrated with the aid of two example calculations

Radiation haunts shipyard workers

International Nuclear Information System (INIS)

Torrey, L.

1978-01-01

The apparent link recently found by Dr. Najarian between cancer among workers at a US Naval dockyard where up to 5000 civilian employees have been exposed to low dose irradiation while servicing nuclear ships and their radiation exposure is discussed. The study has revealed that 38.4% of the deaths of nuclear workers at the Portsmouth Naval Shipyard in New Hampshire were caused by cancer while the comparable rate for non-nuclear shipyard workers was 21.7% and the national average in the United States is 18%. The Portsmouth study, launched in October 1977, was based on a survey of 1722 death certificates of shipyard employees and interviews with 592 next-of-kin. In addition the results show that the rate of leukaemia of the shipyard workers was 450% higher than that of the general population, and the incidence of lymph gland cancers was 125% higher than the national rate. The most startling statistics compared mortality among workers aged 60 to 69. In this age group nearly 60% of the nuclear employees had died of cancer, while the cancer death rate among non-nuclear workers was only 26%. If these results are confirmed present ideas concerning the effects of low doses of radiation must be challenged. (U.K.)

Dose contribution from metabolized organically bound tritium after chronic tritiated water intakes in humans

International Nuclear Information System (INIS)

Trivedi, A.; Lamothe, E.; Galeriu, D.

2001-01-01

Our earlier study of acute tritiated water intakes in humans has demonstrated that the dose contribution from metabolized organically bound tritium is less than 10% of the body water dose. To further demonstrate that the dose contribution from the organically bound tritium per unit intake of tritiated water is the same, regardless of whether the intake is acute (all at once) or chronic (spread over time), urine samples from six male radiation workers with chronic tritiated water intakes were collected and analyzed for tritium. These workers have a well-documented dose history and a well-controlled tritium bioassay database, providing assurance that their tritium intakes were in the form of tritiated water. Each month for a full calendar year, urine samples were collected from each exposed worker. The monthly concentration of tritium-in-urine for each exposed worker was no lower than 104 Bq L -1 but no higher than 105 Bq L -1 . These urine samples were analyzed for tritiated water and organically bound tritium to determine the ratio of these tritiated species in urine. The average ratio of tritiated water to organically bound tritium in urine for each exposed worker was 330-129 (range, 297-589). In calculating the dose to these workers, we assumed that, under steady-state conditions, the ratio of the specific activity of tritium ( 3 H activity per gH) in the organic matter and water fractions of urine is representative of the ratio of the specific activity of tritium in the organic matter and water fractions of soft tissue. A mathematical model was developed and used to estimate the dose increase from the metabolized organically bound tritium based on the ratio of tritiated water to organically bound tritium in urine. The resulting average dose from the organically bound tritium was 6.9-3.1% (range, 4.7-9.9%) of the body water dose for the six male workers, and agrees well with the value obtained from our acute tritiated water intakes study in humans. The observed

The National Dose Registration and Information System: Dose distributions in the Netherlands over the period 1989-1993

International Nuclear Information System (INIS)

Dijk, J.W.E. van; Julius, H.W.; Bogaerde, M.A. van de

1994-01-01

In 1988 the Ministry of Social Affairs and Employment commissioned TNO Radiological Service to set up a National Dose REgistration and Information System (NDRIS). The government had three reasons in view to build NDRIS: To improve radiation protection by supervising the occupational doses of radiation workers by using one central database system; To improve the reliability of long term storage of dose data; To improve the possibilities for statistical analysis of occupational doses to guide policy making. Each approved dosimetry service (ADS) in the country sends its dose information to NDRIS on a monthly basis. IN its turn NDRIS sends back for each worker monitored by that ADS, the integrated dose as measured by any ADS. This creates the possibility for each ADS to report to the workers their total annual dose irrespectively whether they work for more than one employer or are monitored by more than one ADS, either simultaneously or successively in the course of the year. European legislation requires that the occupational dose should be controlled in this way. The availability of the centralized database replaces the need of a radiation passbook for national use. The passbook that is needed by radiation workers during interstate travelling can be produced using data from NDRIS

Dose Rate Determination from Airborne Gamma-ray Spectra

DEFF Research Database (Denmark)

Bargholz, Kim

1996-01-01

The standard method for determination of ground level dose rates from airborne gamma-ray is the integral count rate which for a constant flying altitude is assumed proportional to the dose rate. The method gives reasonably results for natural radioactivity which almost always has the same energy...

Calculation of the store house worker dose in a lost wax foundry using MCNP-4C.

Science.gov (United States)

Alegría, Natalia; Legarda, Fernando; Herranz, Margarita; Idoeta, Raquel

2005-01-01

Lost wax casting is an industrial process which permits the transmutation into metal of models made in wax. The wax model is covered with a silicaceous shell of the required thickness and once this shell is built the set is heated and wax melted. Liquid metal is then cast into the shell replacing the wax. When the metal is cool, the shell is broken away in order to recover the metallic piece. In this process zircon sands are used for the preparation of the silicaceous shell. These sands have varying concentrations of natural radionuclides: 238U, 232Th and 235U together with their progenics. The zircon sand is distributed in bags of 50 kg, and 30 bags are on a pallet, weighing 1,500 kg. The pallets with the bags have dimensions 80 cm x 120 cm x 80 cm, and constitute the radiation source in this case. The only pathway of exposure to workers in the store house is external radiation. In this case there is no dust because the bags are closed and covered by plastic, the store house has a good ventilation rate and so radon accumulation is not possible. The workers do not touch with their hands the bags and consequently skin contamination will not take place. In this study all situations of external irradiation to the workers have been considered; transportation of the pallets from vehicle to store house, lifting the pallets to the shelf, resting of the stock on the shelf, getting down the pallets, and carrying the pallets to production area. Using MCNP-4C exposure situations have been simulated, considering that the source has a homogeneous composition, the minimum stock in the store house is constituted by 7 pallets, and the several distances between pallets and workers when they are at work. The photons flux obtained by MCNP-4C is multiplied by the conversion factor of Flux to Kerma for air by conversion factor to Effective Dose by Kerma unit, and by the number of emitted photons. Those conversion factors are obtained of ICRP 74 table 1 and table 17 respectively. This

Calculation of the store house worker dose in a lost wax foundry using MCNP-4C

International Nuclear Information System (INIS)

Alegria, N.; Legarda, F.; Herranz, M.; Idoeta, R.

2005-01-01

Lost wax casting is an industrial process which permits the transmutation into metal of models made in wax. The wax model is covered with a siliceous shell of the required thickness and once this shell is built the set is heated and wax melted. Liquid metal is then cast into the shell replacing the wax. When the metal is cool, the shell is broken away in order to recover the metallic piece. In this process zircon sands are used for the preparation of the siliceous shell. These sands have varying concentrations of natural radionuclides: 238 U, 232 Th and 235 U together with their progenics. The zircon sand is distributed in bags of 50 kg, and 30 bags are on a pallet, weighing 1,500 kg. The pallets with the bags have dimensions 80 cm x 120 cm x 80 cm, and constitute the radiation source in this case. The only pathway of exposure to workers in the store house is external radiation. In this case there is no dust because the bags are closed and covered by plastic, the store house has a good ventilation rate and so radon accumulation is not possible. The workers do not touch with their hands the bags and consequently skin contamination will not take place. In this study all situations of external irradiation to the workers have been considered; transportation of the pallets from vehicle to store house, lifting the pallets to the shelf, resting of the stock on the shelf, getting down the pallets, and carrying the pallets to production area. Using MCNP-4C exposure situations have been simulated, considering that the source has a homogeneous composition, the minimum stock in the store house is constituted by 7 pallets, and the several distances between pallets and workers when they are at work. The photons flux obtained by MCNP-4C is multiplied by the conversion factor of Flux to Kerma for air by conversion factor to Effective Dose by Kerma unit, and by the number of emitted photons. Those conversion factors are obtained of ICRP 74 table 1 and table 17 respectively. This is

Cancer mortality among nuclear workers in Belgium

International Nuclear Information System (INIS)

Engels, H.; Holmstock, L.; Mieghem, E. Van; Swaen, G.M.; Wambersie, A.

2000-01-01

To investigate long term health effects of chronic exposure to low doses of ionising radiation, the Nuclear Research Center (SCK.CEN) in Mol set up a retrospective cohort study in 5 nuclear facilities in Belgium (SCK.CEN, Belgonucleaire, Belgoprocess, 2 Electrabel nuclear power plants). Cancer mortality among nuclear workers is studied in relation to occupational exposure to ionising radiation. This study is part of the 'International Collaborative Study on Cancer Risk among Radiation Workers', coordinated by the International Agency for Research on Cancer (IARC/WHO), pooling data of 14 countries. During the period 1953-1994, all workers registered in one of the participating facilities were included in the study (n=7361). Data have been collected from different information sources: personnel registries (identification, occupational history), dosimetry records (e.g. annual effective dose), National Population Registry and local authorities (vital status). National Institute of Statistics (causes of death from the death certificates), National Radiation Registry/Ministry of Labour (transfer doses), questionnaires (e.g. smoking habits). Retrospective collection of data and privacy protection regulations specific to Belgium hampered the conduct of this study, causing labour intensive and time consuming procedures. Written informed consent of next-of-kin is required to obtain information from the death certificates. Before 1969 only family reported causes of death are available. Despite the above mentioned constraints, first results of Standardised Mortality Ratio (SMR) calculations are now available for SCK.CEN workers for the period 1969-1994 (n=3270, vital status ascertainment: 95%, underlying cause of death ascertainment: 80%). Available SMR's can be summarised as follows: male workers, no measurable dose (n=785): SMR all causes=75% (95%CI: 61-91), SMR all tumours=64% (95%CI: 42-93), 2 leukemia deaths were observed, whereas 1 is expected, male workers, measurable

Determination of skin dose reduction by lead equivalent gloves

International Nuclear Information System (INIS)

Norriza Mohd Isa; Abd Aziz Mhd Ramli

2006-01-01

Radiation protective gloves are always used in medical facilities to protect radiation workers from unnecessary radiation exposure. A study on radiation protection gloves which are produced by local company had been performed by the Medical Physics Group, MINT. The gloves were made of lead equivalent material, as the attenuating element. The gloves were evaluated in term of the percentage of skin dose reduction by using a newly developed procedure and facilities in MINT. Attenuation measurements of the gloves had been carried out using direct beams and scattered radiations of different qualities. TLD rings were fitted on finger phantom; and water phantom were used in the measurement. The result were obtained and analysed based on data supplied by manufacturer. (Author)

Considering job-related doses in Europe

International Nuclear Information System (INIS)

Anon.

1990-01-01

As part of its role of safeguarding nuclear workers the Commission of the European Community has created a European data bank on job-related doses. The data bank is intended to correlate jobs and workers doses and is a useful instrument to observe the collected doses of workers in nuclear power plants. Set up in 1980, the database covers doses in PWRs and BWRs. To create it a questionnaire is distributed to plant operators. The database responses provide information on (i) Trends in total collective doses, including those for some ancillary jobs. It is possible to see trends by calendar year and by fuel cycle number. (ii) Other trends such as dose in terms of installed power or dose in terms of power station design. (iii) Dose differences between power stations, normalized against the differences in dose rates. This is only possible for PWRs that monitor dose rates using the EPRI standard monitoring programme. (vi) The relative dose rate in each plant for a defined job. The questionnaire is not perfectly adapted to all the working criteria in nuclear power stations but it is an effective tool for implementing radiation protection. (author)

Wage determination and discrimination among older workers.

Science.gov (United States)

Quinn, J F

1979-09-01

In this study, the determinants of the wage rates of a large sample of individuals aged 58 to 63 are first analyzed. Second, an explanation for the large discrepancies existing between the average wage rates earned by whites and nonwhites and by men and women is attempted. Human capital and geographic variables were found to be important wage determinants. Education, vocational training, years of job tenure, health, region of residence and local cost of living were significant explanators, especially for whites. Differences in these variables, however, cannot completely explain the wage differentials that exist by race and sex. There is a large unexplained component (especially in the male-female comparison) offering evidence of race and sex discrimination among older workers. In the case of sex discrimination, much of the problem appears to be occupational segregation--the crowding of women into low paying industries and occupations.

Determinants of condom breakage among female sex workers in Karnataka, India

Directory of Open Access Journals (Sweden)

Bradley Janet

2011-12-01

Full Text Available Abstract Background Condoms are effective in preventing the transmission of HIV and other sexually transmitted infections, when properly used. However, recent data from surveys of female sex workers (FSWs in Karnataka in south India, suggest that condom breakage rates may be quite high. It is important therefore to quantify condom breakage rates, and examine what factors might precipitate condom breakage, so that programmers can identify those at risk, and develop appropriate interventions. Methods We explored determinants of reported condom breakage in the previous month among 1,928 female sex workers in four districts of Karnataka using data from cross-sectional surveys undertaken from July 2008 to February 2009. Using stepwise multivariate logistic regression, we examined the possible determinants of condom breakage, controlling for several independent variables including the district and client load. Results Overall, 11.4% of FSWs reported at least one condom break in the previous month. FSWs were much more likely to report breakage if under 20 years of age (AOR 3.43, p = 0.005; if divorced/ separated/widowed (AOR 1.52, p = 0.012; if they were regular alcohol users (AOR 1.63, p = 0.005; if they mostly entertained clients in lodges/rented rooms (AOR 2.99, p = 0.029 or brothels (AOR 4.77, p = 0.003, compared to street based sex workers; if they had ever had anal sex (AOR 2.03, p = 0.006; if the sex worker herself (as opposed to the client applied the condom at last use (AOR 1.90, p Conclusions The reported incidence of condom breakage was high in this study, and this is a major concern for HIV/STI prevention programs, for which condom use is a key prevention tool. Younger and more marginalized female sex workers were most vulnerable to condom breakage. Special effort is therefore required to seek out such women and to provide information and skills on correct condom use. More research is also needed on what specific situational parameters

Operation of the radiation dose registration system for decontamination and related works

International Nuclear Information System (INIS)

Ogawa, Tsubasa; Yasutake, Tsuneo; Itoh, Atsuo; Miyabe, Kenjiro

2017-01-01

The radiation dose registration system for decontamination and related works was established on 15 November 2013. Radiation dose registration center and primary contractors of decontamination and related works manage decontamination registration and management system. As of 31 March 2017, 384 primary contractors joined in the radiation dose registration system for decontamination and related works. 383,087 quarterly exposure dose records for decontamination and related works were registered. Based on the registered data provided by the primary contractors, radiation dose registration center has released the statistical data that represent the radiation control status for workers engaged in radiation work at the work areas of decontamination and related works, etc. The statistical data shows that there were 40,377 workers engaged in decontamination and related works in 2015. The average exposure dose for workers was 0.6 mSv in 2015. The maximum exposure dose for workers was 7.8 mSv in 2015. Dose distribution by age of workers shows the range of 60 to 64 years old were most engaged in decontamination and related works in 2015. Dose distribution by gender of workers shows 97% of workers were male in 2015. From 2012 to 2015, about 95% of workers were exposed to radiation less than 3 mSv. And about 80% of workers were exposed to radiation less than 1 mSv. The average exposure dose per year was ranged from 0.5 to 0.7 mSv. (author)

Overview of internal dose evaluation in the radiopharmaceutical production plant at IPEN

International Nuclear Information System (INIS)

Todo, Alberto S.; Gerulis, Eduardo; Cardoso, Joaquim C.S.; Rodrigues Junior, Orlando

2015-01-01

The internal dosimetry program at the Instituto de Pesquisas Energeticas e Nucleares, IPEN, is accomplished in two steps: the activity measurements are performed at the In Vivo Monitoring Laboratory and subsequently the data analysis and the dose evaluation are carried out by the Dose Calculation Group according to the ICRP models. The objective of this study is to take the whole body and thyroid monitoring results recorded from 2005 to 2015 to see whether the internal contamination control procedure for workers were suitable even with the increase in the radiopharmaceutical production. The study were based in a research called “Search of Variables” for the operations carried out in the restricted areas of radiopharmaceutical production plant, taking into account the dose distribution data for all the tasks recorded by the radioprotection service. This methodology aims to identify and determine the principal variables that impact on the worker's dose. The results were presented for the following variables: individual occupationally exposed, operation variable, area/cell, type of task of operation, which depend on the variable dose. In spite of growth rate in the production of radiopharmaceutical, this study has shown that the improvements in the plant have contributed to the dose reduction of the workers. (author)

Importance of the Computed Tomography Dose Index (CTDI) and Dose Length Product (DLP)

International Nuclear Information System (INIS)

Rasolomboahanginjatovo, L.M.

2014-01-01

This work is under the auspice of the International Atomic Energy Agency (IAEA) projects (RAF/9/053) untitled S trengthening of the technical capacity for the protection patients and worker . The goal of this work is to highlight the importance of the Computed Tomography Dose Index (CTDI) and the Dose Length product (DLP). Measures were done at Polyclinic of Ilafy and CRDT Anosivavaka, Antananarivo, Madagascar. Doses were evaluated by use of pencil ionization chamber model 6000-10 connected with an electrometer RAD-CHECK model 06-256. Knowledge of dose indicator and Diagnostic Reference Level (DRL) allow the monitoring of scanner within the appropriate average dosimeter. It also insures the progressive determination for the most adapted dose requirements by choice of parameters available on scanner device. Measurements confirmed that doses from scanner devices of the two centers were under DRL requirements proposed by the IAEA, the European Commission (EC) and the National Radiological Protection Board (NRPB). The present results confirm that the patient delivered doses for the two centers are optimized. [fr

Part I. Emergency workers

International Nuclear Information System (INIS)

2004-01-01

This monograph deals with assessment of radiological health effects of the Chernobyl accident for emergency workers (part 1) and the population of the contaminated areas in Russia (part 2). The Chernobyl emergency workers and people living in the contaminated areas of Russia received much lower doses than the population of Hiroshima and Nagasaki and it was unclear whether risks of radiation-induced cancers derived with the Japanese data could be extrapolated to the low dose range However, it was predicted as early as in 1990 that the thyroid cancer incidence might be increasing due to incorporated 131 irradiation. What conclusions can be drawn from regarding cancer incidence among emergency workers and residents of the contaminated areas in Russia and the role of the radiation factor on the basis of the registry data? Leukemia incidence. Leukemia incidence is known to be one of principal indications of radiation effects. The radiation risk for leukemias is 3-4 times higher that for solid cancers and its latent period is estimated to be 2-3 years after exposure. Results of the radiation epidemiological studies discussed in this book show that in the worst contaminated Bryansk region the leukemia incidence rate is not higher than in the country in general. Even though some evidence exists for the dose response relationship, the radiation risks appear to be not statistically significant. Since risks of leukemia are known to be higher for those who were children at exposure, long-term epidemiological studies need to be continued. The study of leukemias among emergency workers strongly suggest the existence of dose response relationship. In those who received external doses more than 0.15 Gy the leukemia incidence rate is two time higher and these emergency workers should be referred to as a group of increased radiation risk. Solid cancers. The obtained results provide no evidence to a radiation-induced increase in solid cancers among residents of the contaminated areas

Evaluation of the genotoxic effects of chronic low-dose ionizing radiation exposure on nuclear medicine workers

Energy Technology Data Exchange (ETDEWEB)

Sahin, Ali [Department of Nuclear Medicine, Faculty of Medicine, Medical School, Ataturk University, Erzurum (Turkey)], E-mail: alibabam2001@yahoo.com; Tatar, Abdulgani; Oztas, Sitki [Department of Genetics, Faculty of Medicine, Ataturk University, 25240 Erzurum (Turkey); Seven, Bedri; Varoglu, Erhan [Department of Nuclear Medicine, Faculty of Medicine, Medical School, Ataturk University, Erzurum (Turkey); Yesilyurt, Ahmet [Department of Genetics, Faculty of Medicine, Ataturk University, 25240 Erzurum (Turkey); Ayan, Arif Kursad [Department of Nuclear Medicine, Faculty of Medicine, Medical School, Ataturk University, Erzurum (Turkey)

2009-07-15

Introduction: Nuclear medicine workers are occupationally exposed to chronic ionizing radiation. It is known that ionizing radiation may have damaging effects on chromosomes. In the present study, we investigated the genotoxic effects of ionizing radiation on nuclear medicine workers. We used two different indicators of genotoxicity methods: sister chromatid exchange (SCE) and micronucleus (MN). Methods: The present research was carried out using 21 nuclear medicine workers (11 females and 10 males) during two periods: during normal working conditions and after a 1-month vacation. The radiation dose varied from 1.20 to 48.56 mSv, which accumulated during the occupational exposure time between two vacations. Peripheral blood samples were taken from each subject for two distinct lymphocyte cultures (SCE and MN) in each period. Results: In nearly all subjects, SCE values increased significantly during radiation exposure compared to the postvacation period (P<.05). Similarly, MN frequencies in most of the subjects increased significantly during radiation exposure compared to the postvacation period (P<.05). Conclusions: This study revealed that both SCE and MN frequencies in most of the subjects were significantly higher during exposure to ionizing radiation than after a 1-month vacation period. However, this genotoxic effect was reversible in most of the subjects.

Evaluation of the genotoxic effects of chronic low-dose ionizing radiation exposure on nuclear medicine workers

International Nuclear Information System (INIS)

Sahin, Ali; Tatar, Abdulgani; Oztas, Sitki; Seven, Bedri; Varoglu, Erhan; Yesilyurt, Ahmet; Ayan, Arif Kursad

2009-01-01

Introduction: Nuclear medicine workers are occupationally exposed to chronic ionizing radiation. It is known that ionizing radiation may have damaging effects on chromosomes. In the present study, we investigated the genotoxic effects of ionizing radiation on nuclear medicine workers. We used two different indicators of genotoxicity methods: sister chromatid exchange (SCE) and micronucleus (MN). Methods: The present research was carried out using 21 nuclear medicine workers (11 females and 10 males) during two periods: during normal working conditions and after a 1-month vacation. The radiation dose varied from 1.20 to 48.56 mSv, which accumulated during the occupational exposure time between two vacations. Peripheral blood samples were taken from each subject for two distinct lymphocyte cultures (SCE and MN) in each period. Results: In nearly all subjects, SCE values increased significantly during radiation exposure compared to the postvacation period (P<.05). Similarly, MN frequencies in most of the subjects increased significantly during radiation exposure compared to the postvacation period (P<.05). Conclusions: This study revealed that both SCE and MN frequencies in most of the subjects were significantly higher during exposure to ionizing radiation than after a 1-month vacation period. However, this genotoxic effect was reversible in most of the subjects.

The multilevel determinants of workers' mental health: results from the SALVEO study.

Science.gov (United States)

Marchand, Alain; Durand, Pierre; Haines, Victor; Harvey, Steve

2015-03-01

This study examined the contribution of work, non-work and individual factors on workers' symptoms of psychological distress, depression and emotional exhaustion based on the multilevel determinants of workers' mental health model. Data from the SALVEO Study were collected in 2009-2012 from a sample of 1,954 employees nested in 63 workplaces in the province of Quebec (Canada). Multilevel regression models were used to analyse the data. Altogether, variables explain 32.2 % of psychological distress, 48.4 % of depression and 48.8 % of emotional exhaustion. Mental health outcomes varied slightly between workplaces and skill utilisation, physical and psychological demands, abusive supervision, interpersonal conflicts and job insecurity are related to the outcomes. Living in couple, having young children at home, family-to-work conflict, work-to-family conflict, strained marital and parental relations, and social support outside the workplace associated with the outcomes. Most of the individual characteristics also correlated with the three outcomes. Importantly, non-work and individual factors modulated the number and type of work factors related to the three outcomes. The results of this study suggest expanding perspectives on occupational mental health that fully recognise the complexity of workers' mental health determinants.

Measurement of Natural Radioactive Nuclide Concentrations and the Dose Estimation of Workers Originated from Radon in Manganese Ore Mine

International Nuclear Information System (INIS)

Mansour, N.A.; Hassan, N.M.; Blasy, M.R.

2013-01-01

Manganese ore is widely used in many industries. Such as ore contain natural radioactive nuclides at various concentrations. If this ore contain high concentrations of natural radioactive nuclides, workers handling them might be exposed to significant levels of radiation. Therefore it is important to determine the radioactive nuclides in this ore. Also the regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Nevertheless, at this time there is no globally accepted workplace protocol that sets out safe radon concentration values. In this study the radon concentration measured by using an Alpha Guard radon monitor, the equilibrium factor which was greater than the value given in literature, effective radiation dose, which are necessary for the exact estimation of the radiation dose originating from radon. The regulation of radon concentration at workplaces has gained an accentuated importance in all countries. Approach: The natural radionuclides ( 238 U, 232 Th and 40 K) contents of manganese ore samples collected from Umm Bogma, southwest Sinai and from the mountain access Hamid South Eastern Desert, Egypt have been determined by low background spectroscopy using hyper-pure germanium (HPGe) detector. Results: The mean activities due to the three radionuclides ( 238 U, 232 Th and 40 K) were found to be 1500±65, 490±65 and 364±45 Bqkg -1 , respectively. The absorbed dose rate due to the natural radioactivity in samples under investigation ranged from 1522±45 → 1796±43 nGyh -1 . The radium equivalent activity varied from 3807±114→ 4446±133 Bqkg -1 .The representative external hazard index values for the corresponding samples are also estimated. Conclusion: The results of this assessment obtained by the gamma-ray spectroscopic analysis, have indicated that the levels of natural radioactivity were lower than the international recommended limits.

Development of personal dose monitoring system using wireless data transmission device

International Nuclear Information System (INIS)

Inui, Daisuke; Nakashima, Sadao

2008-01-01

Radiation workers working in radiation controlled area in nuclear power plants etc., are required to carry a dosimeters by regulation law. The workers are controlled daily on personal exposure dose by reading out the exposure dose information of the dosimeters with an area access control gate installed at the entrance of the radiation controlled area. This type of personal dose monitoring system has a problem that each worker can get his personal dose data only at the entrance of the radiation controlled area several times a day. We developed a system to get the real-time acquisition of personal dose data especially for workers working in a high dose area. This system is generally composed of a dosimeter with a wireless attachment, relay station, and monitor. Some relay stations set in main work places in the radiation controlled area can collect real-time personal dose data of each dosimeter carried by workers at the work place with the relay stations, and transmit it to the monitor to get personal dose data of individual workers. A wireless communication system between dosimeters and relay stations is applied to collect efficiently all personal dose data in the work place. (author)

Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Hoover, M.D.; Newton, G.J.; Farrell, R.F.

1996-01-01

This qualitative hazard evaluation systematically assessed potential doses to workers during postulated accident conditions at the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP). Postulated accidents included the spontaneous ignition of a waste drum, puncture of a waste drum by a forklift, dropping of a waste drum from a forklift, and simultaneous dropping of seven drums during a crane failure. The descriptions and estimated frequencies of occurrence for these accidents were developed by the Hazard and Operability Study for CH TRU Waste Handling System (WCAP 14312). The estimated materials at risk, damage ratios, airborne release fractions and respirable fractions for these accidents were taken from the 1995 Safety Analysis Report (SAR) update and from the DOE handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities (DOE-HDBK-3010-94). A Monte Carlo simulation was used to estimate the range of worker exposures that could result from each accident. Guidelines for evaluating the adequacy of defense-in-depth for worker protection at WIPP were adopted from a scheme presented by the International Commission on Radiological Protection in its publication on Protection from Potential Exposure: A Conceptual Framework (ICRP Publication 64). Probabilities of exposures greater than 5, 50, and 300 rem were less than 10 -2 , 10 -4 , and 10 -6 per year, respectively. In conformance with the guidance of DOE standard 3009-94, Appendix A (draft), we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposure under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, as well as members of the public and the environment

Study of Determinants of Lung Cancer Protective Behaviors in Esfahan Steel Company Workers Based On Protection Motivation Theory

OpenAIRE

mohammadali Morowatisharifabad; Leila Hadi varnamkhavasti; Mohammadjavad Zare; Hossein Fallahzadeh; zohre Karimiankakolaki

2017-01-01

Introduction: Lung cancer is known the leading cause of death among cancers. Since in our country a comprehensive scientific information not available on the determinants of protective behavior of lung cancer among workers, this study, aimed to examine determinants of lung cancer protective behaviors among Esfahan Steel Company (ESCO) workers based on protection motivation theory. Methods: This cross-sectional study was performed on 253 workers of the ESCO who were randomly selected. In th...

Method and apparatus for determining the dose value of neutrons

International Nuclear Information System (INIS)

Burgkhardt, B.; Piesch, E.

1976-01-01

A method is provided for determining the dose value of neutrons leaving a body as thermal and intermediate neutrons after having been scattered in the body. A first dose value of thermal and intermediate neutrons is detected on the surface of the body by means of a first detector for neutrons which is shielded against thermal and intermediate neutrons not emerging from the body. A second detector is used to measure a second dose value of the thermal and intermediate neutrons not emerging from the body. A first correction factor based on the first and second values is obtained from a calibration diagram and is applied to the first dose value to determine a first corrected first dose value. 21 Claims, 6 Drawing Figures

Workers radiation protection. Occupational exposure to ionizing radiations in France: 2016 results

International Nuclear Information System (INIS)

2017-06-01

National results of the individual monitoring of occupational exposure to ionizing radiation are reported for all civilian and military activities subject to authorization or declaration (i.e. medical and veterinary activities, nuclear industry, defence, non-nuclear industry and research), as well as for activities concerned by the enhanced exposure to natural radiation. 372 262 workers within activities subject to authorization or declaration were monitored by passive dosimetry in 2015, which represents an increase by 1.8 % compared to 2015. The average individual dose in 2016 was very close to the value in 2015. Furthermore, 14 218 workers received more than 1 mSv (i.e. the legal dose limit for the public), and 2 703 workers received more than 5 mSv. 1 worker received more than 20 mSv (i.e. the dose limit for the workers in the French regulation). As a result, the collective dose increased from 61.9 to 63.2 man.Sv (2 %), thus reaching the same level as in the years 2009 to 2013. Important differences are noticed according to the occupational activities: the average dose in the medical and veterinary field (which represents 61.2 % of the monitored workers) and that in the research field (3.1 % of the monitored workers) are less than 0.35 mSv; the average doses are higher in the nuclear field and in the non-nuclear industry (representing together 30.5 % of the monitored workers), respectively 1.15 mSv and 1.36 mSv. Concerning internal dosimetry, 279 659 individual examinations have been performed in 2016, 54 % of which are radio-toxicological analysis of excreta and 46 % are direct body counting. In 2016, 5 workers had a committed effective dose greater than or equal to 1 mSv and the maximum dose was 19.4 mSv. Data or trends relative to workers exposed to natural radioactivity are also dealt with in this report (air-crews, personnel subjected to radon exposure). In particular, results of aircrew dosimetry are reported: in 2016, the average individual dose of 19 875

Workers radiation protection. Occupational exposure to ionizing radiations in France: 2015 results

International Nuclear Information System (INIS)

2016-06-01

National results of the individual monitoring of occupational exposure to ionizing radiation are reported for all civilian and military activities subject to authorization or declaration (i.e. medical and veterinary activities, nuclear industry, defence, non-nuclear industry and research), as well as for activities concerned by the enhanced exposure to natural radiation. 365 830 workers within activities subject to authorization or declaration were monitored by passive dosimetry in 2015, which represents an increase by 1.7 % compared to 2014. The average individual dose in 2015 was very close to the value in 2014. Furthermore, 14 138 workers received more than 1 mSv (i.e. the legal dose limit for the public), and 2 606 workers received more than 5 mSv. 2 workers received more than 20 mSv (i.e. the dose limit for the workers in the French regulation). As a result, the collective dose increased from 56.3 to 61.9 man.Sv (10 %), thus reaching the same level as in the years 2009 to 2013. Important differences are noticed according to the occupational activities: the average dose in the medical and veterinary field (which represents 62.4 % of the monitored workers) and that in the research field (3.6 % of the monitored workers) are less than 0.4 mSv; the average doses are higher in the nuclear field and in the non-nuclear industry (representing together 30.1 % of the monitored workers), respectively 1.17 mSv and 1.38 mSv. Concerning internal dosimetry, 279 877 individual examinations have been performed in 2015, 52 % of which are radio-toxicological analysis of excreta and 48 % are direct body counting. In 2015, 2 workers had a committed effective dose greater than or equal to 1 mSv and the maximum dose was 3 mSv. Data or trends relative to workers exposed to natural radioactivity are also dealt with in this report (air crews, personnel subjected to radon exposure). In particular, results of aircrew dosimetry are reported: in 2015, the average individual dose of 19 565

Recommendations of the ICRP and the workers

International Nuclear Information System (INIS)

1979-01-01

Examination of the different links in the nuclear power generation chain indicated that the mean annual dose exceeded 500 mrem (5mSva -1 ) for workers in uranium mines, nuclear power stations of the light water variety and reprocessing plants. This dose has been consistently exceeded over the past few years. More research is urged into the effects of small radiation doses and the variation of the relative biological effectiveness as a function of dose. The subject of social security for occupational diseases is also discussed with particular respect to the itinerant worker. It is suggested that a mean annual dose of 500 mrem should be incorporated in legislative texts. (U.K.)

Worker safety for occupations affected by the use, transportation and storage of radioactive and hazardous materials

International Nuclear Information System (INIS)

1994-07-01

A study group under the auspices of the National Conference of State Legislatures (NCSL) Labor Committee and the High-level Radioactive Waste/Hazardous Materials Transportation Task Force examined worker protection and safety programs for occupations affected by the use, transportation and storage of radioactive and hazardous materials. Concern about the risks posed to people who live along spent nuclear fuel transportation routes has led to demands for redundant inspections of the transported spent fuel. It would also be prudent to examine the radiological risk to the inspectors themselves before state of federal regulations are promulgated which require redundant inspections. Other workers may also come close to a spent fuel cask during normal operations. The dose rate to which these inspectors and handlers are exposed is higher than the dose rate to which any other group is exposed during incident-free truck transportation and higher than the dose rate to the drivers when they are in the truck cab. This report consists of miscellaneous papers covering topics related to determining radiation doses to workers involved in the transport of radioactive materials

Internal dosimetry contamination: update of revision of the dose coefficients for intakes of radionuclides by workers

International Nuclear Information System (INIS)

Gomez Parada, I.; Rojo, A.M.; Sanguineti, R.

1995-01-01

ICRP publication 60 introduces new biological information related to the detriment associated with radiation exposures. The International Commission on Radiological Protection has also issued, in publications 57, 67 y 69, new biokinetic models for selected radionuclides since the issue of publication 30. In publication 66 the new human respiratory tract model for radiological protection is described. The aim of the present paper is to compare values of dose coefficients for workers calculated using the new tissue weighting factors, biokinetic models and lung model with those given in publication 30.The software package LUPED 1.1 was used to calculate dose coefficients for inhalation and ingestion. When possible, some changes in the biokinetic models were made trying to incorporate new parameters. The following radionuclides were analysed: 60 Co, 90 Sr, 99m Tc, 131 I, 137 Cs, 239 Pu y 241 Am. Most of the inhalation dose coefficients calculated with the new assumptions are within a factor of three of those calculated using the ICRP 30 lung and biokinetic models. Generally, the inhalation dose coefficients calculated with the new respiratory tract model and assuming a 5μm AMAD are lower than those calculated using the ICRP 30 model and parameters. The inhalation dose coefficients are generally within 10-90 % of the corresponding Publication 61 values, the difference tending to increase for relative insoluble compounds. (author). 10 refs., 4 tabs

TLD personnel monitoring dose estimation- extending the upper limit of the dose range

International Nuclear Information System (INIS)

Popli, K.L.; Sathian, Deepa; Divakaran, T.; Massand, O.P.

2001-01-01

TLD personnel monitoring was introduced in the year 1975 in India and at present nearly 41,000 radiation workers are being monitored by 13 monitoring laboratories all over India. The BARC- TLD being used for personnel monitoring is based on CaSO 4 :Dy embedded in PTFE and semi-automatic TL reader using hot N 2 Gas for heating the dosimeters. This reader has the range to measure γ dose from ten μSv to 3 μSv and x-ray dose form 1 μ Sv to 0.3 Sv due to the higher sensitivity of CaSO 4 : Dy to lower energy photons (20keV-50 keV) generated by diagnostic x-ray units. The x-ray radiation workers are at present nearly 35% of the total radiation workers monitored and this number is expected to grow as more and more number of x-ray workers are covered under this service. The upper limit of the x-ray dose range of the instrument is 0.3 Sv, whereas in the past one year it has been observed that at least 25% of the total overexposures reported in case of x-ray workers have recorded the dose more than 0.3 Sv. This paper presents the technique developed to extend the upper limit of the range from 0.3 Sv to 1 Sv for x-rays and 10 Sv for γ rays

Evaluating the Influence of Nutrition Determinants on Construction Workers' Food Choices.

Science.gov (United States)

Okoro, Chioma Sylvia; Musonda, Innocent; Agumba, Justus

2017-11-01

Nutritional knowledge as well as economic, social, biological, and cultural factors have been known to determine an individual's food choices. Despite the existence of research on the factors which influence nutrition globally, there is little known about the extent to which these factors influence the food choices of construction workers, which in turn influence their health and safety during construction activities. The present article investigates the extent to which construction workers' nutrition is influenced by nutritional knowledge, as well as economic, environmental, social, psychological, and physiological factors. A field questionnaire survey was conducted on site construction workers in the Gauteng Province of South Africa. Principal components analysis and multiple regression analysis were used to analyze the data. Findings revealed that consumption of foods termed alternative foods including dairy products, eggs, nuts, fish, and cereals, was influenced by nutritional knowledge and resources. Foods termed traditional core foods were influenced by cultural background; foods termed secondary core foods comprising fruits and vegetables were influenced by economic factors, resources, and cultural background; while foods termed core foods were mostly influenced by nutritional knowledge. By providing evidence of the factors which most influence selection and consumption of certain foods by construction workers, relevant nutrition interventions will be designed and implemented, taking cognizance of these factors.

Establishment of a networked national occupational dose registry system (NODRS)

International Nuclear Information System (INIS)

Mayya, Y.S.

2010-01-01

Maintenance of occupational dose data of radiation workers is a mandatory requirement of the Indian Protection Program. It is now planned to introduce online fingerprint comparison, for a quick and easy identification of an existing radiation worker. An analysis of occupational dose trends in the non-DAE sector has been initiated to help in improvement of work practices so that doses received by the workers are kept well below the dose limits

Determination of environmental radioactivity for dose assessment

International Nuclear Information System (INIS)

Nakoaka, A.; Fukushima, M.; Takagi, S.

1980-01-01

A method was devised to determine detection limits for radioactivity in environmental samples. The method is based on the 5 mrem/yr whole-body dose objective established by the Japan Atomic Enerty Commission and is valid for assessing the internal dose from radionuclides in the environment around a nuclear facility. Eleven samples and 15 radionuclides were considered. Internal dose was assumed to be one-half of the total dose (5 mrem/yr) and was assessed using the critical pathway method. Needed detection limits (NDLs) were established to confirm the dose of 5 mrem/yr when there was more than one radionuclide per sample. The NDLs for γ-emitters were 10 -5 pCi/l. for air; 10 -3 pCi/l. for seawater; 10 -1 pCi/l. for drinking water; 10 0 pCi/kg for vegetables and fish; 10 0 pCi/l. for milk; and 10 1 pCi/kg for molluscs, crustaceans, seaweeds, soil and submarine sediments. The NDLs for β-emitters were 1-1/100 of those for γ-emitters. (author)

Dose constraint for Industrial gammagraphy developed by regulatory authorities

International Nuclear Information System (INIS)

Salinas Mariaca, Rodrigo

2008-01-01

Aware that the dose limitation established by the Basic Safety Standards, is one of the radiation protection requirements necessary but not sufficient; and also aware that given the characteristics of the different practices and the culture of security already achieved in such practices, the workers occupationally exposed are far below from the respective limits. It becomes imperative to improve and exploit another of the requirements established by the referred standards, which is the Dose Constraint. This job takes as a basis the dose history having in the Bolivian Authority in nuclear issues, referred to the practices related to Nuclear Gauges, Well Logging, Radiotherapy and Industrial Gammagraphy (practices considered dangerous). This analysis is intended to be the pivot for the remainder practices and had as its goal, the establishment of a specific dose constraint value. The dose constraint suggested for every practices studied, were determined considering the percentile 95 and with the logic that if that 95% are able to achieve certain values of effective dose, the other 5% should be able to adapt their working conditions in order to decrease their doses. The spread of this work is intended not only aware, to other regulatory bodies to achieve a symbiosis between the different requirements of the Standard, but basically emphasize the fact that it is not convenient let the requirement of dose constraint exclusively in the hands of the regulated institutions and associated workers; making it, very subjective among those institutions according to their analysis (many times with no statistical support). Furthermore these dose constraint values should be determined previously to a new practice authorization or failing shortly after its implementation. (author)

Health management of radiation workers

International Nuclear Information System (INIS)

Kunugita, Naoki; Igari, Kazuyuki

2013-01-01

People in Japan have expressed great anxiety about possible radiation and radioactivity after the accident at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company's (TEPCO), due to the great earthquake and tsunami in eastern Japan on 11 March 2011. A large number of workers were engaged in response and recovery operations, and they were possibly exposed to high doses of radiation as compared to the general population. In the accident at the Chernobyl Nuclear Power Plant in 1986, high doses of radiation to 134 plant staff and emergency personnel resulted in acute radiation syndrome (ARS), which proved fatal for 28 of them. In the Fukushima accident, six workers were exposed to more than 250 mSv of radiation during the initial response phase, but no one showed ARS. It is necessary to continue registration of radiation doses for all workers who were exposed to radiation to facilitate suitable healthcare management in the future. In addition to radiation exposure, a group of workers were also exposed to other health hazards. Frequent occurrence of heat disorders has been a concern for the workers wearing protective clothing with poor ventilation. A comprehensive program to prevent heat illness was implemented by TEPCO under the guidance of the Ministry of Health, Labour, and Welfare. It is important to provide effective systems not only for prevention of radiation exposure but also for general management of other health risks including heat disorders and infection. (author)

Networked National Occupational Dose Registry System (NODRS)

International Nuclear Information System (INIS)

Sapra, B.K.

2016-01-01

Recording of occupational doses received by radiation workers during their working life is a mandatory aspect of radiation protection. Maintaining of life-time dose data of these radiation workers is also necessary for (i) ensuring and reviewing radiation safety of workers, (ii) certification and other legal purposes, and (iii) for statistical analysis and epidemiological studies. Centralized dose records are being maintained by BARC since the inception of Directorate of Radiation Protection in late sixties. The dose records were computerized since 1975 and the systems were upgraded from time to time. The requirement of personnel data information was made a pre-requisite for allotment of personnel number to new persons for TLD Badge services since 1992

Development of posture-specific computational phantoms using motion capture technology and application to radiation dose-reconstruction for the 1999 Tokai-Mura nuclear criticality accident

International Nuclear Information System (INIS)

Vazquez, Justin A; Caracappa, Peter F; Xu, X George

2014-01-01

The majority of existing computational phantoms are designed to represent workers in typical standing anatomical postures with fixed arm and leg positions. However, workers found in accident-related scenarios often assume varied postures. This paper describes the development and application of two phantoms with adjusted postures specified by data acquired from a motion capture system to simulate unique human postures found in a 1999 criticality accident that took place at a JCO facility in Tokai-Mura, Japan. In the course of this accident, two workers were fatally exposed to extremely high levels of radiation. Implementation of the emergent techniques discussed produced more accurate and more detailed dose estimates for the two workers than were reported in previous studies. A total-body dose of 6.43 and 26.38 Gy was estimated for the two workers, who assumed a crouching and a standing posture, respectively. Additionally, organ-specific dose estimates were determined, including a 7.93 Gy dose to the thyroid and 6.11 Gy dose to the stomach for the crouching worker and a 41.71 Gy dose to the liver and a 37.26 Gy dose to the stomach for the standing worker. Implications for the medical prognosis of the workers are discussed, and the results of this study were found to correlate better with the patient outcome than previous estimates, suggesting potential future applications of such methods for improved epidemiological studies involving next-generation computational phantom tools. (paper)

Vaccination coverage among social and healthcare workers in ten countries of Samu-social international sites.

Science.gov (United States)

Marshall, Esaie; Salmon, Dominique; Bousfiha, Nadia; Togola, Yacouba; Ouedraogo, François; Santantonio, Maud; Dieng, Coumba Khadidja; Tartière, Suzanne; Emmanuelli, Xavier

2017-09-18

We aim to determine the vaccination coverage of social and healthcare workers in International sites of Samusocial, providing emergency care to homeless people, and to assess factors associated with having received necessary doses at adulthood. Data on immunization coverage of social and healthcare workers were provided by a cross-sectional survey, conducted from February to April 2015 among 252 Samusocial workers in 10 countries. Vaccination status and characteristics of participants were collected through a self-administered questionnaire. Prevalence rate ratio (PRR) of vaccination status was calculated using Poisson regression models. Among 252 Samusocial social and health workers who felt a questionnaire, median age was 39years, 42.1% were female, 88.9% were in contact with homeless beneficiaries (19.1% health workers). Overall, 90.1% of Samusocial staff felt adult vaccinations was useful and 70.2% wished to receive booster doses in future. Vaccination coverage at adulthood was satisfactory for diphtheria and poliomyelitis (96%), but low for influenza (20.8%), meningococcus (50.5%), hepatitis B (56.3%), yellow fever (58.1%), measles (81.3%) and pertussis (90.7%). The main reasons for not having received vaccination booster doses were forgetting the dates of booster doses (38.4%) and not having received the information (13.5%). In adjusted analysis, prevalence of up-to-date for vaccination schedule was 35% higher among health workers than among social workers (aPRR=1.35, 95%CI: 1.01-1.82, P=0.05) and was 56% higher among workers who had a documentary evidence of vaccination than in those who did not (aPRR=1.56, 95%CI: 1.19-2.02, P=0.001). The Samusocial International workers vaccine coverage at adulthood was insufficient and disparate by region. It is necessary to strengthen the outreach of this staff and increase immunization policy for hepatitis B, diphtheria, tetanus, and measles, as well as for yellow fever, rabies and meningococcal ACYW135 vaccines in at

An investigation into psychological stress and its determinants in Xinjiang desert oil workers

Science.gov (United States)

Ning, Li; Guan, Suzhen; Liu, Jiwen

2018-01-01

Abstract The present study aims to investigate psychological stress and its determinants in Xinjiang field oil workers. Specifically, we aim to elucidate the mechanisms underlying psychological stress by comprehensively and quantitatively evaluating the processes involved in psychological stress, the factors which influence it, and their relationship. The participants were 1200 field oil workers in Xinjiang who had been in service for at least 1 year. A structural equation model based on data from the symptom checklist, social support research scale, personality questionnaire, occupational burnout questionnaire, and occupational stress questionnaire was constructed to investigate the social (environmental) factors that influence physiological stress and the interplay among these factors. The positive incidence of psychological stress in the field oil workers in Xinjiang was 12.54%. The structural equation model indicated that the main factors that influenced psychological stress in these workers included social support (0.077), occupational role (0.165), personal strain response (0.139), personality (0.189), and occupational burnout (0.380). Among these factors, occupational role, personality, and occupational burnout had a relatively strong predictive power for psychological stress reactions. The cortisol level in workers with positive psychological stress was significantly higher than that in workers with negative psychological stress. Occupational stress, personality, and occupational burnout exert an impact on psychological stress in field oil workers. Therefore, interventions to address these factors should be taken to reduce the incidence of psychological stress. PMID:29642166

Management and processing of dosimetric data of workers exposed to ionizing radiation

International Nuclear Information System (INIS)

Rasoarimalala, T.

2012-01-01

The Madagascar - INSTN Radiation protection and Dosimetry Department use the reader HARSHAW TLD 6600 for workers doses reading. Although the performance of this device, manual works is required to store and to maintain the dosimetric data after reading and to note the TLDs sent to the establishments. To avoid these manual works, this present work proposes computer programs written in Python and using SQLite software. One of the programs in python retrieves dose values after reading and transfers directly these doses in the workers database. The use of SQLite software provides a way for the dosimetric data management and the TLDs movement monitoring. The other program assesses estimation of the dose received by worker through a trend curve for workers dosimetric monitoring. The calculated differences of this curve over the curve connecting all points are less than 20%, acceptable limit in radiation protection for TLDs. This present work presents then significances for the personnel occupying individual monitoring of ionizing radiation workers and for these workers too. [fr

Occupational dose trends in Tanzania

International Nuclear Information System (INIS)

Muhogora, W.E.; Nyanda, A.M.; Ngaile, J.E.; Lema, U.S.

1998-01-01

This paper describes the present status of occupational radiation exposure of monitored workers in Tanzania from 1986 to 1997. The analysis of dose records observes over this period, a fluctuating trend both in the individual and collective doses. The trend is more related to the fluctuations of the number of radiation workers than to the possible radiation safety changes of the working conditions. It has been found that, the maximum annual dose for the worker in all work categories was about 18 mSv y -1 . This suggests that the occupational radiation exposure in all practices satisfies the current dose limitation system. The national exposure summary shows that, the highest collective dose of 12.8 man-Sv which is 90% of the total collective dose, was due to medical applications. The applications in industry and research had a contribution of nearly 0.8 and 0.7 man-Sv respectively. From the professional point of view, the medical diagnostic radiographers received the highest collective dose of 11.2 man-Sv. Although the medical physicists recorded the minimum collective dose of nearly 0.07 man-Sv, the data shows that this profession received the highest mean dose of about 33 mSv in 12 years. Some achievements of the personnel monitoring services and suggestions for future improvement are pointed out. (author)

Fast neutron radiation inactivation of Bacillus subtilis: Absorbed dose determination

International Nuclear Information System (INIS)

Song Lingli; Zheng Chun; Ai Zihui; Li Junjie; Dai Shaofeng

2011-01-01

In this paper, fast neutron inactivation effects of Bacillus subtilis were investigated with fission fast neutrons from CFBR-II reactor of INPC (Institute of Nuclear Physics and Chemistry) and mono-energetic neutrons from the Van de Graaff accelerator at Peking University. The method for determining the absorbed dose in the Bacillus subtilis suspension contained in test tubes is introduced. The absorbed dose, on account of its dependence on the volume and the form of confined state, was determined by combined experiments and Monte Carlo method. Using the calculation results of absorbed dose, the fast neutron inactivation effects on Bacillus subtilis were studied. The survival rates and absorbed dose curve was constructed. (authors)

Determinants of condom breakage among female sex workers in Karnataka, India.

Science.gov (United States)

Bradley, Janet; Rajaram, S; Alary, Michel; Isac, Shajy; Washington, Reynold; Moses, Stephen; Ramesh, B M

2011-12-29

Condoms are effective in preventing the transmission of HIV and other sexually transmitted infections, when properly used. However, recent data from surveys of female sex workers (FSWs) in Karnataka in south India, suggest that condom breakage rates may be quite high. It is important therefore to quantify condom breakage rates, and examine what factors might precipitate condom breakage, so that programmers can identify those at risk, and develop appropriate interventions. We explored determinants of reported condom breakage in the previous month among 1,928 female sex workers in four districts of Karnataka using data from cross-sectional surveys undertaken from July 2008 to February 2009. Using stepwise multivariate logistic regression, we examined the possible determinants of condom breakage, controlling for several independent variables including the district and client load. Overall, 11.4% of FSWs reported at least one condom break in the previous month. FSWs were much more likely to report breakage if under 20 years of age (AOR 3.43, p = 0.005); if divorced/ separated/widowed (AOR 1.52, p = 0.012); if they were regular alcohol users (AOR 1.63, p = 0.005); if they mostly entertained clients in lodges/rented rooms (AOR 2.99, p = 0.029) or brothels (AOR 4.77, p = 0.003), compared to street based sex workers; if they had ever had anal sex (AOR 2.03, p = 0.006); if the sex worker herself (as opposed to the client) applied the condom at last use (AOR 1.90, p < 0.001); if they were inconsistent condom users (AOR 2.77, p < 0.001); and if they had never seen a condom demonstration (AOR 2.37, p < 0.001). The reported incidence of condom breakage was high in this study, and this is a major concern for HIV/STI prevention programs, for which condom use is a key prevention tool. Younger and more marginalized female sex workers were most vulnerable to condom breakage. Special effort is therefore required to seek out such women and to provide information and skills on correct

Immune cells in Chernobyl radiation workers exposed to low-dose irradiation

International Nuclear Information System (INIS)

Bazyka, D.; Chumak, A.; Byelyaeva, N.; Gulaya, N.; Margytich, V.; Thevenon, C.; Guichardant, M.; Lagarde, M.

2002-01-01

the aim of this work was to study immune response parameters in Chernobyl emergency and recovery operation radiation workers and nuclear industry workers exposed under professional limits. The monohydroxylated fatty acid content in peripheral blood mononuclear cell of radiation workers compared to unexposed control at the 12-th year after Chernobyl NPP accident was studied too

A practical approach to determine dose metrics for nanomaterials.

Science.gov (United States)

Delmaar, Christiaan J E; Peijnenburg, Willie J G M; Oomen, Agnes G; Chen, Jingwen; de Jong, Wim H; Sips, Adriënne J A M; Wang, Zhuang; Park, Margriet V D Z

2015-05-01

Traditionally, administered mass is used to describe doses of conventional chemical substances in toxicity studies. For deriving toxic doses of nanomaterials, mass and chemical composition alone may not adequately describe the dose, because particles with the same chemical composition can have completely different toxic mass doses depending on properties such as particle size. Other dose metrics such as particle number, volume, or surface area have been suggested, but consensus is lacking. The discussion regarding the most adequate dose metric for nanomaterials clearly needs a systematic, unbiased approach to determine the most appropriate dose metric for nanomaterials. In the present study, the authors propose such an approach and apply it to results from in vitro and in vivo experiments with silver and silica nanomaterials. The proposed approach is shown to provide a convenient tool to systematically investigate and interpret dose metrics of nanomaterials. Recommendations for study designs aimed at investigating dose metrics are provided. © 2015 SETAC.

Determination of the radiation dose to the body due to external radiation

International Nuclear Information System (INIS)

Drexler, G.; Eckerl, H.

1985-01-01

Section 63 of the Radiation Protection Ordinance defines the basic requirement, determination of radiation dose to the body. The determination of dose equivalents for the body is the basic step in practical monitoring of dose equivalents or dose limits with regard to individuals or population groups, both for constant or varying conditions of exposure. The main field of monitoring activities is the protection of persons occupationally exposed to ionizing radiation. Conversion factors between body doses and radiation quantities are explained. (DG) [de

The uniform application of ALARA to all radiation workers

International Nuclear Information System (INIS)

Pomroy, C.

1988-05-01

New information on the dosimetry and epidemiology of atomic bomb survivors suggests that risk estimates may have to be revised upwards. This has focussed increased attention on the ALARA principle. The ICRP believes that ALARA principle is the driving force in keeping average radiation doses low. In practice, the optimization process required for ALARA varies between different sectors of the nuclear industry. For instance, the power utilities have developed procedures for comparing different dose reduction options. Similarly, uranium mine operators have applied optimization techniques to questions concerning ventilation and shielding of ore trucks. Missing from this list however, is the use of a formal optimizing technique in medical and research uses of radioactivity or radiation. Nonetheless, average annual doses to these workers are quite low. An alternative approach to optimization calculation has been suggested, entailing the identification of sub-groups of workers with substantially higher doses to discover the reasons for the higher doses, and to develop means to reduce them to the overall average. Thus maintenance mechanics in nuclear reactors, by the very nature of their jobs, have more potential for higher dose. The utilities are developing procedures to reduce the maintenance mechanics' doses. If the same analysis is applied to medical workers, it is seen that isotope technicians and therapeutic radiology technicians have average doses well above the overall average. The feasibility of some form of optimization process for these categories of workers is discussed

A single-aliquot OSL protocol using bracketing regenerative doses to accurately determine equivalent doses in quartz

CERN Document Server

Folz, E

1999-01-01

In most cases, sediments show inherent heterogeneity in their luminescence behaviours and bleaching histories, and identical aliquots are not available: single-aliquot determination of the equivalent dose (ED) is then the approach of choice and the advantages of using regenerative protocols are outlined. Experiments on five laboratory bleached and dosed quartz samples, following the protocol described by Murray and Roberts (1998. Measurement of the equivalent dose in quartz using a regenerative-dose single aliquot protocol. Radiation Measurements 27, 171-184), showed the hazards of using a single regeneration dose: a 10% variation in the regenerative dose yielded some equivalent dose estimates that differed from the expected value by more than 5%. A protocol is proposed that allows the use of different regenerative doses to bracket the estimated equivalent dose. The measured ED is found to be in excellent agreement with the known value when the main regeneration dose is within 10% of the true equivalent dose.

A single-aliquot OSL protocol using bracketing regenerative doses to accurately determine equivalent doses in quartz

International Nuclear Information System (INIS)

Folz, Elise; Mercier, Norbert

1999-01-01

In most cases, sediments show inherent heterogeneity in their luminescence behaviours and bleaching histories, and identical aliquots are not available: single-aliquot determination of the equivalent dose (ED) is then the approach of choice and the advantages of using regenerative protocols are outlined. Experiments on five laboratory bleached and dosed quartz samples, following the protocol described by Murray and Roberts (1998. Measurement of the equivalent dose in quartz using a regenerative-dose single aliquot protocol. Radiation Measurements 27, 171-184), showed the hazards of using a single regeneration dose: a 10% variation in the regenerative dose yielded some equivalent dose estimates that differed from the expected value by more than 5%. A protocol is proposed that allows the use of different regenerative doses to bracket the estimated equivalent dose. The measured ED is found to be in excellent agreement with the known value when the main regeneration dose is within 10% of the true equivalent dose

Evaluation of personal dose equivalent 'HP(d)' in a external individual monitoring system for X and gamma radiation

International Nuclear Information System (INIS)

Santoro, C.; Antonio Filho, J.; Santos, M.A.P.

2007-01-01

The good of individual monitoring for external radiation is the assessment of occupational exposure from X and γ radiations in order to assure that the radiological conditions of the workplace are acceptable, safe and satisfactory. The evaluation of radiations doses for workers must not exceed dose limits specified for workers, according to national regulatory agencies. Nowadays, there are two external monitoring systems in use, both based on ICRU definitions. In the conventional system, the workers doses are evaluated in terms of Hx. The personal dosimeter is worn over chest surface and it is calibrated in function of air kerma. In the new system, the workers doses are evaluated in terms of HP(d) and the personal dosimeter is calibrated in function of phantom doses. The aim of this paper is to adapt an external dosimetry laboratory (based on photographic dosimetry) to evaluate the personal dosimeters in terms of HP(d). In this way, a simple methodology, based on linear programming, was utilized. In this adaptation, calibration curves were obtained for radiation qualities (W and N series) described by International Organization for Standardization (ISO 4037-1, 1995). These calibration curves offer a better accuracy on dose determinations and energy below 140 keV, improving the quality of service rendered the society. (author)

Extremity doses to interventional radiologists

International Nuclear Information System (INIS)

Wihtby, M.; Martin, C. J.

2002-01-01

Radiologists performing interventional procedures are often required to stand close to the patient's side when carrying out manipulations under fluoroscopic control. This can result in their extremities receiving a high radiation dose, due to scattered radiation. These doses are sometimes high enough to warrant that the radiologist in question be designated a classified radiation worker. Classification in the UK is a result of any worker receiving or likely to receive in the course of their duties in excess of 3/10ths of any annual dose limit (500mSv to extremities, skin). The doses to the legs of radiologists have received less attention than those to the hands, however the doses may be high, due to the proximity of the legs and feet to scattered radiation. The legs can be exposed to a relatively high level of scattered radiation as the radiation in produced from scatter of the un attenuated beam from the bottom of the patient couch. The routine monitoring of extremity doses in interventional radiology is difficult due to several factors. Firstly a wide range of interventional procedures in undertaken in every radiology department, and these procedures require many different techniques, equipment and skills. This means that the position the radiologist adopts in relation to scattering medium and therefore their exposure, depends heavily on the type of procedure. As the hands which manipulate the catheters within the patient are often located close to the patients side and to the area under irradiation, the distribution of dose across the hands can be variable, with very high localised doses, making routine monitoring difficult. The purpose of this study was to determine the magnitude and distribution of dose to the hands and legs of interventional radiologists carrying out a wide range of both diagnostic and therapeutic interventional procedures. To ascertain the most effective method of monitoring the highest dose in accordance with the Basic safety standards

Estimation of annual radiation dose received by some industrial workers

International Nuclear Information System (INIS)

Garg, Ajay; Chauhan, R.P.; Kumar, Sushil

2013-01-01

Radon and its progeny in the atmosphere, soil, ground water, oil and gas deposits contributes the largest fraction of the natural radiation dose to populations, enhanced interest exhibited in tracking its concentration is thus fundamental for radiation protection. The combustion of coal in various industrial units like thermal power plants. National fertilizer plants, paper mill etc. results in the release of some natural radioactivity to the atmosphere through formation of fly ash and bottom ash or slag. This consequent increases the radioactivity in soil, water and atmosphere around thermal power plants. Keeping this in mind the measurements of radon, thoron and their progeny concentration in the environment of some industrial units has been carried out using solid state nuclear track detectors (SSNTD). The specially designed twin cup dosimeter used here consists two chambers of cylindrical geometry separated by a wall in the middle with each having length of 4.5 cm and radius of 3.1 cm. This dosimeter employs three SSNTDs out of which two detectors were placed in each chamber and a third one was placed on the outer surface of the dosimeter. One chamber is fitted with glass fiber filter so that radon and thoron both can diffuse into the chamber while in other chamber, a semi permeable membrane is used. The membrane mode measures the radon concentration alone as it can diffuse through the membrane but suppresses the thoron. The twin cup dosimeter also has a provision for bare mode enabling it to register tracks due to radon, thoron and their progeny in total. Therefore, using this dosimeter we can measure the individual concentration of radon, thoron, and their progeny at the same time. The annual effective doses received by the workers in some industrial units has been calculated. The results indicate some higher levels in coal handling and fly ash area of the plants. (author)

Bremsstrahlung doses from natural uranium ingots

International Nuclear Information System (INIS)

Anderson, J. L.; Hertel, N. E.

2005-01-01

In the past, some privately owned commercial facilities in the United States were involved in producing or processing radioactive materials used in the production of atomic weapons. Seven different geometrical objects, representative of the configurations of natural uranium metal potentially encountered by workers at these facilities, are modelled to determine gamma ray and Bremsstrahlung dose rates. The dose rates are calculated using the MCNP5 code and also by using the MICROSHIELD point-kernel code. Both gamma ray and Bremsstrahlung dose rates are calculated and combined to obtain a total dose rate. The two methods were found to be in good agreement despite differences in modelling assumptions and method differences. Computed total dose rates on the surface of these objects ranged from ∼51-84 μSv h -1 and 17-95 μSv h -1 using the MCNP5 and the MICROSHIELD modeling, respectively. The partitioning of the computed dose rates between gamma rays and Bremsstrahlung were the same order of magnitude for each object. (authors)

Bremsstrahlung doses from natural uranium ingots.

Science.gov (United States)

Anderson, Jeri L; Hertel, Nolan E

2005-01-01

In the past, some privately owned commercial facilities in the United States were involved in producing or processing radioactive materials used in the production of atomic weapons. Seven different geometrical objects, representative of the configurations of natural uranium metal potentially encountered by workers at these facilities, are modelled to determine gamma ray and bremsstrahlung dose rates. The dose rates are calculated using the MCNP5 code and also by using the MICROSHIELD point-kernel code. Both gamma ray and bremsstrahlung dose rates are calculated and combined to obtain a total dose rate. The two methods were found to be in good agreement despite differences in modelling assumptions and method differences. Computed total dose rates on the surface of these objects ranged from approximately 51-84 microSv h(-1) and 17-95 microSv h(-1) using the MCNP5 and the MICROSHIELD modeling, respectively. The partitioning of the computed dose rates between gamma rays and bremsstrahlung were the same order of magnitude for each object.

Occupational dose assessment and national dose registry system in Iran

International Nuclear Information System (INIS)

Jafari-Zadeh, M.; Nazeri, F.; Hosseini-Pooya, S. M.; Taheri, M.; Gheshlaghi, F.; Kardan, M. R.; Babakhani, A.; Rastkhah, N.; Yousefi-Nejad, F.; Darabi, M.; Oruji, T.; Gholamali-Zadeh, Z.; Karimi-Diba, J.; Kazemi-Movahed, A. A.; Dashti-Pour, M. R.; Enferadi, A.; Jahanbakhshian, M. H.; Sadegh-Khani, M. R.

2011-01-01

This report presents status of external and internal dose assessment of workers and introducing the structure of National Dose Registry System of Iran (NDRSI). As well as types of individual dosemeters in use, techniques for internal dose assessment are presented. Results obtained from the International Atomic Energy Agency intercomparison programme on measurement of personal dose equivalent H p (10) and consistency of the measured doses with the delivered doses are shown. Also, implementation of dosimetry standards, establishment of quality management system, authorisation and approval procedure of dosimetry service providers are discussed. (authors)

Doses from radiation exposure

International Nuclear Information System (INIS)

Menzel, H-G.; Harrison, J.D.

2012-01-01

Practical implementation of the International Commission on Radiological Protection’s (ICRP) system of protection requires the availability of appropriate methods and data. The work of Committee 2 is concerned with the development of reference data and methods for the assessment of internal and external radiation exposure of workers and members of the public. This involves the development of reference biokinetic and dosimetric models, reference anatomical models of the human body, and reference anatomical and physiological data. Following ICRP’s 2007 Recommendations, Committee 2 has focused on the provision of new reference dose coefficients for external and internal exposure. As well as specifying changes to the radiation and tissue weighting factors used in the calculation of protection quantities, the 2007 Recommendations introduced the use of reference anatomical phantoms based on medical imaging data, requiring explicit sex averaging of male and female organ-equivalent doses in the calculation of effective dose. In preparation for the calculation of new dose coefficients, Committee 2 and its task groups have provided updated nuclear decay data (ICRP Publication 107) and adult reference computational phantoms (ICRP Publication 110). New dose coefficients for external exposures of workers are complete (ICRP Publication 116), and work is in progress on a series of reports on internal dose coefficients to workers from inhaled and ingested radionuclides. Reference phantoms for children will also be provided and used in the calculation of dose coefficients for public exposures. Committee 2 also has task groups on exposures to radiation in space and on the use of effective dose.

Performance of thermoluminescent materials for high dose dosimetry

International Nuclear Information System (INIS)

Texeira, Maria I.; Cecatti, Sonia G.P.; Caldas, Linda V.E.

2008-01-01

Cases involving high-doses of ionizing radiation are becoming increasingly common.The objective of this work was to characterize thermoluminescent materials for the dosimetry of workers exposed to high doses. Samples of TLD-200, TLD-400 and TLD-800 pellets from Thermo Electron Corporation were studied in gamma high-doses. Dose-response curves were obtained for doses between 100 mGy and 100 Gy. The reproducibility, the lower detection limits and dose-response curves were obtained for all three materials. The different kinds of detectors show usefulness for dosimetry of workers exposed accidentally to high doses. (author)

Personal Doses Recorded by Service of Personal Dosimetry

International Nuclear Information System (INIS)

Mihai, F.; Gheorghiu, A.; Stochioiu, A.; Udup, E.

2009-01-01

In this work we present occupational exposure statistics on: number of workers on different dose ranges; average of the mean annual doses (MAD) over the period 2000 - 2007 on all monitored workers as well as on those who have been received doses over the minimum detection limit (MDL). The statistic is made on different types of nuclear laboratories. The data are obtained on almost 1000 workers occupational exposure to different sources of radiations (gamma and X-ray) and monitored by Photo dosimetry Survey Unit, IFIN - HH. These results point out the evolution of the individual doses received during eight years and can be used to analyse the need of radiation protection in different nuclear facilities from Romania

Determination of tolerance dose uncertainties and optimal design of dose response experiments with small animal numbers

International Nuclear Information System (INIS)

Karger, C.P.; Hartmann, G.H.

2001-01-01

Background: Dose response experiments aim to determine the complication probability as a function of dose. Adjusting the parameters of the frequently used dose response model P(D)=1/[1+(D 50 /D) k ] to the experimental data, 2 intuitive quantities are obtained: The tolerance dose D 50 and the slope parameter k. For mathematical reasons, however, standard statistic software uses a different set of parameters. Therefore, the resulting fit parameters of the statistic software as well as their standard errors have to be transformed to obtain D 50 and k as well as their standard errors. Material and Methods: The influence of the number of dose levels on the uncertainty of the fit parameters is studied by a simulation for a fixed number of animals. For experiments with small animal numbers, statistical artifacts may prevent the determination of the standard errors of the fit parameters. Consequences on the design of dose response experiments are investigated. Results: Explicit formulas are presented, which allow to calculate the parameters D 50 and k as well as their standard errors from the output of standard statistic software. The simulation shows, that the standard errors of the resulting parameters are independent of the number of dose levels, as long as the total number of animals involved in the experiment, remains constant. Conclusion: Statistical artifacts in experiments containing small animal numbers may be prevented by an adequate design of the experiment. For this, it is suggested to select a higher number of dose levels, rather than using a higher number of animals per dose level. (orig.) [de

The determination of effective doses from the intake of tritiated water

International Nuclear Information System (INIS)

1987-08-01

To comply with the regulatory requirements relating to the dose from exposures to tritiated water (HTO), Atomic Energy Control Board (AECB) licensees currently measure tritium concentration in urine to determine whole body dose. This approach has been based on the consideration that the time-integrated tritium concentration (which is proportional to accumulated dose) in any organ from urine concentrations are always conservative. The International Commission on Radiological Protection (ICRP) recommends that the average soft tissue dose be used to determine effective dose equivalents for HTO exposures. The ICRP also recommends that only the retention in body water be considered when committed doses from HTO exposures are calculated; this recommendation is based on the consideration that the errors introduced by neglecting the long-lived tritium component (those tritium atoms retained in organic molecules of the body cells) are small (only of the order of 10% of the committed dose equivalent to the whole body). The AECB position is presented in the following regulatory policy statement

The informed radiation worker and fetal dose policies

International Nuclear Information System (INIS)

Harshaw, F.B.

1991-01-01

The role of women in a workplace in which radioactive materials and radiation producing equipment are used has never been more controversial than it is now. So important, in fact, has this become that the Supreme Court has decided to hear a case that will have major implication not only for female radiation worker but for all employers and certainly for all health physicist involved in attempting to set a reasonable policy for the female worker and her potential for pregnancy. In this paper, a review of the recent BEIR V information and the UNSCEAR data will be made as well as a review of fetal development. Also, the ALARA requirements will be reviewed. Finally, risk perception will be discussed

Dose limits

International Nuclear Information System (INIS)

Fitoussi, L.

1987-12-01

The dose limit is defined to be the level of harmfulness which must not be exceeded, so that an activity can be exercised in a regular manner without running a risk unacceptable to man and the society. The paper examines the effects of radiation categorised into stochastic and non-stochastic. Dose limits for workers and the public are discussed

Measurement and research of the exposure doses of the animal guardians and radiation workers in the animal hospital in Gwangju

International Nuclear Information System (INIS)

Kang, Ji Seung; Yun, Seon Yeong; Yeo, Hwa Yeon; Dong, Kyung Rae

2016-01-01

In modern society, having companion animals as family members is getting popular. According to the data from National Statistical Office, the population of people with companion animals and pets is now over 10 million. The increase of companion animals led to an increase of animal hospitals. Accordingly, radiation generating devices for diagnosis are being used frequently. In addition, as animal hospitals are increasingly using radiation generating devices, in order to protect the related workers and promote animal cares, the government enacted the regulations relating to operations and installations of the devices at animal hospitals. Therefore, this study handles the radiation safety management related stuffs by measuring and assessing radiation dose to the animal guardians and radiation workers in the animal hospitals in Gwangju

Measurement and research of the exposure doses of the animal guardians and radiation workers in the animal hospital in Gwangju

Energy Technology Data Exchange (ETDEWEB)

Kang, Ji Seung; Yun, Seon Yeong; Yeo, Hwa Yeon [Dept. of Radiology, Nambu University, Gwangju (Korea, Republic of); Dong, Kyung Rae [Dept. of of Radiological Technology, Gwangju Health University, Kwangju (Korea, Republic of)

2016-11-15

In modern society, having companion animals as family members is getting popular. According to the data from National Statistical Office, the population of people with companion animals and pets is now over 10 million. The increase of companion animals led to an increase of animal hospitals. Accordingly, radiation generating devices for diagnosis are being used frequently. In addition, as animal hospitals are increasingly using radiation generating devices, in order to protect the related workers and promote animal cares, the government enacted the regulations relating to operations and installations of the devices at animal hospitals. Therefore, this study handles the radiation safety management related stuffs by measuring and assessing radiation dose to the animal guardians and radiation workers in the animal hospitals in Gwangju.

Use of dose constraints for occupational exposure

International Nuclear Information System (INIS)

Kaijage, Tunu

2015-02-01

The use of dose constraints for occupational exposure was reviewed in this project. The role of dose constraints as used in optimization of protection of workers was described. Different issues to be considered in application of the concept and challenges associated with their implementation were also discussed. The situation where dose constraints could be misinterpreted to dose limits is also explained as the two are clearly differentiated by the International Commission of Radiological Protection (ICRP) Publication 103. Moreover, recommendations to all parties responsible for protection and safety of workers were discussed. (au)

Dose Determination of Activated Charcoal in Management of ...

African Journals Online (AJOL)

measured by high performance liquid chromatography (HPLC) for dose determination of activated ... paracetamol, benzodiazepines and alcohol [11]. .... Stability. The stability (short term) of standard and amitriptyline sample solutions was ...

Determination of the absorbed dose and dose-distribution in water for low- and medium-energetic photons

International Nuclear Information System (INIS)

Bultman, J.H.

1990-05-01

The methods to determine the absorbed dose to water for low and medium energy photons were studied. Large differences between the results of these methods exists. So, a research proposition has been made to explain these differences. The goal of this research will be the development of a method to determine the absorbed dose below approximately 400 keV with an ionization chamber calibrated at 60 Co gamma radiation. To explain the differences between the set of methods, some causes were proposed, like the influence of the ionisation chamber on the measurement in water. Also, some methods to determine the factors are proposed. (author). 29 refs

Determination of the total indicative dose in drinking and mineral waters

International Nuclear Information System (INIS)

Flesch, K.; Schulz, H.; Knappik, R.; Koehler, M.

2006-01-01

In Europe and Germany administrative regulations exist for the surveillance of the total indicative dose of water supplied for human consumption. This parameter, which cannot be analyzed directly, has to be calculated using nuclide specific activity concentration and age specific dose conversion factors and consumption rates. Available calculation methods differ regarding the used radionuclides, consumption rates and whether they use age specific dose conversion factors or not. In Germany administrative guidelines for the determination of the total indicative dose are still not available. As they have analyzed a large number of waters in the past, the authors derive a praxis orientated concept for the determination of the total indicative dose which respects radiological, analytical and hydrochemical aspects as well. Finally it is suggested to handle sparkling waters in the same manner as drinking waters. (orig.)

Grain elevator workers show work-related pulmonary function changes and dose-effect relationships with dust exposure.

Science.gov (United States)

Corey, P; Hutcheon, M; Broder, I; Mintz, S

1982-01-01

The purpose of this study was to determine whether grain handlers underwent work-related changes in their pulmonary function and, if so, to examine the dose-effect relationships with dust exposure. The pulmonary function of grain handlers was measured at the beginning and end of work shifts over a period of one week, during which their exposure to dust was measured daily. The results showed changes indicative of a within-day obstructive change, in addition to a small restrictive defect occurring over the course of a week. Civic outside labourers who were examined as a control group showed a similar within-week obstructive change without any associated restriction of lung volume. The data on the grain handlers were also used to examine the dose-effect relationships of dust exposure, both on baseline pulmonary function and on within-day changes in these measurements. The baseline flow rates of workers who did not wear a mask were found to vary inversely with their average exposure to respirable dust. In addition, the flow rates underwent a within-day decrease that varied directly with their corresponding exposure to respirable dust and was unrelated to mask wearing. The median of the slopes for this relationship indicated that 50% of the subjects had a decrease of at least 923 ml/s in the value of their Vmax50%VC for each 1 mg/m3 increase in the concentration of respirable dust. Non-respirable dust did not have a measurable effect either on the baseline or the within-day changes in pulmonary function. The acute changes were unaffected by age, duration of employment, or extent of smoking. PMID:7138793

Determination of organ doses in radiographic imaging and diagnostic radiology

International Nuclear Information System (INIS)

Rathjen, M.

1981-01-01

Earlier publications on diagnostic radiation exposure commonly presented data on the gonadal dose. This emphasis on the genetic radiation risk is no longer valid in view of recent radiobiological findings; equal attention should be paid to the somatic radiation risk which is manifested by the induction of malignant neoplasms, e.g. in the lungs, red bone marrow, thyroid and female breast (ICRP 26). The permissible radiation doses for these organs and the gonals for routine diagnostic radiology are determined. A formula is established on the basis of terms from relevant publications (e.g. open-air dose, backscattering factor) and from the author's own measurements in an Alderson-Rando phantom (depth dose curves, dose decrements). The measurements were carried out using CaP 2 thermoluminescence dosemeters, and the organ doses for the various techniques of X-ray examination were calculated by computer. Calculations of this type will enable the radiologist to determine the patient exposure quickly and easily from the records kept according to Sect. 29 of the X-ray Ordinance. Experimental value from relevant publications are compared with the author's own results. (orig./HP) [de

Determination of Absorbed Dose to Water for Leksell Gamma Knife Unit

International Nuclear Information System (INIS)

Hrsak, H.

2013-01-01

Because of geometry of photon beams in Leksell Gamma Knife Unit (LGK), there are several technical problems in applying standard protocols for determination of absorbed dose to water (Dw). Currently, Dw in LGK unit, measured at the center of spherical plastic phantom, is used for dose calculation in LGK radiosurgery. Treatment planning software (LGP TPS) accepts this value as a measurement in water and since plastic phantom has higher electron density than water, this leads to systematic errors in dose calculation. To reduce these errors, a photon attenuation correction (PAC) method was applied. For that purpose, measurements of absorbed dose in a center of three different plastic phantoms with 16 cm diameter (ABS - acrylonitrile butadiene styrene, PMMA - polymethyl metacrylate, PMMA + teflon - polytetrafluoroethylene 5 mm shell) were made with ionization chamber (Semiflex, PTW Freiburg). For measured dose values, PAC to water was applied based on electron density (ED) and equivalent water depths (EWD) of the plastic phantoms. The relation between CT number and ED was determined by measuring CT number of standard CT to ED phantom (CIRS Model 062 Phantom). Absorbed dose in plastic phantoms was 2.5 % lower than calculated dose in water for ABS phantom and more than 5.5 % lower for PMMA and PMMA+teflon phantom. Calculated dose in water showed more consistent values for all three phantoms (max. difference 2.6 %). EWD for human cranial bones and brain has value close to the EWD of ABS phantom, which makes this phantom most suitable for dose measurements in clinical application. In LGK radiosurgery determination of errors related to the difference of phantom materials should not be neglected and measured dose should be corrected before usage for patient treatment dose calculation.(author)

Neuromuscular dose-response studies: determining sample size.

Science.gov (United States)

Kopman, A F; Lien, C A; Naguib, M

2011-02-01

Investigators planning dose-response studies of neuromuscular blockers have rarely used a priori power analysis to determine the minimal sample size their protocols require. Institutional Review Boards and peer-reviewed journals now generally ask for this information. This study outlines a proposed method for meeting these requirements. The slopes of the dose-response relationships of eight neuromuscular blocking agents were determined using regression analysis. These values were substituted for γ in the Hill equation. When this is done, the coefficient of variation (COV) around the mean value of the ED₅₀ for each drug is easily calculated. Using these values, we performed an a priori one-sample two-tailed t-test of the means to determine the required sample size when the allowable error in the ED₅₀ was varied from ±10-20%. The COV averaged 22% (range 15-27%). We used a COV value of 25% in determining the sample size. If the allowable error in finding the mean ED₅₀ is ±15%, a sample size of 24 is needed to achieve a power of 80%. Increasing 'accuracy' beyond this point requires increasing greater sample sizes (e.g. an 'n' of 37 for a ±12% error). On the basis of the results of this retrospective analysis, a total sample size of not less than 24 subjects should be adequate for determining a neuromuscular blocking drug's clinical potency with a reasonable degree of assurance.

76 FR 76184 - Notice of Determinations Regarding Eligibility To Apply for Worker Adjustment Assistance

Science.gov (United States)

2011-12-06

... met. TA-W No. Subject firm Location Impact date 80,097 Ingersoll Rand, Security Carmel, IN April 8..., LLC, Android Shreveport, LA......... October 28, 2010. Industries. Negative Determinations for Worker...

77 FR 38661 - Notice of Determinations Regarding Eligibility To Apply for Worker Adjustment Assistance

Science.gov (United States)

2012-06-28

... December 7, 2010. Company, Armstrong World Industries, Inc., 1st Choice Personnel. 81,573 New Age Industrial Norton, KS May 19, 2010. Corporation. Negative Determinations for Worker Adjustment Assistance In...

Dose determination in computed tomography; Determinacion de dosis en tomografia computada

Energy Technology Data Exchange (ETDEWEB)

Descamps, C.; Garrigo, E.; Venencia, D. [Fundacion Marie Curie, Instituto Privado de Radioterapia, Departamento de Fisica Medica, Obispo Oro 423, X5000BFI Cordoba (Argentina); Gonzalez, M. [Universidad Nacional de Cordoba, Facultad de Ciencias Exactas, Fisicas y Naturales, Av. Velez Sarsfield 299, Corboba (Argentina); Germanier, A., E-mail: agermani@ceprocor.uncor.edu [Ministerio de Ciencia y Tecnologia, Ceprocor, Alvarez de Arenas 230, X5004AAP Barrio Juniors, Cordoba (Argentina)

2011-10-15

In the last years the methodologies to determine the dose in computed tomography have been revised. In this work was realized a dosimetric study about the exploration protocols used for simulation of radiotherapy treatments. The methodology described in the Report No. 111 of the American Association of Medical Physiques on a computed tomograph of two cuts was applied. A cylindrical phantom of water was used with dimensions: 30 cm of diameter and 50 cm of longitude that simulates the absorption and dispersion conditions of a mature body of size average. The doses were determined with ionization chamber and thermoluminescent dosimetry. The results indicate that the dose information that provides the tomograph underestimates the dose between 32 and 35%.

Ir-192 HDR transit dose and radial dose function determination using alanine/EPR dosimetry

International Nuclear Information System (INIS)

Calcina, Carmen S Guzman; Almeida, Adelaide de; Rocha, Jose R Oliveira; Abrego, Felipe Chen; Baffa, Oswaldo

2005-01-01

Source positioning close to the tumour in high dose rate (HDR) brachytherapy is not instantaneous. An increment of dose will be delivered during the movement of the source in the trajectory to its static position. This increment is the transit dose, often not taken into account in brachytherapeutic treatment planning. The transit dose depends on the prescribed dose, number of treatment fractions, velocity and activity of the source. Combining all these factors, the transit dose can be 5% higher than the prescribed absorbed dose value (Sang-Hyun and Muller-Runkel, 1994 Phys. Med. Biol. 39 1181-8, Nath et al 1995 Med. Phys. 22 209-34). However, it cannot exceed this percentage (Nath et al 1995). In this work, we use the alanine-EPR (electron paramagnetic resonance) dosimetric system using analysis of the first derivative of the signal. The transit dose was evaluated for an HDR system and is consistent with that already presented for TLD dosimeters (Bastin et al 1993 Int. J. Radiat. Oncol. Biol. Phys. 26 695-702). Also using the same dosimetric system, the radial dose function, used to evaluate the geometric dose degradation around the source, was determined and its behaviour agrees better with those obtained by Monte Carlo simulations (Nath et al 1995, Williamson and Nath 1991 Med. Phys. 18 434-48, Ballester et al 1997 Med. Phys. 24 1221-8, Ballester et al 2001 Phys. Med. Biol. 46 N79-90) than with TLD measurements (Nath et al 1990 Med. Phys. 17 1032-40)

Incidence and mortality by cancer among French nuclear workers of contracting companies

International Nuclear Information System (INIS)

Guerin, S.; Haddy, N.; Giardini, M.; Paoletti, C.; De Vathaire, F.

2006-01-01

Full text of publication follows: Current radiation protection standards of occupationally exposed workers are based on an extrapolation of cancer risks estimates derived from studies of the survivors of atomic bombings in Hiroshima and Nagasaki. In order to confirm these standards, International Agency for Research Cancer coordinated a retrospective cohort study to estimate the risk of cancer death after low-level exposure to gamma-ray, in a worldwide population of 400 000 nuclear industry workers in 15 countries. Methods: The present study is part of the international study and includes about 13,000 French nuclear industry workers of 10 contracting companies and subsidiary companies. This study was restricted to workers who wore a radiation dosimeter or badge. Contracting companies were selected on the basis of at least 100 workers in activity in 1996. A retrospective cohort was constituted. For each worker, we collected data concerning personal identifiers, occupational history, exposure history, vital status and cause of death. In order to guarantee the reliability of dosimetry data, we confronted monthly doses of X and gamma rays obtained from each company with monthly doses obtained from the National Institute of Radio Protection (I.R.S.N.). The cut off date was the 31 December of 2000. An incidence study is running within this cohort. Data relatives to poly-exposures, incident cancers and other pathologies, have being collected through a questionnaire form. Results: A total of 12,690 workers were included in the cohort, 1,457 could not be identified. Among the 11,233 identified workers, 280 deaths were recorded and 36% of them were cancer. Most of the workers were men (96%) and the median age at cut off date was equal to 41 years old. Only 25% of workers were exposed seven years or more. The median cumulative dose was equal to 3.1 mSv and 25% of workers had a cumulative dose superior to 22 mSv. Conclusion: Median cumulative dose was lower than expected as

Determinants of asthma phenotypes in supermarket bakery workers.

NARCIS (Netherlands)

Baatjies, R.; Lopata, A.L.; Sander, I.; Raulf-Heimsoth, M.; Bateman, E.D.; Meijster, T.; Heederik, D.J.J.; Robins, T.G.; Jeebhay, M.F.

2009-01-01

While baker's asthma has been well described, various asthma phenotypes in bakery workers have yet to be characterised. Our study aims to describe the asthma phenotypes in supermarket bakery workers in relation to host risk factors and self-reported exposure to flour dust. A cross-sectional study of

Determinants of asthma phenotypes in supermarket bakery workers

NARCIS (Netherlands)

Baatjies, R.; Lopata, A.L.; Sander, I.; Raulf-Heimsoth, M.; Batemane, E.D.; Meijster, T.; Heederik, D.; Robins, T.G.; Jeebhay, M.F.

2009-01-01

While baker's asthma has been well described, various asthma phenotypes in bakery workers have yet to be characterised. Our study aims to describe the asthma phenotypes in supermarket bakery workers in relation to host risk factors and self-reported exposure to flour dust. A cross-sectional study of

Improving occupational health care for construction workers: a process evaluation.

Science.gov (United States)

Boschman, Julitta S; van der Molen, Henk F; Sluiter, Judith K; Frings-Dresen, Monique H W

2013-03-11

To evaluate the process of a job-specific workers' health surveillance (WHS) in improving occupational health care for construction workers. From January to July 2012 were 899 bricklayers and supervisors invited for the job-specific WHS at three locations of one occupational health service throughout the Netherlands. The intervention aimed at detecting signs of work-related health problems, reduced work capacity and/or reduced work functioning. Measurements were obtained using a recruitment record and questionnaires at baseline and follow-up. The process evaluation included the following: reach (attendance rate), intervention dose delivered (provision of written recommendations and follow-up appointments), intervention dose received (intention to follow-up on advice directly after WHS and remembrance of advice three months later), and fidelity (protocol adherence). The workers scored their increase in knowledge from 0-10 with regard to health status and work ability, their satisfaction with the intervention and the perceived (future) effect of such an intervention. Program implementation was defined as the mean score of reach, fidelity, and intervention dose delivered and received. Reach was 9% (77 workers participated), fidelity was 67%, the intervention dose delivered was 92 and 63%, and the intervention dose received was 68 and 49%. The total programme implementation was 58%. The increases in knowledge regarding the health status and work ability of the workers after the WHS were graded as 7.0 and 5.9, respectively. The satisfaction of the workers with the entire intervention was graded as 7.5. The perceived (future) effects on health status were graded as 6.3, and the effects on work ability were graded with a 5.2. The economic recession affected the workers as well as the occupational health service that enacted the implementation. Programme implementation was acceptable. Low reach, limited protocol adherence and modest engagement of the workers with respect

Cancer mortality among two different populations of French nuclear workers

Energy Technology Data Exchange (ETDEWEB)

Samson, Eric; Telle-Lamberton, Maylis; Caer-Lorho, Sylvaine [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France). DRPH, SRBE, LEPID; and others

2011-08-15

The aim of this paper is to study the effect of external photon radiation on the mortality of two populations of French nuclear workers: workers exposed only to external photon radiation and workers potentially exposed also to internal contamination or to neutrons. External photon radiation has been measured through individual dosimeters. Potential exposure to internal contamination or to neutrons has been assessed by experts on the basis of quantitative measurements or of worksite and type of activity. The mortality observed in each population was compared with that expected from national mortality statistics, by computing standardized mortality ratios. Dose-effect relationships were analyzed through trend tests and log-linear Poisson regressions. 14,796 workers were exposed only to external photon radiation; 14,408 workers were also potentially exposed to internal radiation or to neutrons. Between 1968 and 1994, the number of deaths is respectively, 645 and 1,197. The mean external photon dose was respectively, 3.7 and 12.9 mSv. Similar Healthy Worker Effects were observed in the two populations (SMR = 0.59). SMR of 2.41 90% CI [1.39-3.90] was observed for malignant melanoma among workers of the second population. Significant dose-effect relationships were observed: among workers exposed only to external photon radiation for leukemia except CLL and in the other population, for cancers and other diseases related to tobacco or alcohol consumption. Results differed between the two populations. The increase in leukemia risk with dose in the first population will have to be confirmed with extended follow-up. In the other population, results may have been confounded by alpha-emitters inhalation, tobacco, or alcohol consumption.

Cancer mortality among two different populations of French nuclear workers

International Nuclear Information System (INIS)

Samson, Eric; Telle-Lamberton, Maylis; Caer-Lorho, Sylvaine

2011-01-01

The aim of this paper is to study the effect of external photon radiation on the mortality of two populations of French nuclear workers: workers exposed only to external photon radiation and workers potentially exposed also to internal contamination or to neutrons. External photon radiation has been measured through individual dosimeters. Potential exposure to internal contamination or to neutrons has been assessed by experts on the basis of quantitative measurements or of worksite and type of activity. The mortality observed in each population was compared with that expected from national mortality statistics, by computing standardized mortality ratios. Dose-effect relationships were analyzed through trend tests and log-linear Poisson regressions. 14,796 workers were exposed only to external photon radiation; 14,408 workers were also potentially exposed to internal radiation or to neutrons. Between 1968 and 1994, the number of deaths is respectively, 645 and 1,197. The mean external photon dose was respectively, 3.7 and 12.9 mSv. Similar Healthy Worker Effects were observed in the two populations (SMR = 0.59). SMR of 2.41 90% CI [1.39-3.90] was observed for malignant melanoma among workers of the second population. Significant dose-effect relationships were observed: among workers exposed only to external photon radiation for leukemia except CLL and in the other population, for cancers and other diseases related to tobacco or alcohol consumption. Results differed between the two populations. The increase in leukemia risk with dose in the first population will have to be confirmed with extended follow-up. In the other population, results may have been confounded by alpha-emitters inhalation, tobacco, or alcohol consumption.

75 FR 51846 - Notice of Determinations Regarding Eligibility To Apply for Worker Adjustment Assistance

Science.gov (United States)

2010-08-23

... 202(b)(1); (B) An affirmative determination of market disruption or threat thereof under section 421(b... Viewpointe Archive Parsippany, NJ......... December 11, 2008. Services, LLC, On-Site Leased Workers from...

Biodosimetry of Chernobyl cleanup workers from Estonia and Latvia using the glycophorin A in vivo somatic cell mutation assay

International Nuclear Information System (INIS)

Bigbee, W.L.; Jensen, R.H.; Veidebaum, T.

1997-01-01

The reactor accident at Chernobyl in 1986 necessitated a massive environmental cleanup that involved over 600,000 workers from all 15 Republics of the former Soviet Union. To determine whether the whole-body radiation received by workers in the course of these decontamination activities resulted in a detectable biological response, over 1,500 blood samples were obtained from cleanup workers sent from two Baltic countries, Estonia and Latvia. Here we report the results of studies of biodosimetry using the glycophorin A (GPA) locus in vivo somatic cell mutation assay applied to 734 blood samples from these workers, to 51 control samples from unexposed Baltic populations and to 94 samples from historical U.S. controls. The data reveal inconsistent evidence that the protracted radiation exposures received by these workers resulted in a significant dose-associated increase in GPA locus mutations compared with the controls. Taken together, these data suggest that the average radiation exposure to these workers does not greatly exceed 10 cGy, the minimum levels at which radiation effects might be detectable by the assay. Although the protracted nature of the exposure may have reduced the efficiency of induction of GPA locus mutations, it is likely that the estimated physical doses for these cleanup worker populations (median reported dose 9.5 cGy) were too low to result in radiation damage to erythroid stem cells that can be detected reliably by this method. 25 refs., 2 figs., 3 tabs

Occupational dose measurement in interventional cardiology, dosimetry comparison study

International Nuclear Information System (INIS)

Ahmad, A.M.A.

2008-05-01

The number of cardiology interventional procedures has significantly increased recently. This is due to the reliability of the diagnostic equipment to diagnose many heart disease. In the procedures the x-ray used results in increasing radiation doses to the staff. The cardiologists and other staff members in interventional cardiology are usually working close to the area under examination and receive the dose primarily from scattered radiation from the patient. Therefore workers in interventional cardiology are expected to receive high doses. This study overviews the status of occupational exposure at the three cardiology centers at three different hospitals in Khartoum compared with that received by workers at other medical practices (radiotherapy, nuclear medicine and diagnostic radiology) in the Institute of Nuclear and Technology (INMO) at El Gezira. The TLD Harshaw 6600 reader was used in the assessment of effective dose for Hp (10). Two TLDs were used by each worker at the three cardiology centres, one worn under a protective apron and the other worn outside and above the apron as specified by the ICRP. Each worker at the other sections was facilitated with one dosimeter to be worn on the chest. The annual doses received by 14 cardiologists, 13 nurses and 9 technologists at the three cardiology centres were in the range: (0.84-4.77), (0.15-2.08), (0.32-1.10) mSv respectively. In the INMO the annual doses received by 7 doctors, 5 nurses and 14 technologists were in the range: (0.12-0.51), (0.11-0.65), (0.03-1.39) mSv respectively. The results showed that the annual doses received by the workers do not exceed 20 mSv. The study also indicated that doses received by workers in interventional cardiology, in particular the cardiologists are high compared to that received at the other medical sections.(Author)

Measured dose to ovaries and testes from Hodgkin's fields and determination of genetically significant dose

International Nuclear Information System (INIS)

Niroomand-Rad, A.; Cumberlin, R.

1993-01-01

The purpose of this study was to determine the genetically significant dose from therapeutic radiation exposure with Hodgkin's fields by estimating the doses to ovaries and testes. Phantom measurements were performed to verify estimated doses to ovaries and testes from Hodgkin's fields. Thermoluminescent LiF dosimeters (TLD-100) of 1 x 3 x 3 mm 3 dimensions were embedded in phantoms and exposed to standard mantle and paraaortic fields using Co-60, 4 MV, 6 MV, and 10 MV photon beams. The results show that measured doses to ovaries and testes are about two to five times higher than the corresponding graphically estimated doses for Co-60 and 4 MVX photon beams as depicted in ICRP publication 44. In addition, the measured doses to ovaries and testes are about 30% to 65% lower for 10 MV photon beams than for their corresponding Co-60 photon beams. The genetically significant dose from Hodgkin's treatment (less than 0.01 mSv) adds about 4% to the genetically significant dose contribution to medical procedures and adds less than 1% to the genetically significant dose from all sources. Therefore, the consequence to society is considered to be very small. The consequences for the individual patient are, likewise, small. 28 refs., 3 figs., 5 tabs

Health survey of radiation workers. Results of questionnaire

International Nuclear Information System (INIS)

Morikawa, Kaoru; Aoyama, Takashi; Kawagoe, Yasumitsu; Sunayashiki, Tadashi; Tanaka, Kiyoshi; Nishitani, Motohiro; Yoshinaga, Nobuharu

1998-01-01

The Japanese Society of Radiological Technology asked radiation workers about the radiation doses and the state of their health as well as family. The reports by the Health and Welfare Ministry were referenced to compare radiation workers with others. The questionnaire was sent to about 4,000 members, and returned from 2,479. The survey showed that 684 persons (27.6%) felt health anxiety, 455 persons (18.4%) had medical check for recent one year, and 1,645 persons (66.4%) had anamnesis. Radiation doses for one year and cumulated doses varied according to engaging duration. (K.H.)

Workers radiation protection. Occupational exposure to ionizing radiations in France: 2015 results. 2016 Mission report

International Nuclear Information System (INIS)

2016-06-01

National results of the individual monitoring of occupational exposure to ionizing radiation are reported for all civilian and military activities subject to authorization or declaration (i.e. medical and veterinary activities, nuclear industry, defence, non-nuclear industry and research), as well as for activities concerned by the enhanced exposure to natural radiation. 365 830 workers within activities subject to authorization or declaration were monitored by passive dosimetry in 2015, which represents an increase by 1.7 % compared to 2014. The average individual dose in 2015 was very close to the value in 2014. Furthermore, 14 138 workers received more than 1 mSv (i.e. the legal dose limit for the public), and 2 606 workers received more than 5 mSv. 2 workers received more than 20 mSv (i.e. the dose limit for the workers in the French regulation). As a result, the collective dose increased from 56.3 to 61.9 man.Sv (10 %), thus reaching the same level as in the years 2009 to 2013. Important differences are noticed according to the occupational activities: the average dose in the medical and veterinary field (which represents 62.4 % of the monitored workers) and that in the research field (3.6 % of the monitored workers) are less than 0.4 mSv; the average doses are higher in the nuclear field and in the non-nuclear industry (representing together 30.1 % of the monitored workers), respectively 1.17 mSv and 1.38 mSv. Concerning internal dosimetry, 279 877 individual examinations have been performed in 2015, 52 % of which are radio-toxicological analysis of excreta and 48 % are direct body counting. In 2015, 2 workers had a committed effective dose greater than or equal to 1 mSv and the maximum dose was 3 mSv. Data or trends relative to workers exposed to natural radioactivity are also dealt with in this report (air crews, personnel subjected to radon exposure). In particular, results of aircrew dosimetry are reported: in 2015, the average individual dose of 19 565

Occupational radiation dose in Indonesia 1981-1986

International Nuclear Information System (INIS)

Hiswara, E.; Ismono, A.

1993-01-01

Occupational radiation dose in Indonesia 1981-1986. This paper presents the occupational radiation dose in Indonesia during the period of 1981-1986. The highest collective dose accurated in 1983 was calculated to be 2.68 man-Sv, with the maximum mean dose per worker, who received dose more than zero, was around 11.07 mSv in the same year. In 1985, a relative collective dose from medical occupations of 1.88 man mSv for 10 6 population was estimated based on its total collective dose of 0.31 man-mSv. The total number of workers who received annual collective dose less than 5 mSv varied from 97.0% in 1981 to 99.5% in 1986. As a group, the industrial occupations has considerably higher risk in receiving a dose than others. (authors). 11 refs., 7 tabs

Dose determination on buildup region using photodiodes

International Nuclear Information System (INIS)

Khoury, H.J.; Lopes, F.J.; Melo, F. de A.

1989-01-01

A clinical dosemeter using photodiode BPW-34 was developed, allowing the determination of dose on buildup region. The measures were made with X-rays beam of linear accelerator and with gamma radiation of cobalt 60. The results were compared with others made in a ionization chamber. (C.G.C.) [pt

Determining effective radiation mutagen dose for garlic (Allium sativum L.)

International Nuclear Information System (INIS)

Taner, Y.; Kunter, B.

2004-01-01

This study was carried out to get database for future garlic mutation breeding studies. For this aim, 0, 5, 10, 15, 20, 25 and 30 Gy doses of Cs 137 (gamma-ray) were applied on garlic cloves as a physical mutagen. 50 cloves were used for each dose. Sixty days after treatment, germination rate and shoot development of cloves were determined. The Effective Mutagen Dose (ED 50 ) was calculated by regression analyses. According to the results, 4.455 Gy dose was found to be effective as ED 50 . (author)

Committed effective dose determination in southern Brazilian cereal flours.

Science.gov (United States)

Scheibel, V; Appoloni, C R

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of (228)Th, (228)Ra, (226)Ra, (40)K, (7)Be and (137)Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of (228)Th and (40)K were 3.5±0.4 and 1469±17 Bq kg(-1) for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for (137)Cs ranged from 0.04 to 0.4 Bq kg(-1). The highest committed effective dose was 0.36 μSv.y(-1) for (228)Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y(-1), to the public exposure.

Committed effective dose determination in southern Brazilian cereal flours

International Nuclear Information System (INIS)

Scheibel, V.; Appoloni, C. R.

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of 228 Th, 228 Ra, 226 Ra, 40 K, 7 Be and 137 Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of 228 Th and 40 K were 3.5±0.4 and 1469±17 Bq kg -1 for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for 137 Cs ranged from 0.04 to 0.4 Bq kg -1 . The highest committed effective dose was 0.36 μSv.y -1 for 228 Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y -1 , to the public exposure. (authors)

Determination of Several Clinical Parameters of the Blood for the HealthyEvaluation of the Radiation Worker

International Nuclear Information System (INIS)

Yazid, M; Triyono; Aris-Bastianudin

2000-01-01

Determination of the several clinical parameters of the blood for healthyevaluation of the radiation worker has been done. This research was done forarrangement of the medical general check up of the radiation worker toobserve pathological indicator of several body organs. The blood sample wastaken from vena mediana cubiti and analyzed by reagent using standardprocedure from Boehringer Mainheim. That procedure is specific for eachclinical parameters. That clinical parameters concentration was measured byClinicon Photometer 4010. The clinical data of the radiation worker wascompared to the non radiation worker. The measurement results of 501patients, shown that total protein concentrations for all worker are > 8.00g%, the cholesterol concentration of 25 patient are > 260 mg%. The glucoseconcentration for fasting condition of 7 patients are > 200 mg/dl, the ureumconcentration of all patients are 7mg% and the creatinine of 112 patients are > 1.4 mg%. From those results canbe concluded that the most pathological indicator can be identified fromliver, heart and kidney function respectively. From the clinical aspects canbe seen that there is no significant difference between the health ofradiation worker and non radiation worker. (author)

Monthly radiation protection training of workers: An evaluation of two years operational practice

International Nuclear Information System (INIS)

Berus, D.; Covens, P.

2011-01-01

Radiation protection training and education is important in stimulating safety culture of occupationally exposed workers. Taking into account the mandatory requirements in relation to education and training a digital training tool was introduced for communication of personal dose results and regular information on radiation protection. This tool enables that personal dose reports are monthly sent to the individual mailbox of workers together with short comprehensive slideshows on radiation protection topics. After two years of operational practice a survey was organised to evaluate the training tool. The results show that the majority (92%) of the occupationally exposed workers are aware of the communication of personal dose results through e-mail. Furthermore, 81% of these workers are also aware of their monthly and cumulated dose level. The monthly information on radiation protection topics is however less consulted. Around 40% of the workers that noticed the link are indifferent to the monthly information. The interest in radiation protection issues increases however with the education level.

Interpretation of bioassay data from nuclear fuel fabrication workers

International Nuclear Information System (INIS)

Melo, D.; Xavier, M.

2005-01-01

Full text: In nuclear fuel fabrication facilities, workers are exposed to different compounds of enriched uranium. Although in this kind of facility the main route of intake is inhalation, ingestion may occur in some situations. The interpretation of the bioassay data is very complex, since it is necessary taking into account all the different parameters, which is a big challenge. Due to the high cost of the individual monitoring programme for internal dose assessment in the routine monitoring programmes, usually only one type of measurement is assigned. In complex situations like the one described in this paper, where several parameters can compromise the accuracy of the bioassay interpretation it is need to have a combination of techniques to evaluate the internal dose. According to ICRP 78 (1997), the general order of preference in terms of accuracy of interpretation is: body activity measurement, excreta analysis and personal air sampling. Results of monitoring of working environment may provide information that assists in interpretation on particle size, chemical form and solubility, time of intake. A group of seventeen workers from controlled area of the fuel fabrication facility was selected to evaluate the internal dose using all different available techniques during a certain period. The workers were monitored for determination of uranium content in the daily urinary and faecal excretion (collected over a period of 3 consecutive days), chest counting and personal air sampling. The results have shown that at least two types of sensitivity techniques must be used, since there are some sources of uncertainties on the bioassay interpretation, like mixture of uranium compounds intake and different routes of intake. The combination of urine and faeces analysis has shown to be the more appropriate methodology for assessing internal dose in this situation. (author)

Cytogenetic studies in workers with chronic occupational radiation exposure

International Nuclear Information System (INIS)

Grynszpan, D.

1989-01-01

The technique of chromosomal aberration detection on peripheral lymphocytes blood samples from monazite industry workers was used to study the cytogenetic effect of low chronic radiation doses. Cells from 51 workers and 21 controls were analysed. Cytogenetic data from individuals from different working areas were statistically compared among themselves and with the control group. The possible correlations between chromosomal aberration frequencies and cumulative external dose and working time were investigated. The influence of smoking was also tested. The link to the wives spontaneous abortions was analysed. Our results indicate possible biological effects on this sample of workers. (author)

Determination of beta-ray emitter concentrations in bioassay samples of the victims in JCO criticality accident

International Nuclear Information System (INIS)

Yukawa, Masae; Nishimura, Yoshikazu; Watanabe, Yoshito

2001-01-01

Concentrations of neutron-induced β-ray emitters in the hair, blood, urine and bone of three workers severely exposed to neutrons in JCO criticality accident were measured with a low background β-ray spectrometer (Pico β) and liquid scintillation counter for the purpose of neutron dose estimation. 32 P is generated by the fast neutron of 2.5 MeV and over in sulfur with (n, p) reaction. Since content of sulfur in hair is high as compared with the other human tissues, we tried to estimate fast neutron fluence to the body surface of the victims using concentrations of 32 P and stable sulfur in their hair. The result shows that two workers, who were exposed to the higher neutron radiation than another worker, received higher doses of irradiation to the frontal side of their trunks than to the heads. For a more detailed mapping of neutron fluence in the body, the measurements of 32 P and 45 Ca induced by (n, γ) reaction in bone were carried out. The results show that one worker (worker A) received a higher dose of neutrons at the frontal right side of the trunk, and that the dose decreased with the distance from the central part of the body. The other (worker B) seems to have gotten a higher dose of irradiation in the face, hands and waist. High amount of 32 P was detected in urine of the workers, and the concentration gradient among three workers showed a similar tendency to the estimated neutron dose from 24 Na in blood. Therefore, radioactivity of 32 P in urine could be used for estimating the neutron exposure dose. Moreover, the activity can be easily determined by scintillation counting, and urine is less invading bioassay sample that can be collected by non-medical stuffs. (author)

Health effects study of the nuclear industry workers in Japan

International Nuclear Information System (INIS)

Tamiko Iwasaki

1997-01-01

To clarify the effects of low-dose and low-dose-rate exposure to the human body, study on the health effects of the nuclear industry workers in Japan was conducted since 1990 by the Institute of Radiation Epidemiology, the Radiation Effects Association, which had been entrusted by the Science and Technology Agency of the Japanese Government. In the first phase analysis between 1986 and 1992, the study population was selected from among persons who were engaged in radiation work at nuclear power plants and associated facilities, and registered in the Radiation Dose Registration Center for Workers. The cohort consisted of 114,900 persons who satisfied the criteria of nationality, age, sex, etc. The average follow-up period was 4.6 years, and the average cumulative dose per person was 13.9 mSv. The total number of deaths among the study population was 1,758, including 661 deaths due to all malignant neoplasms. The Standardized Mortality Ratio of various death causes was compared. Furthermore, the cohort was grouped by five different dose levels, and the O/E was calculated to test whether there is a trend for the death rate to increase with dose. Among nuclear workers no significant increase in deaths nor any relationship with radiation dose was found, except the pancreatic cancer with 10-years lag. Since many previous studies of nuclear industry workers have demonstrated no significant association between exposure dose and pancreatic cancer, we cannot immediately conclude a causal relationship between with radiation. (author)

Internal dose estimation by bio-assay techniques

International Nuclear Information System (INIS)

Sawant, Pramilla D.

2016-01-01

Radiation exposure, both external and internal, can occur to radiation workers during the operation of various nuclear fuel cycle facilities and radiation facilities. The assessment of radiation doses to workers, routinely or potentially exposed to radiation, through intake of radionuclide is an integral part of the radiation protection programme. Internal dose is the radiation exposure that results from the intake of radioactive materials into the body by inhalation, ingestion, absorption through the skin or via wounds. Assessment of radiation doses arising from the intake of radioactive material by the workers is termed as internal exposure assessment. Unlike external exposure, internal exposure cannot be measured directly. Its evaluation is based on the calculation of the intake of radionuclide either from direct measurements (e.g, external monitoring of whole body or of specific organs and tissues) or indirect measurements (e.g. radioactivity in urine, faeces, breath or samples from the working environment) (ICRP Pub. 78, 1997 and NRPB-W60, 2004). Another method of internal dose assessment is based on the measurement of airborne radionuclides in the working areas of the facility and the worker's occupancy in those areas

Dose estimate for effective internal contamination in the occupationally exposed workers(OEW) that handling open sources for thyroid therapy using 131 I (3779)

International Nuclear Information System (INIS)

Lecuna, J.A.; Carrizales, L.I.; Dantas, B.M.

2013-01-01

Handling of a variety of unsealed sources in Nuclear Medicine has led a significant risk of internal exposure of workers. 131 I stands out among the radionuclides of frequent use due its wide application in diagnosis and treatment of thyroid diseases. The increasing radionuclide use for medical purposes and treatment of diseases creates a need for capable methodologies of controlling the internal contamination of work. Currently, in Venezuela, there are about 17 Nuclear Medicine Services between public and private, of which 5 are operating; however, individual monitoring is still limited in the control of internal exposure. This work presents the development of bioassay techniques 'in vivo', in order to quantify the incorporation of 131 I used in Nuclear Medicine. It also presents the research results of internal exposure of a group of workers involved in handling of therapeutic dose of 131 I . The 'in vivo' detection system was calibrated with the thyroid simulator developed at the Institute of Radiologic Protection and Dosimetry (IRD, Rio de Janeiro - Brazil) and which also has the UTN-IVIC (Caracas - Venezuela). The results showed that the bioassay method developed in this work has sufficient sensitivity for its use in routine intake survey of workers in Nuclear Medicine. Between the two workers controlled in this study, both had measurable results in terms of incorporation. Therefore, it is important to keep control of it and also gives us the possibility to evaluate the incorporations in suspected accident. The highest estimate of the effective dose was 1,28x10 -5 Sv by inhalation and 1,27x10 -5 Sv by ingestion

Retrospective Dosimetry and Clinical Follow-up Programme of Chernobyl Accident Clean-up Workers in Latvia

International Nuclear Information System (INIS)

Mironova-Ulmane, N.; Pavlenko, A.; Zvagule, T.; Karner, T.; Bruvere, R.; Volrate, A.

2001-01-01

Full text: About 6500 Latvian inhabitants were recruited for clean-up works at Chernobyl Nuclear Power Plant during 1986-1991. Absorbed doses for them are usually unknown, because only less then half of the clean-up workers cohort had officially documented external exposure. Clinical investigations show high morbidity rate of clean-up workers compared with general population. The results of Electronic Spin Resonance (ESR) dose reconstruction (doses absorbed in the tooth enamel) for the clean-up workers were always higher as documented of exposure doses of physical measurements. In many cases more than half of total absorbed dose is due to 90 Sr accumulated in teeth. Most of the clean-up workers have poli-symptomatic sicknesses that exhibit tendency to progress, and their morbidity exceeds that observed in general population. ESR dosimetry programs and clinical follow-up improved existing knowledge in the field of radiation medicine. These data will help to develop and apply the proper treatment and rehabilitation procedures for clean-up workers. (author)

The development of wireless radiation dose monitoring using smart phone

Energy Technology Data Exchange (ETDEWEB)

Lee, Jin Woo; Jeong, Gyo Seong; Lee, Yun Jong [Advanced Radiation Technology Institute, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Chong Yeal [Chonbuk National University, Jeonju (Korea, Republic of); Lim, Chai Wan [REMTECH, Seoul (Korea, Republic of)

2016-11-15

Radiation workers at a nuclear facility or radiation working area should hold personal dosimeters. some types of dosimeters have functions to generate audible or visible alarms to radiation workers. However, such devices used in radiation fields these days have no functions to communicate with other equipment or the responsible personnel. our project aims at the development of a remote wireless radiation dose monitoring system that can be utilized to monitor the radiation dose for radiation workers and to notify the radiation protection manager of the dose information in real time. We use a commercial survey meter for personal radiation measurement and a smart phone for a mobile wireless communication tool and a Beacon for position detection of radiation workers using Blue tooth communication. In this report, the developed wireless dose monitoring of cellular phone is introduced.

Software for the estimation of foetal radiation dose to patients and staff in diagnostic radiology

Energy Technology Data Exchange (ETDEWEB)

Osei, E K [Department of Radiation Physics, Princess Margaret Hospital, 610 University Avenue, Toronto ON M5G 2M9 (Canada); Darko, J B [Department of Radiation Physics, Princess Margaret Hospital, 610 University Avenue, Toronto ON M5G 2M9 (Canada); Faulkner, K [Quality Assurance Centre, Newcastle General Hospital, Westgate Road, Newcastle Upon Tyne NE4 6BE (United Kingdom); Kotre, C J [Regional Medical Physics Department, Newcastle General Hospital, Westgate Road, Newcastle Upon Tyne NE4 6BE (United Kingdom)

2003-06-01

Occasionally, it is clinically necessary to perform a radiological examination(s) on a woman who is known to be pregnant or an examination is performed on a woman who subsequently discovers that she was pregnant at the time. In radiological examinations, especially of the lower abdomen and pelvis area, the foetus is directly irradiated. It is therefore important to be able to determine the absorbed dose to the foetus in diagnostic radiology for pregnant patients as well as the foetal dose from occupational exposure of the pregnant worker. The determination of the absorbed dose to the unborn child in diagnostic radiology is of interest as a basis for risk estimates from medical exposure of the pregnant patient and occupational exposure of the pregnant worker. In this paper we describe a simple computer program, FetDose, which calculates the dose to the foetus from both medical and occupational exposures of the pregnant woman. It also calculates the risks of in utero exposure, compares calculated doses with published data in the literature and provides information on the natural spontaneous risks. The program will be a useful tool for the medical and paramedical personnel who are involved with foetal dose (and hence risks) calculations and counselling of pregnant women who may be concerned about in utero exposure of their foetuses.

Software for the estimation of foetal radiation dose to patients and staff in diagnostic radiology

International Nuclear Information System (INIS)

Osei, E K; Darko, J B; Faulkner, K; Kotre, C J

2003-01-01

Occasionally, it is clinically necessary to perform a radiological examination(s) on a woman who is known to be pregnant or an examination is performed on a woman who subsequently discovers that she was pregnant at the time. In radiological examinations, especially of the lower abdomen and pelvis area, the foetus is directly irradiated. It is therefore important to be able to determine the absorbed dose to the foetus in diagnostic radiology for pregnant patients as well as the foetal dose from occupational exposure of the pregnant worker. The determination of the absorbed dose to the unborn child in diagnostic radiology is of interest as a basis for risk estimates from medical exposure of the pregnant patient and occupational exposure of the pregnant worker. In this paper we describe a simple computer program, FetDose, which calculates the dose to the foetus from both medical and occupational exposures of the pregnant woman. It also calculates the risks of in utero exposure, compares calculated doses with published data in the literature and provides information on the natural spontaneous risks. The program will be a useful tool for the medical and paramedical personnel who are involved with foetal dose (and hence risks) calculations and counselling of pregnant women who may be concerned about in utero exposure of their foetuses

Dose Reduction Techniques

International Nuclear Information System (INIS)

WAGGONER, L.O.

2000-01-01

As radiation safety specialists, one of the things we are required to do is evaluate tools, equipment, materials and work practices and decide whether the use of these products or work practices will reduce radiation dose or risk to the environment. There is a tendency for many workers that work with radioactive material to accomplish radiological work the same way they have always done it rather than look for new technology or change their work practices. New technology is being developed all the time that can make radiological work easier and result in less radiation dose to the worker or reduce the possibility that contamination will be spread to the environment. As we discuss the various tools and techniques that reduce radiation dose, keep in mind that the radiological controls should be reasonable. We can not always get the dose to zero, so we must try to accomplish the work efficiently and cost-effectively. There are times we may have to accept there is only so much you can do. The goal is to do the smart things that protect the worker but do not hinder him while the task is being accomplished. In addition, we should not demand that large amounts of money be spent for equipment that has marginal value in order to save a few millirem. We have broken the handout into sections that should simplify the presentation. Time, distance, shielding, and source reduction are methods used to reduce dose and are covered in Part I on work execution. We then look at operational considerations, radiological design parameters, and discuss the characteristics of personnel who deal with ALARA. This handout should give you an overview of what it takes to have an effective dose reduction program

Dose Reduction Techniques

Energy Technology Data Exchange (ETDEWEB)

WAGGONER, L.O.

2000-05-16

As radiation safety specialists, one of the things we are required to do is evaluate tools, equipment, materials and work practices and decide whether the use of these products or work practices will reduce radiation dose or risk to the environment. There is a tendency for many workers that work with radioactive material to accomplish radiological work the same way they have always done it rather than look for new technology or change their work practices. New technology is being developed all the time that can make radiological work easier and result in less radiation dose to the worker or reduce the possibility that contamination will be spread to the environment. As we discuss the various tools and techniques that reduce radiation dose, keep in mind that the radiological controls should be reasonable. We can not always get the dose to zero, so we must try to accomplish the work efficiently and cost-effectively. There are times we may have to accept there is only so much you can do. The goal is to do the smart things that protect the worker but do not hinder him while the task is being accomplished. In addition, we should not demand that large amounts of money be spent for equipment that has marginal value in order to save a few millirem. We have broken the handout into sections that should simplify the presentation. Time, distance, shielding, and source reduction are methods used to reduce dose and are covered in Part I on work execution. We then look at operational considerations, radiological design parameters, and discuss the characteristics of personnel who deal with ALARA. This handout should give you an overview of what it takes to have an effective dose reduction program.

Dose Reduction Techniques

CERN Document Server

Waggoner, L O

2000-01-01

As radiation safety specialists, one of the things we are required to do is evaluate tools, equipment, materials and work practices and decide whether the use of these products or work practices will reduce radiation dose or risk to the environment. There is a tendency for many workers that work with radioactive material to accomplish radiological work the same way they have always done it rather than look for new technology or change their work practices. New technology is being developed all the time that can make radiological work easier and result in less radiation dose to the worker or reduce the possibility that contamination will be spread to the environment. As we discuss the various tools and techniques that reduce radiation dose, keep in mind that the radiological controls should be reasonable. We can not always get the dose to zero, so we must try to accomplish the work efficiently and cost-effectively. There are times we may have to accept there is only so much you can do. The goal is to do the sm...

Worker resignation due to patient nuisance in hospitals: Determinants and prevention.

Science.gov (United States)

Kusui, Yoshiyuki; Yamazaki, Toru; Yamada, Tomomi; Hamada, Masayuki; Ueshima, Kazumune; Tajima, Kazuo; Sokejima, Shigeru

2017-01-02

To investigate determinants and protective strategies for the resignation of health care workers resulting from patient-derived nuisance in medical institutions, we conducted a cross-sectional survey in the 57 hospitals in Mie Prefecture, Japan. A random sampling of 775 employees (physicians, nurses, administrators, and other health care workers) was provided self-administered questionnaires. Among 480 participants who experienced patient-derived nuisance, 132 participants considered resignation as a result, giving an estimated prevalence of 17.1% (95% CI: 14.4%-19.8%) of all respondents. Nonphysical nuisances such as "demand for an unwarranted apology" (OR: 2.57; 95% CI: 1.61-4.12) had higher ORs for considering resignation than other kinds of nuisance. By contrast, OR for the provision of human support by medical institutions was 0.49 (95% CI: 0.28-0.86). Human support was associated with alleviation of the intention to resign.

Policing practices as a structural determinant for HIV among sex workers: a systematic review of empirical findings.

Science.gov (United States)

Footer, Katherine Ha; Silberzahn, Bradley E; Tormohlen, Kayla N; Sherman, Susan G

2016-01-01

Sex workers are disproportionately infected with HIV worldwide. Significant focus has been placed on understanding the structural determinants of HIV and designing related interventions. Although there is growing international evidence that policing is an important structural HIV determinant among sex workers, the evidence has not been systematically reviewed. We conducted a systematic review of quantitative studies to examine the effects of policing on HIV and STI infection and HIV-related outcomes (condom use; syringe use; number of clients; HIV/STI testing and access) among cis and trans women sex workers. Databases included PubMed, Embase, Scopus, Sociological Abstracts, Popline, Global Health (OVID), Web of Science, IBSS, IndMed and WHOLIS. We searched for studies that included police practices as an exposure for HIV or STI infection or HIV-related outcomes. Of the 137 peer-reviewed articles identified for full text review, 14 were included, representing sex workers' experiences with police across five settings. Arrest was the most commonly explored measure with between 6 and 45% of sex workers reporting having ever been arrested. Sexual coercion was observed between 3 and 37% of the time and police extortion between 12 and 28% across studies. Half the studies used a single measure to capture police behaviours. Studies predominantly focused on "extra-legal policing practices," with insufficient attention to the role of "legal enforcement activities". All studies found an association between police behaviours and HIV or STI infection, or a related risk behaviour. The review points to a small body of evidence that confirms policing practices as an important structural HIV determinant for sex workers, but studies lack generalizability with respect to identifying those police behaviours most relevant to women's HIV risk environment.

Determination of Absorbed Dose in Large 60-Co Fields Radiotherapy

International Nuclear Information System (INIS)

Hrsak, H.

2003-01-01

Radiation in radiotherapy has selective impact on ill and healthy tissue. During the therapy the healthy tissue receives certain amount of dose. Therefore dose calculations in outer radiotherapy must be accurate because too high doses produce damage in healthy tissue and too low doses cannot ensure efficient treatment of cancer cells. A requirement on accuracy in the dose calculations has lead to improvement of detectors, and development of absolute and relative dosimetry. Determination of the dose distribution with use of computer is based on data provided by the relative dosimetry. This paper compares the percentage depth doses in cubic water phantoms of various dimensions with percentage depth doses calculated with use of Mayneord factor from the experimental depth doses measured in water phantom of large dimension. Depth doses in water phantoms were calculated by the model of empirical dosimetrical functions. The calculations were based on the assumption that large 6 0C o photon field exceeds the phantom's limits. The experimental basis for dose calculations by the model of empirical dosimetrical functions were exposure doses measured in air and dose reduction factors because of finite phantom dimensions. Calculations were performed by fortran 90 software. It was found that the deviation of dosimetric model was small in comparison to the experimental data. (author)

Exposure to low doses of ionizing radiations

International Nuclear Information System (INIS)

Le Guen, B.

2008-01-01

The author discusses the knowledge about the effects of ionizing radiations on mankind. Some of them have been well documented (skin cancer and leukaemia for the pioneer scientists who worked on radiations, some other types of cancer for workers who handled luminescent paints, rock miners, nuclear explosion survivors, patients submitted to radiological treatments). He also evokes the issue of hereditary cancers, and discusses the issue of low dose irradiation where some surveys can now be performed on workers. He discusses the biological effects of these low doses. He outlines that many questions remain about these effects, notably the influence of dose level and of dose rate level on the biological reaction

Neutron dose and energy spectra measurements at Savannah River Plant

International Nuclear Information System (INIS)

Brackenbush, L.W.; Soldat, K.L.; Haggard, D.L.; Faust, L.G.; Tomeraasen, P.L.

1987-08-01

Because some workers have a high potential for significant neutron exposure, the Savannah River Plant (SRP) contracted with Pacific Northwest Laboratory (PNL) to verify the accuracy of neutron dosimetry at the plant. Energy spectrum and neutron dose measurements were made at the SRP calibrations laboratory and at several other locations. The energy spectra measurements were made using multisphere or Bonner sphere spectrometers, 3 He spectrometers, and NE-213 liquid scintillator spectrometers. Neutron dose equivalent determinations were made using these instruments and others specifically designed to determine dose equivalent, such as the tissue equivalent proportional counter (TEPC). Survey instruments, such as the Eberline PNR-4, and the thermoluminescent dosimeter (TLD)-albedo and track etch dosimeters (TEDs) were also used. The TEPC, subjectively judged to provide the most accurate estimation of true dose equivalent, was used as the reference for comparison with other devices. 29 refs., 43 figs., 13 tabs

Determination of the equivalent of environmental dose, H*(d), in a radiotherapy installation

International Nuclear Information System (INIS)

Lima, M.A.F.; Borges, J.C.; Mota, H.C.

1998-01-01

In order to put into practice radiological protection has been required conversion factors for environmental dose equivalent determination to air kerma value for different kinds of photon and electron beams, such dose values have been determined in a spheric phantom of 30 cm diameter in a alignment field and expanded in a depth of this sphere. Details will be given for determining of equivalent dose distribution calculation using Monte Carlo computational method (ESG4) following the recommendations of ICRU. (Author)

Determinants of Work Performance in Workers with Depression and Anxiety: A Cross-Sectional Study

Directory of Open Access Journals (Sweden)

Ivana Ivandic

2017-04-01

Full Text Available Depression and anxiety are highly prevalent disorders with an impact on existential aspects of person’s life, including employment i.e., work performance (WP. In order to develop appropriate strategies, it is essential to identify determinants of WP. The objective of this study was to identify the built, social, attitudinal and health system-related environmental determinants of WP in workers with anxiety or depression in total (N = 1211 and regarding the level of disability. Hierarchical binary logistic regression was performed on data obtained from implementation of the WHO Model Disability Survey (MDS in Chile in 2015. Hindering aspects of means of transportation and workplace, and the use of personal assistance were determinants of WP for all workers with anxiety or depression. Results differed with level of disability. Hindering aspects of means of transportation and workplace, and discrimination were determinants of WP for persons with mild to moderate disability, while hindering aspects of the workplace and dwelling, and the use of personal assistance were determinants of WP for persons with severe disability. Our results emphasize the need for a broader understanding of determinants of WP and the requirement for an integrative approach in developing both universal and specific strategies that go beyond workplace settings.

Determinants of Work Performance in Workers with Depression and Anxiety: A Cross-Sectional Study.

Science.gov (United States)

Ivandic, Ivana; Kamenov, Kaloyan; Rojas, Diego; Cerón, Gloria; Nowak, Dennis; Sabariego, Carla

2017-04-26

Depression and anxiety are highly prevalent disorders with an impact on existential aspects of person's life, including employment i.e., work performance (WP). In order to develop appropriate strategies, it is essential to identify determinants of WP. The objective of this study was to identify the built, social, attitudinal and health system-related environmental determinants of WP in workers with anxiety or depression in total ( N = 1211) and regarding the level of disability. Hierarchical binary logistic regression was performed on data obtained from implementation of the WHO Model Disability Survey (MDS) in Chile in 2015. Hindering aspects of means of transportation and workplace, and the use of personal assistance were determinants of WP for all workers with anxiety or depression. Results differed with level of disability. Hindering aspects of means of transportation and workplace, and discrimination were determinants of WP for persons with mild to moderate disability, while hindering aspects of the workplace and dwelling, and the use of personal assistance were determinants of WP for persons with severe disability. Our results emphasize the need for a broader understanding of determinants of WP and the requirement for an integrative approach in developing both universal and specific strategies that go beyond workplace settings.

Identification of dose-reduction techniques for BWR and PWR repetitive high-dose jobs

International Nuclear Information System (INIS)

Dionne, B.J.; Baum, J.W.

1984-01-01

As a result of concern about the apparent increase in collective radiation dose to workers at nuclear power plants, this project will provide information to industry in preplanning for radiation protection during maintenance operations. This study identifies Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) repetitive jobs, and respective collective dose trends and dose reduction techniques. 3 references, 2 tables

Determination of eye lenses dose equivalent in terms of Hp(3)

International Nuclear Information System (INIS)

Klamert, V.; Caresana, M.; Minchillo, G.; Tambussi, O.

2002-01-01

The Italian radioprotection legislation requires the determination of personal dose equivalent in terms of H p (10) and H p (0.07) and the determination of the eye lenses dose equivalent in terms of H p (3). Whereas the calibration of a dosemeter for the determination of H p (10) and H p (0.07) is feasible, the calibration of a dosemeter in terms of H p (3) is impossible, owing to the absence of the suitable phantom and the conversion coefficients h pk (3) from air kerma to H p (3). Using an anthropomorphic phantom for the irradiation, the aim of this work is to determine the experimental values of the conversion coefficients and to relate the result of the dosemeter worn on the forehead with the dose equivalent to the eye lenses. The study is performed in the X energy range from 30 keV to 100 keV, i.e. the one most widely used in medical practices