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Sample records for radiation exposure annual

  1. Eighth annual occupational radiation exposure report, 1975

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1976-10-01

    This is a report by the U.S. Nuclear Regulatory Commission on the operation of the Commission's centralized repository of personnel occupational radiation exposure information. Annual reports were received from 387 covered licensees indicating that some 78,713 individuals, having an average exposure of 0.36 rems, were monitored for exposure to radiation during 1975 and that 21,601 individuals terminated their employment or work assignment with covered licensees in 1975. The number of personnel overexposures reported in 1975 decreased from previous years. The most significant overexposures which occurred in 1975 are summarized

  2. Occupational radiation exposure. Twelfth annual report, 1979

    International Nuclear Information System (INIS)

    Brooks, B.; McDonald, S.; Richardson, E.

    1982-08-01

    This report summarizes the occupational exposure data that is maintained in the US Nuclear Regulatory Commission's Radiation Exposure Information and Reports System (REIRS). This report is usually published on an annual basis and is available at all NRC public document rooms. The bulk of the information contained in the report was extracted from annual statistical reports submitted by all NRC licensees subject to the reporting requirements of 10 CFR 20.407. Four categories of licensees - operating nuclear power reactors, fuel fabricators and reprocessors, industrial radiographers, and manufacturers and distributors of specified quantities of byproduct materials - also submit personal identification and exposure information for terminating employees pursuant to 10 CFR 20.408, and some analysis of this data is also presented in this report

  3. Monitoring of radiation exposure. Annual report 2000

    International Nuclear Information System (INIS)

    Rantanen, E.

    2001-03-01

    At the end of 2000, there were 1,779 valid safety licenses in Finland for the use of radiation. In addition, there were 2,038 responsible parties for dental x-ray diagnostics. The registry Radiation and Nuclear Safety Authority (STUK) listed 13,754 radiation sources and 270 radionuclide laboratories. In the year 2000 360 inspections were made concerning the safety licences and 53 concerning dental x-ray diagnostics. The import of radioactive substances amounted to 175,836 GBq and export to 74,420 GBq. Short-lived radionuclides produced in Finland amounted to 55,527 GBq. In the year 2000 there were 10,846 workers monitored for radiation exposure at 1,171 work sites. Of these employees, 27% received an annual dose exceeding the recording level. The annual effective dose limit was not exceeded. The total dose recorded in the dose registry(sum of the individual dosemeter readings) was 6.5 Sv in 2000

  4. Occupational radiation exposure. Annual report No. 11 for 1978

    International Nuclear Information System (INIS)

    Brooks, B.; McDonald, S.; Richardson, E.

    1981-01-01

    This report summarizes the information reported for calendar year 1978 by all NRC licensees to the Commission's centralized repository of personnel occupational radiation exposure information. The bulk of the information in the report is derived from annual reports that were required to be submitted by all NRC licensees pursuant to 10CFR 20.407. Previously only certain categories - commercial nuclear power reactors, industrial radiographers, fuel fabricators and processors and commercial distributors of byproduct materials - of NRC licensees had submitted such reports. The requirement of 10CFR 20.408 for the submission of termination reports continued to apply to only these four categories, and some analysis of the data contained in these reports is also presented. A brief description of personnel overexposures reported by NRC licensees is included as well

  5. Radiation exposures for DOE and DOE contractor employees - 1991. Twenty-fourth annual report

    International Nuclear Information System (INIS)

    Smith, M.H.; Hui, T.E.; Millet, W.H.; Scholes, V.A.

    1994-11-01

    This is the 24th annual radiation exposure report published by US DOE and its predecessor agencies. This report summarizes the radiation exposures received by both employees and visitors at DOE and COE contractor facilities during 1991. Trends in radiations exposures are evaluated. The significance of the doses is addressed by comparing them to the DOE limits and by correlating the doses to health risks based on risk estimates from expert groups

  6. Estimating the whole-body exposure annual dose of radiation workers of petroleum nuclear well logging

    International Nuclear Information System (INIS)

    Tian Yizong; Gao Jianzheng; Liu Wenhong

    2006-01-01

    Objective: By imitating experiment of radioactive sources being installed, to estimate the annual whole-body exposure dose of radiation workers of petroleum nuclear determining wells; Methods: To compre the values of the theory, imitating experiment and γ individual dose monitor calculations. Results: The three values measured above tally with one anather. Conclusion: The annual whole-body exposure doses of radiation workers of petroleum nuclear determining wells are no more than 5 mSv. (authors)

  7. Eleventh annual report of radiation exposures for DOE and DOE contractor employees

    International Nuclear Information System (INIS)

    1978-01-01

    In 1968, the US Atomic Energy Commission (AEC) established a program for reporting certain occupationa radiation exposure information to a central radiation records repository maintained at the Union Carbide Computing Technology Center, Oak Ridge, Tennessee. Annual summaries (WASH-1350-R1 through WASH-1350-R6) were reported for the years 1968-1973 and included data on AEC contracter employees as well as employees of companies in the private sector licensed by the AEC. In January 1975, the operational functions of the AEC, including the maintenance of records on the occupational radiation exposure on contractor employees, were transferred to the Energy Research and Development Administration (ERDA) and the AEC's regulatory functions, including the reporting of information on the occupational radiation exposure of licenses, were transferred to the Nuclear Regulatory Commission (NRC). Previous AEC licenses then reported to NRC while the contractors reported to ERDA. On October 1, 1977, the Department of Energy (DOE) was formed and assumed the responsibilities of ERDA. This report contains the 1978 radiation exposure data for DOE and DOE contractors

  8. Radiation exposures for DOE and DOE contractor employees Eighteenth annual report, 1985

    International Nuclear Information System (INIS)

    1986-12-01

    All US Department of Energy (DOE) and DOE contractors are required to submit occupational radiation exposure records to a central repository. The data required include a summary of whole-body exposures to ionizing radiation, a summary of internal depositions of radioactive materials above specified limits, and occupational exposure reports for terminating employees. This report is a summary of the data submitted by DOE and DOE contractors for 1985. A total of 95,806 DOE and DOE contractor employees were monitored for whole-body ionizing radiation exposures in 1985. In addition to the employees, 96,665 visitors were monitored. Of all employees monitored, 58.4% received a dose equivalent that was less than measurable, 39.8% a measurable exposure less than 1 rem, and 1.9% an exposure greater than 1 rem. One employee received a dose equivalent greater than 5 rem (8.66 rem). The exposure received by 91.9% of the visitors to DOE facilities was less than measurable. No visitors received a dose equivalent greater than 2 rem. The collective dose equivalent for DOE and DOE contractor employees was 8223 person-rem. The collective dose equivalent for visitors was 461 person-rem. These averages are significantly less than the DOE 5-rem/year radiation protection standard for whole-body exposures. Ten new cases of internal depositions were reported in 1985 that exceeded 50% of the pertinent annual dose-equivalent standard. Of these ten cases, eight occurred in a previous year and are reported now because recent revisions in the dose calculations established these cases as reportable depositions. Twenty-six cases reported during 1985 were considered to be the continued tracking of previous depositions. 5 figs., 32 tabs

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

    International Nuclear Information System (INIS)

    Colgan, P. A.; Currivan, L.; Fenton, D.

    2008-01-01

    Whole-body occupational exposure to artificial radiation sources in Ireland for the years 1996-2005 has been reviewed. Dose data have been extracted from the database of the Radiological Protection Inst. of Ireland, which contains data on >95% of monitored workers. The data have been divided into three sectors: medical, industrial and education/ research. Data on exposure to radon in underground mines and show caves for the years 2001-05 are also presented. There has been a continuous increase in the number of exposed workers from 5980 in 1996 to 9892 in 2005. Over the same time period, the number of exposed workers receiving measurable doses has decreased from 676 in 1996 to 189 in 2005 and the collective dose has also decreased from 227.1 to 110.3 man milli-sievert (man mSv). The collective dose to workers in the medical sector has consistently declined over the 10-y period of the study while that attributable to the industrial sector has remained reasonably static. In the education/research sector, the collective dose typically represents 5% or less of the total collective dose from all practices. Over the 10 y of the study, a total of 77914 annual dose records have been accumulated, but only 4040 ( 1 mSv and 21 of these exceeded 5 mSv. Most of the doses >1 mSv were received by individuals working in diagnostic radiology (which also includes interventional radiology) in hospitals and site industrial radiography. There has been only one instance of a dose above the annual dose limit of 20 mSv. Evaluating the data for the period 2001-05 separately, the average annual collective dose from the medical, industrial and educational/research sectors are ∼60, 70 and 2 man mSv with the average dose per exposed worker who received a measurable dose being 0.32, 0.79 and 0.24 mSv, respectively. Diagnostic radiology and site industrial radiography each represents >60% of the collective dose in their respective sectors. Available data on radon exposure in one underground

  10. Occupational radiation exposure at Commercial Nuclear Power reactors 1983. Volume 5. Annual report

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1985-03-01

    This report presents an updated compilation of occupational radiation exposure at commercial nuclear power reactors for the years 1969 through 1983. The summary based on information received from the 75 light-water-cooled reactors (LWRs) and one high temperature gas-cooled reactor (HTGR). The total number of personnel monitored at LWRs in 1983 was 136,700. The number of workers that received measurable doses during 1983 and 85,600 which is about 1000 more than that found in 1982. The total collective dose at LWRs for 1983 is estimated to be 56,500 man-rems (man-cSv), which is about 4000 more man-rems (man-cSv) than that reported in 1982. This resulted in the average annual dose for each worker who received a measurable dose increasing slightly to 0.66 rems (cSv), and the average collective dose per reactor increasing by about 50 man-rems (man-cSv), and the average collective dose per reactor increasing by about 50 man-rems (man-cSv) to a value of 753 man-rems (man-cSv). The collective dose per megawatt of electricity generated by each reactor also increased slightly to an average value of 1.7 man-rems (man-cSv) per megawatt-year. Health implications of these annual occupational doses are discussed

  11. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1990: Twenty-third annual report

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-01-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1990. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1990 annual reports submitted by about 443 licensees indicated that approximately 214,568 individuals were monitored, 110,204 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.19 rem (cSv) and an average measurable dose of about 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,361 individuals completed their employment with one or more of the 443 covered licensees during 1990. Some 77,633 of these individuals terminated from power reactor facilities, and about 11,083 of them were considered to be transient workers who received an average dose of 0.67 rem (cSv)

  12. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1992. Twenty-fifth annual report, Volume 14

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-12-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1992. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10CFR20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10CFR20.408. The 1992 annual reports submitted by about 364 licensees indicated that approximately 204,365 individuals were monitored, 183,927 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measurable dose of about 0.30 (cSv). Termination radiation exposure reports were analyzed to reveal that about 74,566 individuals completed their employment with one or more of the 364 covered licensees during 1992. Some 71,846 of these individuals terminated from power reactor facilities, and about 9,724 of them were considered to be transient workers who received an average dose of 0.50 rem (cSv)

  13. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1993. Volume 15, Twenty-six annual report

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1995-01-01

    This report the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1993. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1993 annual reports submitted by about 360 licensees indicated that approximately 189,711 individuals were monitored, 169,872 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measured dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 99,749 individuals completed their employment with one or more of the 360 covered licensees during 1993. Some 91,000 of these individuals terminated from power reactor facilities, and about 12,685 of them were considered to be transient workers who received an average dose of 0.49 rem (cSv)

  14. Fourteenth annual report radiation exposures for DOE and DOE contractor employees - 1981

    International Nuclear Information System (INIS)

    1983-03-01

    All Department of Energy (DOE) and DOE contractors are required by DOE Order 5484.1, Chapter IV, to submit occupational exposure records to a central repository. The data required includes a summary of whole-body exposures to ionizing radiation, a summary of internal depositions of radioactive materials above specified limits, and occupational exposure reports for terminating employees. This report is a summary of the data submitted by DOE and DOE contractors for 1981. A total of 82,873 DOE and DOE contractor employees were monitored for whole-body ionizing radiation exposures in 1981. In addition to the employees, 84,343 visitors were monitored. Of all employees monitored, 54.43% received a dose equivalent that was less than measurable, 44.04% a measurable exposure less than 1 rem, and 1.53% an exposure granter than 1 rem. the exposure received by 88.14% of the visitors to DOE facilities was less than measurable. Only 11.85% of the visitors received a measurable exposure less than 1 rem, and 0.0% of the visitors received an exposure greater than 1 rem. No employees or visitors received a dose equivalent greater than 5 rem. The collective dose equivalent for DOE and DOE contractors employees was 6,902 person-rem. The collective dose equivalent for visitors was 579 person-rem. The total dose equivalent for employees and visitors combined was 7,481 person-rem. The average dose equivalent for all individuals (employees and visitors) monitored was 45 mrem and the average dose equivalent for all individuals who received a measurable exposure was 157 mrem. The highest average dose equivalent was observed for employees monitored at fuel processing facilities (342 mrem) and the lowest among visitors (7 mrem) to DOE facilities. These averages are significantly less than the DOE 5-rem/year radiation protection standard for whole-body exposures

  15. Radiation exposure records management

    International Nuclear Information System (INIS)

    Boiter, H.P.

    1975-12-01

    Management of individual radiation exposure records begins at employment with the accumulation of data pertinent to the individual and any previous occupational radiation exposure. Appropriate radiation monitorinng badges or devices are issued and accountability established. A computer master file is initiated to include the individual's name, payroll number, social security number, birth date, assigned department, and location. From this base, a radiation exposure history is accumulated to include external ionizing radiation exposure to skin and whole body, contributing neutron exposure, contributing tritium exposure, and extremity exposure. It is used also to schedule bioassay sampling and in-vivo counts and to provide other pertinent information. The file is used as a basis for providing periodic reports to management and monthly exposure summaries to departmental line supervision to assist in planning work so that individual annual exposures are kept as low as practical. Radiation exposure records management also includes documentation of radiation surveys performed by the health physicist to establish working rates and the individual estimating and recording his estimated exposure on a day-to-day basis. Exposure information is also available to contribute to Energy Research and Development Administration statistics and to the National Transuranium Registry

  16. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1995: Twenty-eighth annual report. Volume 17

    International Nuclear Information System (INIS)

    Thomas, M.L.

    1997-01-01

    This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission's (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1995 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high-level waste currently licensed, only six categories will be considered in this report. In 1995, the annual collective dose per reactor for light water reactor licensees (LWRs) was 199 person-cSv (person-rem). This is the same value that was reported for 1994. The annual collective dose per reactor for boiling water reactors (BWRs) was 256 person-cSv (person-rem) and, for pressurized water reactors (PWRs), it was 170 person-cSv (person-rem). Analyses of transient worker data indicate that 17,153 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1995, the average measurable dose calculated from reported data was 0.26 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.32 cSv (rem)

  17. Occupational radiation exposure at light water cooled power reactors. Annual report, 1977

    International Nuclear Information System (INIS)

    Peck, L.J.

    1979-04-01

    This report presents an updated compilation of occupational radiation exposures at commercial light water cooled nuclear power reactors (LWRs) for the years 1969 through 1977. The information contained in this document was derived from reports submitted to the United States Nuclear Regulatory Commission in accordance with requirements of individual plant Technical Specifications, and in accordance with Part 20.407 of Title 10, Chapter 1, Code of Federal Regulations (10 CFR Part 20.407). An additional 4 LWRs completed a full calendar year of commercial operation for the first time in 1977. This report now encompasses data from 57 commercially operating U.S. nuclear power plants. The number of personnel monitored at LWRs increased approximately 10% in 1977, and the average collective dose to personnel (man-rems per reactor-year) increased 14% over the 1976 average. The average number of personnel receiving measurable exposure per reactor increased 11%, and the average exposure per individual in 1977 was 0.8 rem per person

  18. Occupational radiation exposure at commercial nuclear power reactors, 1981. Annual report

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1982-11-01

    This report presents an updated compilation of occupational radiation exposures at commercial nuclear power reactors for the years 1969 through 1981. This year's report contains data received from the 70 light water cooled reactors (LWRs) and one high temperature gas cooled reactor that had been declared to be in commercial operation for at least one full year as of December 31, 1981. This represents an increase of two reactors over the number contained in last year's report. The total number of personnel monitored at LWRs in 1981 was 124,504, a slight decrease from that found in 1980. The number of workers that received measurable doses during 1981 was 82,183 which is about 2000 more than that found in 1980. The total collective dose at LWRs for 1981 is estimated to be 54,142 man-rems, which is only about 350 man-rems more than that reported in 1980. The report also presents a summary and some analyses of the exposure data contained in the termination reports that have been submitted by nuclear power licensees to the Commission pursuant to 10 CFR Section 20.408. As of December 31, 1981, personal identification and exposure information had been collected and computerized for some 210,000 of these terminating reactor personnel

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

    International Nuclear Information System (INIS)

    Hasford, F.; Owusu-banahene, J.; Otoo, F.; Adu, S.; Sosu, E. K.; Amoako, J. K.; Darko, E. O.; Emi-reynolds, G.; Nani, E. K.; Boadu, M.; Arwui, C. C.; Yeboah, J.

    2008-01-01

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

  20. Collaborative Radiological Health Laboratory annual report 1987: health effects of prenatal and postnatal whole-body exposure to ionizing radiation in the beagle dog. Annual report

    International Nuclear Information System (INIS)

    1988-09-01

    The Collaborative Radiological Health Laboratory (CRHL) was established in 1962 by the U.S. Public Health Service and Colorado State University for the purpose of determining in a carefully controlled animal experiment the lifetime hazards associated with prenatal and early postnatal exposure to ionizing radiation. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. It is a long-term (life span) study of a moderately large and long-lived mammal exposed at one of several times during development to a relatively small and discrete dose of external radiation. Ages-at-irradiation selected for comparison reflect the primary concern with medical exposures during the developmental period. The basic experiment under the contract contains 1,680 beagles that will be maintained and evaluated for most of their natural lives. The annual report summarizes the current status of the study for the reporting period of November 21, 1986 through November 20, 1987

  1. Radiation exposure

    International Nuclear Information System (INIS)

    Dalton, L.K.

    1991-01-01

    The book gives accounts of some social and environmental impacts of the developing radiation industries, including the experiences of affected communities and individuals. Its structure is based on a division which has been made between nuclear and non-nuclear radiation sources, because they create distinctly different problems for environmental protection and so for public health policy. The emissions from electronic and electrical installations - the non-nuclear radiations - are dealt with in Part I. Emissions from radioactive substances - the nuclear radiations - are dealt with in Part II. Part III is for readers who want more detailed information about scientific basis of radiation-related biological changes and their associated health effects. 75 refs., 9 tabs., 7 figs., ills

  2. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1996: Twenty-ninth annual report. Volume 18

    International Nuclear Information System (INIS)

    Thomas, M.L.

    1998-02-01

    This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission's (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1996 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high level waste currently licensed, only six categories will be considered in this report. Annual reports for 1996 were received from a total of 300 NRC licensees, of which 109 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted by the 300 licensees indicated that 138,310 individuals were monitored, 75,139 of whom received a measurable dose. The collective dose incurred by these individuals was 21,755 person-cSv (person-rem) 2 which represents a 13% decrease from the 1995 value. The number of workers receiving a measurable dose also decreased, resulting in the average measurable dose of 0.29 cSv (rem) for 1996. The average measurable dose is defined to be the total collective dose (TEDE) divided by the number of workers receiving a measurable dose. These figures have been adjusted to account for transient reactor workers. Analyses of transient worker data indicate that 22,348 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1996, the average measurable dose calculated from reported was 0.24 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.29 cSv (rem)

  3. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1996: Twenty-ninth annual report. Volume 18

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, M.L. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Hagemeyer, D. [Science Applications International Corp., Oak Ridge, TN (United States)

    1998-02-01

    This report summarizes the occupational exposure data that are maintained in the US Nuclear Regulatory Commission`s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 1996 annual reports submitted by six of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Since there are no geologic repositories for high level waste currently licensed, only six categories will be considered in this report. Annual reports for 1996 were received from a total of 300 NRC licensees, of which 109 were operators of nuclear power reactors in commercial operation. Compilations of the reports submitted by the 300 licensees indicated that 138,310 individuals were monitored, 75,139 of whom received a measurable dose. The collective dose incurred by these individuals was 21,755 person-cSv (person-rem){sup 2} which represents a 13% decrease from the 1995 value. The number of workers receiving a measurable dose also decreased, resulting in the average measurable dose of 0.29 cSv (rem) for 1996. The average measurable dose is defined to be the total collective dose (TEDE) divided by the number of workers receiving a measurable dose. These figures have been adjusted to account for transient reactor workers. Analyses of transient worker data indicate that 22,348 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient workers by multiple licensees. In 1996, the average measurable dose calculated from reported was 0.24 cSv (rem). The corrected dose distribution resulted in an average measurable dose of 0.29 cSv (rem).

  4. Radiation exposure from incorporated isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Beleznay, F [Hungarian Academy of Sciences, Budapest. Central Research Inst. for Physics

    1985-01-01

    Recommendations for the limitation of the burden of the human body from radiation exposure were developed to avoid direct radiation health damage such that the occurrence of stochastic damage can be held below a resonable risk level. The recommendations, published under ICRP 26 and ICRP 30, contain several guidelines and concepts which are discussed here. They include the primary internal dose exposure limits, secondary and implied limits for the monitoring of internal radiation exposure (Annual Limit of Intake, Derived Air Concentrations). Methods are presented for inspection and monitoring of internal exposure in medical laboratories, inspection of incorporation of sup(131)I and sup(99m)Tc.

  5. DOE 2012 occupational radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-10-01

    The U.S. Department of Energy (DOE) Office of Analysis within the Office of Health, Safety and Security (HSS) publishes the annual DOE Occupational Radiation Exposure Report to provide an overview of the status of radiation protection practices at DOE (including the National Nuclear Security Administration [NNSA]). The DOE 2012 Occupational Radiation Exposure Report provides an evaluation of DOE-wide performance regarding compliance with Title 10, Code of Federal Regulations (C.F.R.), Part 835, Occupational Radiation Protection dose limits and as low as reasonably achievable (ALARA) process requirements. In addition, the report provides data to DOE organizations responsible for developing policies for protection of individuals from the adverse health effects of radiation. The report provides a summary and an analysis of occupational radiation exposure information from the monitoring of individuals involved in DOE activities. Over the past 5-year period, the occupational radiation exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site.

  6. DOE 2011 occupational radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2012-12-01

    The U.S. Department of Energy (DOE) Office of Analysis within the Office of Health, Safety and Security (HSS) publishes the annual DOE Occupational Radiation Exposure Report to provide an overview of the status of radiation protection practices at DOE (including the National Nuclear Security Administration [NNSA]). The DOE 2011 Occupational Radiation Exposure Report provides an evaluation of DOE-wide performance regarding compliance with Title 10, Code of Federal Regulations (C.F.R.), Part 835, Occupational Radiation Protection dose limits and as low as reasonably achievable (ALARA) process requirements. In addition, the report provides data to DOE organizations responsible for developing policies for protection of individuals from the adverse health effects of radiation. The report provides a summary and an analysis of occupational radiation exposure information from the monitoring of individuals involved in DOE activities. The occupational radiation exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site over the past five years.

  7. DOE 2010 occupational radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-11-01

    The U.S. Department of Energy (DOE) Office of Analysis within the Office of Health, Safety and Security (HSS) publishes the annual DOE Occupational Radiation Exposure Report to provide an overview of the status of radiation protection practices at DOE.* The DOE 2010 Occupational Radiation Exposure Report provides an evaluation of DOE-wide performance regarding compliance with DOE Part 835 dose limits and as low as reasonably achievable (ALARA) process requirements. In addition, the report provides data to DOE organizations responsible for developing policies for protection of individuals from the effects of radiation. The report provides a summary and an analysis of occupational radiation exposure information from the monitoring of individuals involved in DOE activities. The occupational radiation exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site over the past 5 years.

  8. Radiation Exposure and Pregnancy

    Science.gov (United States)

    Fact Sheet Adopted: June 2010 Updated: June 2017 Health Physics Society Specialists in Radiation Safety Radiation Exposure and ... radiation and pregnancy can be found on the Health Physics Society " Ask the Experts" Web site. she should ...

  9. Radiation practices. Annual report 2002

    International Nuclear Information System (INIS)

    Rantanen, E.

    2003-06-01

    A total of 1820 safety licences granted for the use of radiation in Finland were current at the end of 2002. There were also 2037 undertakings for dental X-ray diagnostics (licencefree). The Safety Licence Register of the Radiation and Nuclear Safety Authority (STUK) listed 14 120 radiation devices and 262 radionuclide laboratories. In 2002, STUK performed 401 inspections of licensed practices and 25 inspections of licence-free dental X-ray practices. Restrictions were ordered on the use of one device. Repairs were ordered in 116 cases and recommended in 55 cases. No remarks were given in 254 cases. Imports of radioactive substances amounted to 110 157 GBq and exports totalled 22 359 GBq. Short-lived radionuclides produced in Finland amounted to 42 487 GBq. The STUK interim storage for radioactive wastes received 65 batches of low-level wastes. A total of 11 190 workers were individually monitored for radiation exposure at 1176 workplaces. Of these workers, some 32% were category A workers and 67% category B workers. In no case were annual dose limits exceeded. The total dose in the use of radiation and nuclear energy recorded in the STUK Dose Register was 6.35 Sv. The mean doses in typical diagnostic X-ray procedures based on phantom measurements were below the reference levels issued by the European Community, the IAEA and STUK. Accuracy of the therapeutic doses underlying good therapeutic results in radiotherapy has remained within acceptable limits, and no excessive doses jeopardizing the safety of therapy have occurred. In the regulatory control of natural radiation, inspection reports requesting performance of radon repairs or measurements of radon concentrations were sent to 145 enterprises. Underground radon inspections were performed in 4 mines and 7 excavation sites. The mean effective dose to aircraft crew caused by cosmic radiation was 1.6 mSv. Ministry of Social Affairs and Health Decree on the Limitation of Public Exposure to Non-Ionizing Radiation

  10. Ambient radioactivity levels and radiation doses. Annual report 2009

    International Nuclear Information System (INIS)

    Bernhard-Stroel, Claudia; Hachenburger, Claudia; Trugenberger-Schnabel, Angela; Peter, Josef

    2010-12-01

    The annual report on environmental radioactivity and radiation exposure 2009 consists of two parts. Part A: General information: natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposures from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. Part B includes current data and their evaluation for natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposures from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation.

  11. Radiation exposures: risks and realities

    International Nuclear Information System (INIS)

    Ganesh, G.

    2010-01-01

    Discovery of radioactivity in 1869 by Henry Becquerel and artificial radioactivity by Irene Curie in 1934 led to the development of nuclear field and nuclear materials in 20th century. They are widely used for man-kind across the globe in electricity production, carbon dating, treatment and diagnosis of diseases etc. While deriving benefits and utilizing nuclear resources for the benefit of man-kind, it is inevitable that exposure to radiation can not be avoided. Radiation exists all around us either natural or man-made which can not be totally eliminated or avoided. Radiation exposures from natural background contribute 2.4 to 3.6 mSv in a year. Radiation exposures incurred by a member of public due to nuclear industries constitute less than one hundredth of annual dose due to natural background. Hence it is important to understand the risk posed by radiation and comparison of radiation risk with various risks arising due to other sources. Studies have indicated that risks due to environmental pollution, cigarette smoking, alcohol consumption, heart diseases are far higher in magnitude compared to radiation risks from man made sources. This paper brings about the details and awareness regarding radiation exposures, radiation risk, various risks associated with other industries and benefits of radiation exposures. (author)

  12. Monitoring of radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service.

  13. Monitoring of radiation exposure

    International Nuclear Information System (INIS)

    2000-02-01

    The guide specifies the requirements for the monitoring of radiation exposure in instances where radiation is used. In addition to workers, the guide covers students, apprentices and visitors. The guide shall also apply to exposure from natural radiation. However, the monitoring of radiation exposure in nuclear power plants is dealt with in YVL Guide 7.10 and 7.11. The guide defines the concepts relevant to the monitoring of radiation exposure and provides guidelines for determining the necessity of monitoring and subsequently arranging such in different operations. In addition, the guide specifies the criteria for the approval and regulatory control of the dosimetric service

  14. Radiation camera exposure control

    International Nuclear Information System (INIS)

    Martone, R.J.; Yarsawich, M.; Wolczek, W.

    1976-01-01

    A system and method for governing the exposure of an image generated by a radiation camera to an image sensing camera is disclosed. The exposure is terminated in response to the accumulation of a predetermined quantity of radiation, defining a radiation density, occurring in a predetermined area. An index is produced which represents the value of that quantity of radiation whose accumulation causes the exposure termination. The value of the predetermined radiation quantity represented by the index is sensed so that the radiation camera image intensity can be calibrated to compensate for changes in exposure amounts due to desired variations in radiation density of the exposure, to maintain the detectability of the image by the image sensing camera notwithstanding such variations. Provision is also made for calibrating the image intensity in accordance with the sensitivity of the image sensing camera, and for locating the index for maintaining its detectability and causing the proper centering of the radiation camera image

  15. Hazards of radiation exposure

    International Nuclear Information System (INIS)

    Solomon, S.B.

    1982-01-01

    Radiation induced carcinogenesis and mutagenesis form the main risks to health from exposure to low levels of radiation. There is scant data on somatic and genetic risks at environmental and occupational levels of radiation exposure. The available data on radiation induced carcinogenesis and mutagenesis are for high doses and high dose rates of radiation. Risk assessments for low level radiation are obtained using these data, assuming a linear dose-response relationship. During uranium mining the chief source of radiation hazard is inhalation of radon daughters. The correlation between radon daughter exposure and the increased incidence of lung cancer has been well documented. For radiation exposures at and below occupational limits, the associated risk of radiation induced cancers and genetic abnormalities is small and should not lead to a detectable increase over naturally occurring rates

  16. Radiation exposure management

    International Nuclear Information System (INIS)

    Snihs, J.O.

    1985-01-01

    Radiation exposure management includes administrative control, education and training, monitoring and dose assessments and planning of work and radiation protection. The information and discussion given in the paper are based on experiences in Sweden mainly from nuclear power installations. (Author)

  17. Natural radiation exposure indoors

    International Nuclear Information System (INIS)

    Brown, L.; Cliff, K.D.; Wrixon, A.D.

    1981-01-01

    A brief review is presented of the state of knowledge of indoor natural radiation exposure in the U.K. and the current survey work the N.R.P.B. is carrying out in this field. Discussion is limited in this instance to the improvement in estimation of population exposure and the identification of areas and circumstances in which high exposure occur, rather than the study of properties of a building and methods of building affecting exposure to radiation. (U.K.)

  18. Volume of baseline data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes of the annual report 1988 'Environmental radioactivity and radiation exposure'

    International Nuclear Information System (INIS)

    Abelmann, S.; Buenger, T.; Fusban, H.U.; Ruehle, H.; Viertel, H.; Gans, I.

    1991-01-01

    This WaBoLu volume is a shortened version of the annual report by the Federal Ministry of the Environment, Nature Protection and Reactor Safety 'Environmental radioactivity and radiation exposure' and gives an overview of the data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes, compiled for the area of the Federal Republic of Germany in 1988 by the Institute of Water, Soil and Air Hygiene (WaBoLu) of the Federal Health Office. (BBR) With 22 figs., 15 tabs [de

  19. Exposure to natural radiation

    International Nuclear Information System (INIS)

    Green, B.M.R.

    1985-01-01

    A brief report is given of a seminar on the exposure to enhanced natural radiation and its regulatory implications held in 1985 at Maastricht, the Netherlands. The themes of the working sessions included sources of enhanced natural radiation, parameters influencing human exposure, measurement and survey programmes, technical countermeasures, risk and assessment studies, philosophies of dose limitations and national and international policies. (U.K.)

  20. Ambient radioactivity levels and radiation doses. Annual report 2011

    International Nuclear Information System (INIS)

    Bernhard-Stroel, Claudia; Hachenburger, Claudia; Trugenberger-Schnabel, Angela; Peter, Josef

    2013-07-01

    The annual report 2011 on ambient radioactivity levels and radiation doses covers the following issues: Part A: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. Part B; Current data and their evaluation: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. The Appendix includes Explanations of terms, radiation doses and related units, external and internal radiation exposure, stochastic and deterministic radiation effects, genetic radiation effects, induction of malignant neoplasm, risk assessment, physical units and glossary, laws, ordinances, guidelines, recommendations and other regulations concerning radiation protection, list of selected radionuclides.

  1. Radiation exposure and radiation protection

    International Nuclear Information System (INIS)

    Heuck, F.; Scherer, E.

    1985-01-01

    The present volume is devoted to the radiation hazards and the protective measures which can be taken. It describes the current state of knowledge on the changes which exposure to ionizing rays and other forms of physical energy can induce in organs and tissues, in the functional units and systems of the organism. Special attention is paid to general cellular radiation biology and radiation pathology and to general questions of the biological effects of densely ionizing particle radiation, in order to achieve a better all-round understanding of the effects of radiation on the living organism. Aside from the overviews dealing with the effects of radiation on the abdominal organs, urinary tract, lungs, cerebral and nervous tissue, bones, and skin, the discussion continues with the lymphatic system, the bone marrow as a bloodforming organ, and the various phases of reaction in the reproductive organs, including damage and subsequent regeneration. A special section deals with environmental radiation hazards, including exposure to natural radiation and the dangers of working with radioactive substances, and examines radiation catastrophes from the medical point of view. Not only reactor accidents are covered, but also nuclear explosions, with exhaustive discussion of possible damage and treatment. The state of knowledge on chemical protection against radiation is reviewed in detail. Finally, there is thorough treatment of the mechanism of the substances used for protection against radiation damage in man and of experience concerning this subject to date. In the final section of the book the problems of combined radiotherapy are discussed. The improvement in the efficacy of tumor radiotherapy by means of heavy particles is elucidated, and the significance of the efficacy of tumor therapy using electron-affinitive substances is explained. There is also discussion of the simultaneous use of radiation and pharmaceuticals in the treatment of tumors. (orig./MG) [de

  2. DOE 2013 occupational radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-11-01

    The Office of Analysis within the U.S. Department of Energy (DOE) Office of Environment, Health, Safety and Security (EHSS) publishes the annual DOE Occupational Radiation Exposure Report to provide an overview of the status of radiation protection practices at DOE (including the National Nuclear Security Administration [NNSA]). The DOE 2013 Occupational Radiation Exposure Report provides an evaluation of DOE-wide performance regarding compliance with Title 10, Code of Federal Regulations (C.F.R.), Part 835, Occupational Radiation Protection dose limits and as low as reasonably achievable (ALARA) process requirements. In addition, the report provides data to DOE organizations responsible for developing policies for protection of individuals from the adverse health effects of radiation. The report provides a summary and an analysis of occupational radiation exposure information from the monitoring of individuals involved in DOE activities. Over the past five-year period, the occupational radiation exposure information has been analyzed in terms of aggregate data, dose to individuals, and dose by site.

  3. Americans' Average Radiation Exposure

    International Nuclear Information System (INIS)

    2000-01-01

    We live with radiation every day. We receive radiation exposures from cosmic rays, from outer space, from radon gas, and from other naturally radioactive elements in the earth. This is called natural background radiation. It includes the radiation we get from plants, animals, and from our own bodies. We also are exposed to man-made sources of radiation, including medical and dental treatments, television sets and emission from coal-fired power plants. Generally, radiation exposures from man-made sources are only a fraction of those received from natural sources. One exception is high exposures used by doctors to treat cancer patients. Each year in the United States, the average dose to people from natural and man-made radiation sources is about 360 millirem. A millirem is an extremely tiny amount of energy absorbed by tissues in the body

  4. Radiation exposure during ESWL

    International Nuclear Information System (INIS)

    McCullough, D.L.; Van Swearingen, F.L.; Dyer, R.B.; Appel, B.

    1987-01-01

    This paper discusses exposure to ionizing radiation by the ESWL patient and for health professionals. Although the patient is exposed acutely to the highest level of radiation, the lithotripter team is chronically exposed to ionizing radiation at varying levels. Attention to detail is important in reducing that exposure. The operator should follow the guidelines set forth in this chapter in order to minimize exposure to the patient, himself or herself, and to all co-workers. At the present time, investigation of an alternative modality for stone localization, ultrasound, is being investigated

  5. Collaborative Radiological Health Laboratory annual report 1986: health effects of prenatal and postnatal whole-body exposure to ionizing radiation in the beagle dog

    International Nuclear Information System (INIS)

    1987-08-01

    The Collaborative Radiological Health Laboratory was established in 1962 by the U.S. Public Health Service and Colorado State University for the purpose of determining in a carefully controlled animal experiment the life-time hazards associated with prenatal and early postnatal exposure to ionizing radiation. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. This is a long-term (lifespan) study of a moderately large and long-lived mammal exposed at one of several times during development to a relatively small and discrete dose of external radiation. Ages-at-irradiation selected for comparison reflect the primary concern with medical exposures during the development period. The basis experiment under this contract contains 1,680 beagles that will be maintained and evaluated for most of their natural lives. Commitment of animals began in December 1967 and was completed in October 1972. The annual report summarizes the current status of the study for the reporting period of November 21, 1985 through November 20, 1986

  6. Collaborative Radiological Health Laboratory annual report, 1988: Health effects of prenatal and postnatal whole-body exposure to ionizing radiation in the beagle dog

    International Nuclear Information System (INIS)

    1989-09-01

    The Collaborative Radiological Health Laboratory was established in 1962 by the U.S. Public Health Service and Colorado State University for the purpose of determining, in a carefully controlled animal experiment, the life-time hazards associated with prenatal and early postnatal exposure to ionizing radiation. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. This is a long-term (life span) study of a moderately large and long-lived mammal exposed at one of several times during development to a relatively small and discrete dose of external radiation. Ages-at-irradiation selected for comparison reflect the primary concern with medical exposures during the developmental period. The basic experiment under the contract contains 1,680 beagles that will be maintained and evaluated for most of their natural lives. Commitment of animals began in December 1967 and was completed in February 1973. The annual report summarizes the current status of the study for the reporting period of November 21, 1987 through November 20, 1988

  7. Collaborative Radiological Health Laboratory annual report 1985: health effects of prenatal and postnatal whole-body exposure to ionizing radiation in the beagle dog

    International Nuclear Information System (INIS)

    1986-07-01

    The Collaborative Radiological Health Laboratory was established in 1962 by the U.S. Public Health Service and Colorado State University for the purpose of determining in a carefully controlled animal experiment the life-time hazards associated with prenatal and early postnatal exposure to ionizing radiation. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. This is a long-term (lifespan) study of a moderately large and long-lived mammal exposed at one of several times during development to a relatively small and discrete dose of external radiation. Ages-at-irradiation selected for comparison reflect the primary concern with medical exposures during the development period. The basic experiment under the contract contains 1,680 beagles that will be maintained and evaluated for most of their natural lives. Commitment of animals began in December 1967 and was completed in October 1972. The annual report summarizes the current status of the study for the reporting period of November 21, 1984 through November 20, 1985

  8. Occupational radiation exposure in Slovakia

    International Nuclear Information System (INIS)

    Boehm, K.; Cabanekova, H.

    2014-01-01

    Recently are 2 nuclear power plants in operation in the Slovak republic. Apart from nuclear facilities there are 450 licensed undertakings with monitored workers. The majority of the licensed undertakings are active in health care. In Slovak republic are five dosimetry services performing assessments on personal doses due to external exposure and two dosimetry services are approved to carry out monitoring of internal exposure. Dosemeters used for the monitoring of external individual exposure include: personal whole-body film dosemeters, thermoluminescence dosemeters (TLD) or optically stimulated luminescence dosimeters (OSL) for measurements of beta and gamma radiation; TLD for measurements of neutron radiation and TLD for extremities. The measured operational dose quantities are Hp(10), Hp(3) and Hp(0.07). Approved dosimetry service reports the measured dose data to the employers and to the Central register of occupational doses (CROD). Annually are monitored about 12500 - 16200 active workers. Average effective doses per one monitored worker are presented. (author)

  9. Ionizing radiation, radiation sources, radiation exposure, radiation effects. Pt. 2

    International Nuclear Information System (INIS)

    Schultz, E.

    1985-01-01

    Part 2 deals with radiation exposure due to artificial radiation sources. The article describes X-ray diagnosis complete with an analysis of major methods, nuclear-medical diagnosis, percutaneous radiation therapy, isotope therapy, radiation from industrial generation of nucler energy and other sources of ionizing radiation. In conclusion, the authors attempt to asses total dose, genetically significant dose and various hazards of total radiation exposure by means of a summation of all radiation impacts. (orig./WU) [de

  10. Radiation exposure during ureteroscopy

    International Nuclear Information System (INIS)

    Bagley, D.H.; Cubler-Goodman, A.

    1990-01-01

    Use of fluoroscopy during ureteroscopy increases the risk of radiation exposure to the urologist and patient. Radiation entrance dosages were measured at skin level in 37 patients, and at the neck, trunk and finger of the urologist, and neck and trunk of the circulating nurse. Radiation exposure time was measured in 79 patients, and was related to the purpose of the procedure and the type of ureteroscope used, whether rigid or flexible. Exposure could be minimized by decreasing the fluoroscopy time. A portable C-arm fluoroscopy unit with electronic imaging and last image hold mode should be used to minimize exposure time. Lead aprons and thyroid shields should be used by the urologist and other personnel in the endoscopy room

  11. Radiation Practices. Annual report 2004

    International Nuclear Information System (INIS)

    Rantanen, E.

    2005-06-01

    A total of 1791 safety licences for the use of radiation were current at the end of 2004. There were 1924 responsible parties engaged in licence-exempt dental X-ray practices, made notifiable to STUK. Regulatory control of the use of radiation was carried out through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of a Dose Register. Radiation safety guides were also published and research was conducted to support the regulatory control. In 2004, STUK conducted 438 inspections of licensed practices and 38 inspections of notifiable licence-exempt dental X-ray practices. Restrictions were imposed on the use of five appliances. Repairs were ordered in 150 inspections and recommended in 85 inspections. No remarks were given in 229 inspections. A total of 11 082 workers engaged in radiation work were subject to individual monitoring in 2004. 135 000 dose entries were made in the register maintained by STUK. In no case did the individual dose of any worker exceed the dose limits stipulated in the Radiation Decree. Regulatory control of natural radiation concentrated on radon at workplaces and exposure of aircrews to cosmic radiation. At the end of 2004, 55 workplaces including a total of 74 work areas were subject to radon monitoring. A total of 2540 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation focused particularly on mobile phones and sunbeds. Radiation safety assessments were also made for public broadcasting equipment, radars, 'artificial sun' aboard a cruise liner, UVC bactericide lamps in a bakery and show laser lights. A recommendation on radiation safety for sunbeds was prepared in association with other Nordic countries. Most research and development work was done in jointly financed research projects and

  12. NTPR Radiation Exposure Reports

    Science.gov (United States)

    History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak Atoll Cleanup Documents TRAC About Who We Are Our Values History Locations Our Leadership Director Support Center Contact Us FAQ Sheet Links Success Stories Contracts Business Opportunities Current

  13. 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.

  14. Radiation practices. Annual report 2008

    International Nuclear Information System (INIS)

    Rantanen, E.

    2009-09-01

    1775 safety licences for the use of radiation were current at the end of 2008. 1831 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. STUK conducted 424 inspections of licensed practices and 18 inspections of notifiable licence-exempt dental X-ray practices in 2008. 209 repair orders and recommendations were issued. Use of one appliance was prohibited. A total of just over 11 500 workers were subject to individual monitoring in 2008, and about 140 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 89 workplaces including a total of 201 work areas were subject to radon monitoring during 2008. Some 3700 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation in 2008 focused particularly on mobile phones, sunbeds and lasers. Ten mobile phone types and five baby monitors were tested in market surveillance of wireless communication devices. 25 sunbed facilities were inspected and nine laser display inspections were performed. There were 22 abnormal incidents involving the use of radiation in 2008. Seventeen of these incidents concerned the use of radiation in industry, research or transportation, four concerned the use of radiation in health care, and one concerned the use of non-ionizing radiation. None of these incidents had serious consequences. (orig.)

  15. Radiation Practices. Annual Report 2003

    International Nuclear Information System (INIS)

    Rantanen, E.

    2004-01-01

    A total of 1811 safety licences for the use of radiation were current at the end of 2003. There were 1962 responsible parties engaged in licence-exempt dental X-ray practices, made notifiable to STUK. Regulatory control of the use of radiation was carried out through regular inspections performed at places of use, postal control, guidance, maintenance of a Dose Register and research intended to support the regulatory control. A total of 10 900 workers engaged in radiation work were subject to individual monitoring in 2003. 135 000 dose entries were made in the register maintained by STUK. In no case did the individual dose of any worker exceed the dose limits stipulated in the Radiation Decree. Regulatory control of natural radiation concentrated on radon at workplaces and exposure of aircrews to cosmic radiation. At the end of 2003, 90 workplaces including a total of 141 work areas were subject to ongoing radon monitoring. A total of 2485 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. The DOS Laboratory of STO joined the international MRA agreement on the 'self declaration principle'. Regulatory control of the use of non-ionizing radiation focused particularly on mobile phones and sun-beds. Mobile phone market control began by measuring the radiation produced by a range of 12 mobile phones of varying type. Spot check inspections were conducted at tanning facilities and a report was completed on radiation safety improvements at such establishments. A method of measurement based on commercial CCD spectroradiometers was developed for spectral measurements of UV phototherapy appliances and sunbeds. The said method is also suitable for measurements at places of use. A new type of magnetometer, which measures peak values over a wide frequency band weighted according to exposure limits, was developed for measuring low frequency magnetic fields. In

  16. Radiation practices. Annual report 2011

    Energy Technology Data Exchange (ETDEWEB)

    Rantanen, E. (ed.)

    2012-09-15

    1791 safety licences for the use of radiation were current at the end of 2011. 1702 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 575 inspections of licensed practices in 2011. 633 repair orders and recommendations were issued in the course of inspections. A total of nearly 11 700 workers were subject to individual monitoring in 2011 and about 143 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 166 workplaces including a total of 288 work areas were subject to radon monitoring during 2011. Just over 3600 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK was involved in four ionizing radiation research projects, and also took part in an international expert group evaluation of STUK research activities. New alpha and beta sources were procured for metrological activities and a Co-60 irradiation device procured in 2010 was installed and taken into use. Calibration and testing services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2011 focused particularly on mobile phones, sunbeds and lasers. Orders were issued to 5 responsible parties to discontinue the use of tattoo removal lasers. 7 sunbed facilities were inspected and 10 on-site laser display inspections were performed. Five mobile phone types were tested in market surveillance of wireless communication devices. Non-ionizing radiation research activities were also subjected to the evaluation of STUK research activities

  17. Radiation Practices. Annual Report 2005

    International Nuclear Information System (INIS)

    Rantanen, E.

    2006-06-01

    1764 safety licences for the use of radiation were current at the end of 2005. 1907 responsible parties were engaged in notifiable licence-exempt dental X-ray practices. Regulatory control of the use of radiation was performed through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. STUK conducted 458 inspections of licensed practices and 62 inspections of notifiable licence-exempt dental X-ray practices in 2005. 273 remedial orders and recommendations were issued. Use of one appliance was prohibited. A total of 11 698 workers engaged in radiation work were subject to individual monitoring in 2005. 137 000 dose entries were made in the Dose Register. In no case did the individual dose of any worker exceed the dose limits stipulated in the Radiation Decree. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 90 workplaces including a total of 233 work areas were subject to radon monitoring during 2005. 2600 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation in 2005 continued to focus particularly on mobile phones and sunbeds. 15 mobile phone types were tested in market surveillance of mobile phones. A total of 44 sunbed appliances were inspected at 36 sunbed facilities. Most research and development work took place within jointly financed research projects. This work focused especially on developing testing and measuring methods for determining exposure to electromagnetic fields caused by mobile phones and their base stations. There were 13 abnormal incidents involving the use of radiation in 2005. Eight of these incidents concerned

  18. Radiation hormesis at occupational exposure

    International Nuclear Information System (INIS)

    Zaharieva, E.; Georgieva, R.

    2006-01-01

    Full text: The aim of our work was to find appropriate biomarkers applicable in molecular epidemiological surveys of occupationally exposed individuals to prove radiation hormesis. Blood samples were taken from a group of irradiated persons, and from a control group. For each worker we estimated a parameter arbitrarily called by us 'mean annual dose' as a quotient of cumulated dose and length of service. DNA repair synthesis in leucocytes before and after in vitro exposure to a challenge dose of 2.0 Gy gamma rays was determined by the level of incorporation of radioactively labeled nucleotides, level of DNA damage in lymphocytes was analyzed by single cell gel electrophoresis and level of lipid peroxidation processes was evaluated by malonedialdehyde concentration in blood plasma. A significant decrease of potentially lethal damage in persons with 'mean annual dose' lower or equal to 5 mSv/y was found, compared to the control group. The highest repair capacity after a challenging dose of 2.0 Gy gamma rays as well as a significant decrease in the level of oxidative stress determined in the blood plasma was evaluated for persons from the same group. The present investigation of occupationally exposed workers showed that annual doses no higher than twice the natural radiation background exert positive effects on DNA damage and repair, increase cellular resistance and decrease oxidative stress

  19. Radiation practices. Annual report 2009

    International Nuclear Information System (INIS)

    Rantanen, E.

    2010-08-01

    1 742 safety licences for the use of radiation were current at the end of 2009. 1 820 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 414 inspections of licensed practices in 2009. 392 repair orders and recommendations were issued. A total of nearly 11 600 workers were subject to individual monitoring in 2009. Just under 160 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 108 workplaces including a total of 219 work areas were subject to radon monitoring during 2009. 3655 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK took part in three major ionizing radiation research projects. An IAEA research project tested IAEA/WHO diagnostic dosimetry guidelines. The accuracy and reliability of internal and external radiotherapy dosimetric methods in modern radiotherapy technology was studied as part of a European metrology research programme. In metrological activities the calibration procedure for radiotherapy accelerator electron beam dosemeters was modified by changing from meter calibration in hospitals to laboratory calibration. Some irradiation appliances were also replaced. Calibration services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2009 focused particularly on mobile phones, sunbeds and lasers. Fifteen mobile phone types were tested in market surveillance of wireless communication devices. 19 sunbed facilities were inspected and ten laser display inspections were

  20. Radiation practices. Annual report 2010

    Energy Technology Data Exchange (ETDEWEB)

    Rantanen, E. (ed.)

    2011-07-01

    1760 safety licences for the use of radiation were current at the end of 2010. 1789 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 384 inspections of licensed practices in 2010. 447 repair orders and recommendations were issued in the course of inspections. A total of nearly 12 100 workers were subject to individual monitoring in 2010. Just under 160 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 140 workplaces including a total of 348 work areas were subject to radon monitoring during 2010. 3428 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK took part in three major ionizing radiation research projects. An IAEA research project tested diagnostic dosimetry guidelines. The accuracy and reliability of internal and external radiotherapy dosimetric methods in modern radiotherapy technology were studied as part of a European metrology research programme. In metrological activities the dosemeter calibration procedure for radiotherapy accelerator electron beams was modified by changing from meter calibrations in hospitals to laboratory calibrations. Some irradiation appliances were also replaced. Calibration services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2010 focused particularly on mobile phones, sunbeds and lasers. 16 sunbed facilities were inspected and 8 on-site laser display inspections were performed. Ten mobile phone types were tested in market surveillance of

  1. Doses from radiation exposure

    CERN Document Server

    Menzel, H G

    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 effecti...

  2. Exposure to background radiation in Australia

    Energy Technology Data Exchange (ETDEWEB)

    Solomon, S.B. [Australian Radiation Lab., Melbourne, VIC (Australia)

    1997-12-31

    The average effective dose received by the Australian population is estimated to be {approx}1.8 mSv / year. One half of this exposure arises from exposure from terrestrial radiation and cosmic rays, the remainder from radionuclides within the body and from inhalation of radon progeny. This paper reviews a number of research programmes carried out by the Australian Radiation Laboratory to study radiation exposure from natural background, particularly in the workplace and illustrate approaches to the quantification and management of exposure to natural radiation. The average radiation doses to the Australian population are relatively low; the average annual radon concentration ranged from 6 Bq m{sup -3} in Queensland to 16 Bq m{sup -3} in the Australian Capital Territory (ACT). Of more importance is the emerging issue of exposure to elevated background radiation in the workplace. Two situation are presented; the radiation exposure to air crues and show cave tour guides. Annual doses up to 3.8 mSv were estimated for international crew members while the highest estimate for show cave tour guides was 9 mSv per year. 9 refs., 2 tabs., 4 figs.

  3. Exposure to background radiation in Australia

    International Nuclear Information System (INIS)

    Solomon, S.B.

    1997-01-01

    The average effective dose received by the Australian population is estimated to be ∼1.8 mSv / year. One half of this exposure arises from exposure from terrestrial radiation and cosmic rays, the remainder from radionuclides within the body and from inhalation of radon progeny. This paper reviews a number of research programmes carried out by the Australian Radiation Laboratory to study radiation exposure from natural background, particularly in the workplace and illustrate approaches to the quantification and management of exposure to natural radiation. The average radiation doses to the Australian population are relatively low; the average annual radon concentration ranged from 6 Bq m -3 in Queensland to 16 Bq m -3 in the Australian Capital Territory (ACT). Of more importance is the emerging issue of exposure to elevated background radiation in the workplace. Two situation are presented; the radiation exposure to air crues and show cave tour guides. Annual doses up to 3.8 mSv were estimated for international crew members while the highest estimate for show cave tour guides was 9 mSv per year

  4. Aircrew radiation exposure assessment for Yugoslav airlines

    Energy Technology Data Exchange (ETDEWEB)

    Antic, Dragoljub [Vinca Inst. of Nuclear Sciences, Belgrade (Yugoslavia); Petrovic, Zika [Yugoslav Airlines, JAT, Bulevar umetnosti 16, 11001 Belgrade (Yugoslavia)

    1997-12-31

    The presented study shows that the crews of the intercontinental flights can receive significant annual effective doses (1.5-2.0 mSv). The exposure of the crews is comparable with natural radiation level on the ground level (it can be up to 5 times higher for some air crew members in the intercontinental flights), but smaller than maximum permissible dose for general population. The annual exposures of the passengers are generally smaller than the exposures of tile air crews. because the passengers have a limited number of flights per year compared with the members of the air-crews. (author).

  5. Occupational radiation exposures in Canada - 1982

    International Nuclear Information System (INIS)

    Fujimoto, K.R.; Wilson, J.A.; Ashmore, J.P.; Grogan, D.

    1983-12-01

    This report is the fifth in a series of annual reports in Occupational Radiation Exposures in Canada. The data is derived from the Radiation Protection Bureau's National Dose Registry which contains dose records for radiation workers. The report presents average yearly doses by region and occupational category, dose distributions, and variation of average doses with time. Statistical data concerning investigations of high exposures reported by the National Dosimetry Services are included, and individual cases are briefly summarized where the maximum permissible dose is exceeded

  6. Occupational radiation exposures in Canada - 1980

    International Nuclear Information System (INIS)

    Ashmore, J.P.; Fujimoto, K.R.; Wilson, J.A.; Grogan, D.

    1981-08-01

    This report is the third in a series of annual reports on Occupational Radiation Exposures in Canada. The data is derived from the Radiation Protection Bureau's National Dose Registry which includes dose records for radiation workers. The report presents average yearly doses by region and occupational category, dose distributions, and variation of average doses with time. Statistical data concerning investigations of high exposures reported by the National Dosimetry Services are included and individual cases are briefly summarized where the maximum permissible dose is exceeded. The decrease in the overall average doses established over the last 20 years appears to be changing. In some occupational categories a consistent upward trend is observed

  7. Radiation exposures for DOE and DOE contractor employees, 1987

    International Nuclear Information System (INIS)

    1989-10-01

    This report is one of series of annual reports provided by the US Department of Energy (DOE) summarizing occupational radiation exposures received by DOE and DOE contractor employees. These reports provide an overview of radiation exposures received each year, as well as identification of trends in exposures being experienced over the years. 5 figs., 30 tabs

  8. Radiation exposure of nursing personnel to brachytherapy patients

    International Nuclear Information System (INIS)

    Cobb, P.D.; Kase, K.R.; Bjaerngard, B.E.

    1978-01-01

    The radiation exposure of nursing personnel to brachytherapy patients has been analyzed from data collected during the years 1973-1976, at four different hospitals. The average annual dose per exposed nurse ranged between 25 and 150 mrem. The radiation exposure per nurse was found to be proportional to the total potential exposure and was uncorrelated with the size of the nursing staff. (author)

  9. Staff radiation exposure in radiation diagnostics

    International Nuclear Information System (INIS)

    Khakimova, N.U.; Malisheva, E.Yu.; Shosafarova, Sh.G.

    2010-01-01

    Present article is devoted to staff radiation exposure in radiation diagnostics. Data on staff radiation exposure obtained during 2005-2008 years was analyzed. It was found that average individual doses of staff of various occupations in Dushanbe city for 2008 year are at 0.29-2.16 mSv range. They are higher than the average health indicators but lower than maximum permissible dose. It was defined that paramedical personnel receives the highest doses among the various categories of staff.

  10. Pregnancy and radiation exposure

    International Nuclear Information System (INIS)

    Trott, K.H.; Gesellschaft fuer Strahlen- und Umweltforschung m.b.H., Neuherberg

    1978-01-01

    In confirmed or presumptive pregnancy it is especially critical to determine the indications for X-ray examination. This assumes that every young woman, before an examination in the pelvic region, be asked explicity when her last normal period was. Examinations of the pelvis which are not acutely necessary should be postponed until the first 10 days after menstruation. If radiologic examination of the true pelvis must be carried out despite pregnancy or is inadvertently done because pregnancy was not recognized, the radiation exposure of the embryo is so small in most cases because of modern dose-sparing equipment, that an interruption of pregnancy is not justified. A dose of less than 1 rad is, as a rule, justifiable, but it is less justifiable that alarmed, uninformed physicians instill a deep-seated fear of giving brith to a freak in a woman through false information. (orig.) [de

  11. Environmental radiation and exposure to radiation

    International Nuclear Information System (INIS)

    1981-02-01

    Compared to 1977 the exposure to radiation of the population of the Federal Republic of Germany from both natural and artificial radiation sources has not greatly charged. The amin part of exposure to natural radiation is caused by environmental radiation and by the absorption of naturally radioactive substances into the body. Artificial exposure to radiation of the population is essentially caused by the use of ionizing rays and radioactive substances in medicine. When radioactive materials are released from nuclear facilities the exposure to radiation of the population is only very slightly increased. The real exposure to radiation of individual people can even in the worst affected places, have been at most fractions of a millirem. The exposure to radiation in the worst afected places in the area of a hard-coal power station is higher than that coming from a nuclear power station of the same capacity. The summation of all contributions to the exposure of radiation by nuclear facilities to the population led in 1978 in the Federal Republic of Germany to a genetically significant dose of clearly less than 1 millerem per year. The medium-ranged exposure to radiation by external radiation effects through professional work was in 1978 at 80 millirems. No difference to 1977. The contribution of radionuclide from the fallout coming from nuclear-weapon tests and which has been deposited in the soil, to the whole-body dose for 1978 applies the same as the genetically significant dose of the population with less than 1 millirem. (orig./HP) [de

  12. Annual radiation dose in thermoluminescence dating

    International Nuclear Information System (INIS)

    Li Huhou

    1988-01-01

    The annual radiation dose in thermoluminescence dating has been discussed. The autor gives an entirely new concept of the enviromental radiation in the thermoluminescence dating. Methods of annual dose detemination used by author are dating. Methods of annual dose determination used by author are summed up, and the results of different methods are compared. The emanium escapiug of three radioactive decay serieses in nature has been considered, and several determination methods are described. The contribution of cosmic rays for the annual radiation dose has been mentioned

  13. Annual radiation dose in thermoluminescence dating

    Energy Technology Data Exchange (ETDEWEB)

    Huhou, Li [Chinese Academy of Social Sciences, Beijing, BJ (China). Inst. of Archaeology

    1988-11-01

    The annual radiation dose in thermoluminescence dating has been discussed. The autor gives an entirely new concept of the enviromental radiation in the thermoluminescence dating. Methods of annual dose detemination used by author are dating. Methods of annual dose determination used by author are summed up, and the results of different methods are compared. The emanium escapiug of three radioactive decay serieses in nature has been considered, and several determination methods are described. The contribution of cosmic rays for the annual radiation dose has been mentioned.

  14. Occupational radiation exposures in canada-1983

    International Nuclear Information System (INIS)

    Fujimoto, K.; Wilson, J.A.; Ashmore, J.P.; Grogan, D.

    1984-08-01

    This is the sixth in a series of annual reports on Occupational Radiation Exposures in Canada. The information is derived from the National Dose Registry of the Radiation Protection Bureau, Department of National Health and Welfare. As in the past this report presents by occupation: average yearly whole body doses by region, dose distributions, and variations of the average doses with time. The format has been changed to provide more detailed information regarding the various occupations. Statistical data concerning investigations of high exposures reported by the National Dosimetry Services are tabulated in summary form

  15. CSU-FDA (Colorado State Univ.-Food and Drug Administration) Collaborative Radiological Health Laboratory. Annual report - 1982: health effects of prenatal and postnatal whole-body exposure to ionizing radiation in the beagle dog

    International Nuclear Information System (INIS)

    Benjamin, S.A.

    1984-09-01

    The Collaborative Radiological Health Laboratory was established in 1962 by the U.S. Public Health Service and Colorado State University for the purpose of determining in a carefully controlled animal experiment the life-time hazards associated with prenatal and early postnatal exposure to ionizing radiation. The CRHL study is designed to provide information that will facilitate the evaluation of risks to human beings from medical exposure during early development. The study is a long-term (lifespan) study of a moderately large and long-lived mammal exposed at one of several times during development to a relatively small and discrete dose of external radiation. Ages at irradiation selected for comparison reflect the primary concern with medical exposures during the development period. This annual report summarizes the current status of the study for the reporting period of January 1 through December 31, 1982

  16. Ambient radioactivity levels and radiation doses. Annual report 2014; Umweltradioaktivitaet und Strahlenbelastung. Jahresbericht 2014

    Energy Technology Data Exchange (ETDEWEB)

    Trugenberger-Schnabel, Angela; Loebke-Reinl, Angelika; Peter, Josef (comps.) [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    2016-08-15

    The annual report 2014 on ambient radioactivity levels and radiation doses covers the following topics: (1) Actual data and their evaluation: natural environmental radioactivity, artificial environmental radioactivity, occupational radiation exposure, radiation exposures from medical applications, handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. (2) Fundamentals and general information: legal basis and explanations, basic information on natural environmental radioactivity, basic information on artificial radioactivity in the environment, basic information on occupational radiation exposure, basic information on radiation exposures from medical applications, basic information on the handling of radioactive materials and sources of ionizing radiation, basic information on non-ionizing radiation. (3) Tables.

  17. Compliation of summary statistics for radiation worker exposure for the 200 Areas: 1978--1993

    International Nuclear Information System (INIS)

    Brown, R.C.

    1994-01-01

    This document provides estimates of average annual radiation worker exposures for the 200 Areas of the Hanford Site for various facilities. The period of exposures extends from calendar year 1978 through 1993. These estimates were extracted from annual dosimetry reports

  18. Environmental radioactivity and radiation exposure

    International Nuclear Information System (INIS)

    1980-01-01

    In 1977 population exposure in the Federal Republic of Germany has not changed as compared to the previous years. The main share of the total exposure, nearly two thirds, is attributed to natural radioactive substances and cosmic radiation. The largest part (around 85%) of the artificial radiation exposure is caused by X-ray diagnostics. In comparison to this, radiation exposure from application of ionizing radiation in medical therapy, use of radioactive material in research and technology, or from nuclear facilities is small. As in the years before, population exposure caused by nuclear power plants and other nuclear facilities is distinctly less than 1% of the natural radiation exposure. This is also true for the average radiation exposure within a radius of 3 km around nuclear facilities. On the whole, the report makes clear that the total amount of artificial population exposure will substantially decrease only if one succeeds in reducing the high contribution to the radiation exposure caused by medical measures. (orig.) [de

  19. The sources of radiation exposure

    International Nuclear Information System (INIS)

    Bennett, B.G.

    1992-01-01

    Radiation protection of workers and of members of the public requires an assessment of the various sources of exposure, their variations in time or under specific conditions or circumstances, and the possibilities for control or limitation. The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has evaluated the various components of natural and man-made sources in some detail. Natural exposures form the largest component of radiation exposure of man. Variability in exposures depends on elevation, the concentrations of radionuclides in soil, food and water, the composition of building materials and the susceptibility of indoor spaces to radon build-up. Man-made sources have included exposures to fallout from atmospheric nuclear testing and discharged from nuclear fuel cycle installations in routine operations or in accidents. The other main source of radiation exposures of individuals is in medical diagnostic examinations and therapeutic treatments. (author)

  20. Radiation Protection Group Annual Report 2003

    CERN Document Server

    Silari, M

    2004-01-01

    The RP Annual Report summarises the activities carried out by CERN’s Radiation Protection Group in the year 2003. It includes contribution from the EN section of the TIS/IE Group on environmental monitoring. Chapter 1 reports on the measurements and estimations of the impact on the environment and public exposure due to the Organisation’s activities. Chapter 2 provides the results of the monitoring of CERN’s staff, users and contractors to occupational exposure. Chapter 3 deals with operational radiation protection around the accelerators and in the experimental areas. Chapter 4 reports on RP design studies for the LHC and CNGS projects. Chapter 5 addresses the various services provided by the RP Group to other Groups and Divisions at CERN, which include managing radioactive waste, high-level dosimetry, lending radioactive test sources and shipping radioactive materials. Chapter 6 describes activities other than the routine and service tasks, i.e. development work in the field of instrumentation and res...

  1. Occupational exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Snihs, J.O.

    1985-01-01

    An overview of occupational exposure is presented. Concepts and quantities used for radiation protection are explained as well as the ICRP system of dose limitation. The risks correlated to the limits are discussed. However, the actual exposure are often much lower than the limits and the average risk in radiation work is comparable with the average risk in other safe occupations. Actual exposures in various occupations are presented and discussed. (author)

  2. Calculating radiation exposure and dose

    International Nuclear Information System (INIS)

    Hondros, J.

    1987-01-01

    This paper discusses the methods and procedures used to calculate the radiation exposures and radiation doses to designated employees of the Olympic Dam Project. Each of the three major exposure pathways are examined. These are: gamma irradiation, radon daughter inhalation and radioactive dust inhalation. A further section presents ICRP methodology for combining individual pathway exposures to give a total dose figure. Computer programs used for calculations and data storage are also presented briefly

  3. Worldwide exposures to ionizing radiation

    International Nuclear Information System (INIS)

    Bennett, B.G.

    1993-01-01

    All of mankind is exposed to ionizing radiation from natural sources, from human practices that release natural and artificial radionuclides to the environment, and from medical radiation procedures. This paper reviews the assessment in the UNSCEAR 1993 Report of the exposures of human populations worldwide to the various sources of ionizing radiation

  4. Annual report of Radiation Effects Research Foundation

    International Nuclear Information System (INIS)

    1980-01-01

    The Radiation Effects Research Foundation was established in April, 1975, as a private nonprofit Japanese Foundation supported equally by the Government of Japan through the Ministry of Health and Welfare, and the Government of the United States through the National Academy of Sciences under contract with the Energy Research and Development Administration. First, the messages from the chairman and the vice-chairman are described. In the annual report, the review of ABCC-RERF studies of atomic bomb survivors, the summary of research activities, the research projects, the technical report abstracts, the research papers published in Japanese and foreign journals, and the oral presentation and lectures, all from April 1, 1978, to March 31, 1979, are reported. Also the report from the Secretariat and the appendixes are given. The surveys and researches carried out in Hiroshima and Nagasaki have offered very valuable informations to the atomic bomb survivors. Many fears were eliminated, medical interests were given to the serious effects of the exposure to atomic bombs, and many things concerning the cancer induced by radiation were elucidated. The knowledges obtained will save many human lives in future by utilizing them for setting up the health and safety standard in the case of handling ionizing radiation. The progress in researches such as life span study, adult health study, pathology study, genetics program, special cancer program and so on is reported. (Kako, I.)

  5. Effects after prenatal radiation exposures

    International Nuclear Information System (INIS)

    Streffer, C.

    2001-01-01

    The mammalian organism is highly radiosensitive during all prenatal developmental periods. For most effects a dose relationship with a threshold is observed. These threshold doses are generally above the exposures from medical diagnostic procedures. The quality and extent of radiation effects are very much dependent on the developmental stage during which an exposure takes place and on the radiation dose. An exposure during the preimplantation period will cause lethality. Malformations are usually induced after exposures during the major organogenesis. Growth retardation is also possible during the late organogenesis and foetal periods. The lower limits of threshold doses for these effects are in the range of 100 mGy. A radiation exposure during the early foetal period can lead to severe mental retardation and impairment of intelligence. There are very serious effects with radiation doses above 0.3 Gy. Carcinogenesis can apparently occur after radiation exposures during the total prenatal development period. The radiation risk factor up to now has not been clear, but it seems that it is in the range of risk factors for cancer that are observed after exposures during childhood. For radiation doses that are used in radiological diagnostics the risk is zero or very low. A termination of pregnancy after doses below 100 mGy should not be considered. (author)

  6. Radiation exposure and risk estimates for inhaled airborne radioactive pollutants including hot particles. Annual report 1 July 1976--30 June 1977

    International Nuclear Information System (INIS)

    Mewhinney, J.A.

    1978-03-01

    Contents: Mixed-oxide fuel fabrication; Generation of aerosols of mixed uranium-plutonium oxides from dry powders for animal inhalation exposures; Analytical radiochemical determination of U, Pu and Am in biological samples; Physical chemical characterization of mixed uranium-plutonium oxide nuclear fuel as samples during animal inhalation exposure; Pilot studies of deposition and retention of industrial mixed-oxide aerosols in the laboratory rat; Extended radiation dose pattern studies of aerosols of mixed uranium-plutonium oxides treated at 750C inhaled by Fishcer-344 rats, beagle dogs and cynomolgus monkeys; Extended radiation dose pattern studies of aerosols of plutonium dioxide, treated at 850C and inhaled by Fischer-344 rats, beagle dogs and cynomolgus monkeys

  7. Evaluation of environmental radiation exposure

    International Nuclear Information System (INIS)

    Imai, Kazuhiko

    1974-01-01

    The environmental radiation exposure due to radioactive rare gases is most important both at the time of reactor accidents and also in the long-term normal operation of reactor plants. The exposure dose is usually calculated by means of computers. The procedure of the calculation on environmental exposure dose is divided in several consecutive steps. The calculational formulae frequently used and those proposed recently are given with the explanation on released radionuclides, release to the atmosphere, concentration in the atmosphere, β-ray exposure, γ-ray exposure, and calculation of long-term exposure dose. (Mori, K.)

  8. Radiation exposure reduction in APR1400

    International Nuclear Information System (INIS)

    Bae, C. J.; Hwang, H. R.; Matteson, D. M.

    2002-01-01

    The primary contributors to the total occupational radiation exposure in operating nuclear power plants are operation and maintenance activities during refueling outages. The Advanced Power Reactor 1400 (APR1400) includes a number of design improvements and plans to utilize advanced maintenance methods and robotics to minimize the annual collective dose. The major radiation exposure reduction features implemented in APR1400 are a permanent refueling pool seal, quick opening transfer tube blind flange, improved hydrogen peroxide injection at shutdown, improved permanent steam generator work platforms, and more effective temporary shielding. The estimated average annual occupational radiation exposure for APR1400 based on the reference plant experience and an engineering judgment is determined to be in the order of 0.4 man-Sv, which is well within the design goal of 1 man-Sv. The basis of this average annual occupational radiation exposure estimation is an eighteen (18) month fuel cycle with maintenance performed to steam generators and reactor coolant pumps during refueling outage. The outage duration is assumed to be 28 days. The outage work is to be performed on a 24 hour per day basis, seven (7) days a week with overlapping twelve (12) hour work shifts. The occupational radiation exposure for APR1400 is also determined by an alternate method which consists of estimating radiation exposures expected for the major activities during the refueling outage. The major outage activities that cause the majority of the total radiation exposure during refueling outage such as fuel handling, reactor coolant pump maintenance, steam generator inspection and maintenance, reactor vessel head area maintenance, decontamination, and ICI and instrumentation maintenance activities are evaluated at a task level. The calculated value using this method is in close agreement with the value of 0.4 man-Sv, that has been determined based on the experience and engineering judgement

  9. Control of external radiation exposure

    International Nuclear Information System (INIS)

    Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

    2004-01-01

    The following subjects are discussed - Control of external radiation exposure: working time, working distance, shielding: Total Linear Attenuation Coefficient, Half-Value Layer (HVL), Tenth-Value Layer (TVL); Build-up Factor

  10. Occupational external radiation exposure in the GDR in 1976

    International Nuclear Information System (INIS)

    Rothe, W.

    1980-01-01

    In 1976 a total of 36,794 occupationally exposed persons were monitored by the National Board of Nuclear Safety and Radiation Protection, using film badges. The monthly over-exposures (more than 4 mGy) totalled 415. In 11 cases the monthly exposure exceeded 30 mGy and 6 annual exposure values were in the range of 50 to 120 mGy. An attempt has been made to assess the annual collective and annual per caput doses for the exposed population as a whole and some subgroups without completely summing up the individual exposure data. (author)

  11. Intentional exposure to ultraviolet radiation

    International Nuclear Information System (INIS)

    Kivisakk, E.

    1987-01-01

    Exposure to UV radiation can cause a number of detrimental effects to human health. Some of these are particularly grave, as for instance the induction of skin cancer. Nevertheless, intentional exposure to UV radiation is commonly practiced for many purposes, ranging from medical treatment to merely a simple form of pastime. From the radiation point of view, the risks associated with exposure to UV radiation in any particular application should be carefully considered, and only accepted if they are obviously compensated by the benefits of the irradiation. This is not always the case today, to some extent due to shortage of information about the effect of UV radiation - especially on a long term basis

  12. Radiation exposure and infant cancer

    Energy Technology Data Exchange (ETDEWEB)

    Watari, T [Tokyo Univ. (Japan). Faculty of Medicine

    1974-12-01

    Medical exposures accompanied by an increase in radiation use in the field of pediatrics were described. Basic ideas and countermeasures to radiation injuries were outlined. In order to decrease the medical exposure, it is necessary for the doctor, x-ray technician and manufacturer to work together. The mechanism and characteristics of radio carcinogenesis were also mentioned. Particularly, the following two points were described: 1) How many years does it take before carcinogenesis appears as a result of radiation exposure in infancy 2) How and when does the effect of fetus exposure appear. Radiosensitivity in infants and fetuses is greater than that of an adult. The occurrence of leukemia caused by prenatal exposure was reviewed. The relation between irradiation for therapy and morbidity of thyroid cancer was mentioned. Finally, precautions necessary for infants, pregnant women and nursing mothers when using radioisotopes were mentioned.

  13. Occupational radiation exposures in Canada, 1981

    International Nuclear Information System (INIS)

    Fujimoto, K.R.; Wilson, J.A.; Ashmore, J.P.; Grogan, D.

    1983-12-01

    This report is the fourth in a series of annual reports on Occupational Radiation Exposures in Canada. The data is derived from the Radiation Protection Bureau's National Dose Registry which includes those records for radiation workers. The report presents average yearly doses by region and occupational category, dose distributions, and variation of average doses with time. Statistical data concerning investigations of high exposures reported by the National Dosimetry Services are included and individual cases are briefly summarized where the maximum permissible dose is exceeded. The decrease in the overall average doses established over the last 20 years appears to have resumed after an interruption during 1979 to 1980. A brief summary of extremity dose data is also included

  14. Occupational radiation exposures in Canada - 1979

    International Nuclear Information System (INIS)

    Ashmore, J.P.; Fujimoto, K.R.; Wilson, J.A.; Grogan, D.

    1980-12-01

    This report is the second in a series of annual reports on Occupational Radiation Exposures in Canada. The data is derived from the Radiation Protection Bureau's National Dose Registry which includes dose records for radiation workers in Canada. The report presents average yearly doses by region and occupational category, dose distributions, and variation of average doses with time. Statistical data concerning investigations of high exposures are included and individual cases are briefly summarized where the maximum permissible dose is exceeded. The 1979 data indicate that the gradually decreasing trend of the last two decades may be changing. In a number of areas the overall average doses and the averages for some job categories have increased over the corresponding values for 1977 and 1978

  15. DOE occupational radiation exposure 2000 report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2000-12-31

    The U.S. Department of Energy (DOE) Office of Safety and Health publishes the annual DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for DOE and DOE contractor managers in managing radiological safety programs and to assist them in prioritizing resources. We appreciate the efforts and contributions from the various stakeholders within and outside DOE in making this report most useful to them. This report includes occupational radiation exposure information for all monitored DOE employees, contractors, subcontractors, and visitors. The exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included in the analysis.

  16. DOE occupational radiation exposure 2003 report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2003-12-31

    The U.S. Department of Energy (DOE) Office of Corporate Performance Assessment (EH-3) publishes the annual DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for DOE and DOE contractor managers and workers in managing radiological safety programs and to assist them in prioritizing resources. We appreciate the efforts and contributions from the various stakeholders within and outside DOE to make the report most useful. This report includes occupational radiation exposure information for all monitored DOE employees, contractors, subcontractors, and members of the public. DOE is defined to include the National Nuclear Security Administration sites. The exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included in the analysis.

  17. DOE occupational radiation exposure 2004 report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2004-12-31

    The U.S. Department of Energy (DOE) Office of Corporate Performance Assessment (EH-3) publishes the annual DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for DOE and DOE contractor managers and workers in managing radiological safety programs and to assist them in prioritizing resources. We appreciate the efforts and contributions from the various stakeholders within and outside DOE to make the report most useful. This report includes occupational radiation exposure information for all monitored DOE employees, contractors, and subcontractors, as well as members of the public. DOE is defined to include the National Nuclear Security Administration sites. The exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included in the analysis.

  18. Assessment of annual exposure for grout operations

    International Nuclear Information System (INIS)

    Potter, R.E.

    1994-01-01

    An analysis is presented of the direct radiation exposures and dose rates to personnel from assumed quantities of radioactive grout, and Double Shell Tank (DST) waste feed. This analysis was based on filling four disposal vaults per year. Whole body doses were analyzed for occupational workers assigned to the Grout Treatment Facility (GTF). The study makes assumptions that must be met by the facility. Otherwise, the GTF will meet all DOE and WHC direct radiation exposure criteria. This analysis will be published in the Grout Final Safety Analysis Report (FSAR)

  19. Maintenance hemodialysis patients have high cumulative radiation exposure.

    LENUS (Irish Health Repository)

    Kinsella, Sinead M

    2010-10-01

    Hemodialysis is associated with an increased risk of neoplasms which may result, at least in part, from exposure to ionizing radiation associated with frequent radiographic procedures. In order to estimate the average radiation exposure of those on hemodialysis, we conducted a retrospective study of 100 patients in a university-based dialysis unit followed for a median of 3.4 years. The number and type of radiological procedures were obtained from a central radiology database, and the cumulative effective radiation dose was calculated using standardized, procedure-specific radiation levels. The median annual radiation dose was 6.9 millisieverts (mSv) per patient-year. However, 14 patients had an annual cumulative effective radiation dose over 20 mSv, the upper averaged annual limit for occupational exposure. The median total cumulative effective radiation dose per patient over the study period was 21.7 mSv, in which 13 patients had a total cumulative effective radiation dose over 75 mSv, a value reported to be associated with a 7% increased risk of cancer-related mortality. Two-thirds of the total cumulative effective radiation dose was due to CT scanning. The average radiation exposure was significantly associated with the cause of end-stage renal disease, history of ischemic heart disease, transplant waitlist status, number of in-patient hospital days over follow-up, and death during the study period. These results highlight the substantial exposure to ionizing radiation in hemodialysis patients.

  20. Repeated exposure to enhanced UV-B radiation in successive generations increases developmental instability (leaf fluctuating asymmetry) in a desert annual

    International Nuclear Information System (INIS)

    Midgley, G.F.; Wand, S.J.E.; Musil, C.F.

    1998-01-01

    Populations of the desert annual Dimorphotheca sinuata, derived from a common seed stock, were exposed concurrently over four successive generations to either ambient (representing no stratospheric ozone depletion) or elevated (representing 20% stratospheric ozone depletion) UV-B levels during their complete life cycle. Leaf fluctuating asymmetry (FA) was measured in populations of plants grown from seeds of selected generations which had experienced different UV-B exposure histories, and from seeds collected from a wild population of this species which grows in a naturally enhanced UV-B environment. These measured plants had been grown in a greenhouse under essentially UV-B-free conditions. Leaf FA was significantly increased by greater numbers of enhanced UV-B exposures in the parentage of the seed. There was a linear to exponential dose–response relationship between number of UV-B exposure iterations in seed parentage and leaf FA, suggesting that damage to DNA caused by UV-B exposure during plant development may not be fully repaired, and thus be inherited by offspring and accumulated over successive generations in this species. Leaf FA of plants grown from seed from the wild population was not significantly greater than that of control plants whose parentage experienced only ambient UV-B exposures, although this negative result may have been due to low sampling intensity and measurement resolution, and the relatively low UV-B enhancement experienced by the wild population. We conclude that leaf FA may constitute a relatively sensitive yet inexpensive means of quantifying UV-B damage to plants. (author)

  1. Malignant mesothelioma following radiation exposure

    International Nuclear Information System (INIS)

    Antman, K.H.; Corson, J.M.; Li, F.P.; Greenberger, J.; Sytkowski, A.; Henson, D.E.; Weinstein, L.

    1983-01-01

    Mesothelioma developed in proximity to the field of therapeutic radiation administered 10-31 years previously in four patients. In three, mesothelioma arose within the site of prior therapeutic radiation for another cancer. Mesothelioma in the fourth patient developed adjacent to the site of cosmetic radiation to a thyroidectomy scar. None of these four patients recalled an asbestos exposure or had evidence of asbestosis on chest roentgenogram. Lung tissue in one patient was negative for ferruginous bodies, a finding considered to indicate no significant asbestos exposure. Five other patients with radiation-associated mesothelioma have been reported previously, suggesting that radiation is an uncommon cause of human mesothelioma. Problems in the diagnosis of radiation-associated mesotheliomas are considered

  2. Radiation Exposure from Medical Exams and Procedures

    Science.gov (United States)

    Fact Sheet Adopted: January 2010 Health Physics Society Specialists in Radiation Safety Radiation Exposure from Medical Exams and Procedures Ionizing radiation is used daily in hospitals and clinics ...

  3. Radiation Exposure - Multiple Languages

    Science.gov (United States)

    ... Rays) - 繁體中文 (Chinese, Traditional (Cantonese dialect)) PDF California Dental Association Nuclear or Radiation Emergencies - 繁體中文 (Chinese, Traditional (Cantonese dialect)) Bilingual PDF ...

  4. Radiation protection: occupational exposure

    International Nuclear Information System (INIS)

    Shah, G.A.

    1990-01-01

    The basis of the occupational exposure limit of 50 mSv recommended by the ICRP is questioned. New dosimetry at Hiroshima and Nagasaki, the fact that the dose-response curve may be non-linear and that the relative risk model may be applicable, are some of the arguments advanced to support a reduction in the occupational exposure dose limits. 5 refs., 2 tabs., 3 figs

  5. Radiation Protection Group annual report (1997)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1998-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1997. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  6. Radiation Protection Group annual report (1996)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1997-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1996. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  7. Radiation Protection Group annual report (1998)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1999-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1998. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  8. Radiation Protection Group annual report (1996)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1997-03-25

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1996. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  9. Radiation Protection Group annual report (1998)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1999-04-15

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1998. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  10. Radiation Protection Group annual report (1997)

    Energy Technology Data Exchange (ETDEWEB)

    Hoefert, M [ed.

    1998-04-10

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1997. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group.

  11. Radiation Protection Group annual report (1995)

    International Nuclear Information System (INIS)

    Hoefert, M.

    1996-01-01

    The Annual Report of the Radiation Protection Group is intended to inform the Host State Authorities, as well as the CERN Management and staff, about the radiological situation at CERN during the year 1995. The structure of the present report follows that of previous years and has five sections. It presents the results of environmental radiation monitoring, gives information about the radiation control on the sites of the Organization, describes the radiation protection activities around the CERN accelerators, reports on personnel dosimetry, calibration and instrumentation, and briefly comments on the non-routine activities of the Radiation Protection Group

  12. Sarcoma risk after radiation exposure

    Directory of Open Access Journals (Sweden)

    Berrington de Gonzalez Amy

    2012-10-01

    Full Text Available Abstract Sarcomas were one of the first solid cancers to be linked to ionizing radiation exposure. We reviewed the current evidence on this relationship, focusing particularly on the studies that had individual estimates of radiation doses. There is clear evidence of an increased risk of both bone and soft tissue sarcomas after high-dose fractionated radiation exposure (10 + Gy in childhood, and the risk increases approximately linearly in dose, at least up to 40 Gy. There are few studies available of sarcoma after radiotherapy in adulthood for cancer, but data from cancer registries and studies of treatment for benign conditions confirm that the risk of sarcoma is also increased in this age-group after fractionated high-dose exposure. New findings from the long-term follow-up of the Japanese atomic bomb survivors suggest, for the first time, that sarcomas can be induced by acute lower-doses of radiation (

  13. Radiation Exposure of Passengers to Cosmic Radiation

    International Nuclear Information System (INIS)

    Salah El-Din, T.; Gomaa, M.A.; Sallah, N.

    2010-01-01

    The main aim of the present study is to review exposure of Egyptian passengers and occupational workers to cosmic radiation during their work. Computed effective dose of passengers by computer code CARI-6 using during either short route, medium route or long route as well as recommended allowed number of flights per year

  14. Environmental radioactivity and radiation exposure

    International Nuclear Information System (INIS)

    1976-01-01

    The environmental radioactivity in the Federal Republic of Germany was almost as high in 1976 as in 1975. It only increased temporarily in autumn 1976 as a result of the above-ground nuclear weapons test of the People's Republic of China on September 29th 1976 and then returned to its previous level. The radioactivity in food had a slight decreasing trend in 1976, apart from a temporary increase in the radioactivity in milk also caused by the nuclear weapons test mentioned. The population exposure remains basically unchanged in 1976 compared with 1975. The artificial radiation exposure is about half as high as the natural radiation exposure to which man has always been exposed. The former is based to 83% on using X-rays in medicine, particularly for X-ray diagnostic purposes. The population exposure due to nuclear power plants and other nuclear plants is still well below 1% of the natural radiation exposure although in 1976 three new nuclear power plants were put into operation. This is also true for the average radiation exposure within an area of 3 km around the nuclear plant. (orig.) [de

  15. National registry of workers occupational exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Cunha, P.G. da; Mota, H.C.; Alegre, S.

    1995-01-01

    The Brazilian Nuclear Energy Commission started in 1987 a nationwide program in order to collect and maintain the radiation exposure records of the Brazilian workers. This data base consists of several files including: workers - personal data; institutions - section or department where the workers perform their activities; and annual doses - annual integrated doses and any relevant information regarding their exposures. The data base structure is introduced in the present work where its objectives are discussed taking into account the magnitude of the program as well as the difficulties of maintaining and the long term perspectives of a nationwide register of radiation occupational exposures. (author). 15 refs., 1 fig

  16. Occupational radiation exposure in Korea: 2002

    International Nuclear Information System (INIS)

    Jeong, Je Ho; Kwon, Jeong Wan; Lee, Jai Ki

    2005-01-01

    Dose distribution of Korean radiation workers classified by occupational categories was analyzed. Statistics of the Occupational Radiation Exposure(ORE) in 2002 of the radiation workers in diagnostic and dental radiology were obtained from the Korea Food and Drug Agency(KFDA) who maintains the database for individual radiation dose records. Corresponding statistics for the rest of radiation workers were obtained by processing the individual annual doses provided by the Korea RadioIsotope Association(KRIA) after deletion of individual information. The ORE distribution was classified in term of 28 occupational categories, annual individual dose levels, age groups and gender of 52733 radiation workers as of the year of 2002. The total collective dose was 66.4 man-Sv and resulting average individual ORE was 1.26 mSv. Around 80% of the workers were exposed to minimal doses less than 1.2 mSv. However, it appeared that the recorded doses exceeded 20 mSv for 43 workers in the industrial radiography and for 147 workers in the field of radiology. Particularly, recorded doses of 23 workers in radiology exceeded the annual dose limits of 50 mSv, which is extraordinary when the working environment is considered. It is uncertain whether those doses are real or caused by careless placing of dosimeters in the imaging rooms while the X-ray units are in operation. No one in the workforce of 16 operating nuclear power plant units was exposed over 20 mSv in 2002. Number of workers was the largest in their 30's of age and the mean individual dose was the highest in their 20's. Women were around 20% of the radiation workers and their average dose was around one half of that of man workers

  17. Radiation exposure in manned spaceflight

    Energy Technology Data Exchange (ETDEWEB)

    Buecker, H. (Deutsche Forschungsanstalt fuer Luft- und Raumfahrt e.V., Koeln (Germany)); Horneck, G. (Deutsche Forschungsanstalt fuer Luft- und Raumfahrt e.V., Koeln (Germany)); Facius, R. (Deutsche Forschungsanstalt fuer Luft- und Raumfahrt e.V., Koeln (Germany)); Reitz, G. (Deutsche Forschungsanstalt fuer Luft- und Raumfahrt e.V., Koeln (Germany))

    1993-08-01

    Space missions exposure humans to a radiation environment of a particulate composition and intensity not encountered within our biosphere. The natural radiation environment encountered in Earth orbit is a complex mixture of charged particles of galactic and solar origin and of those trapped by the geomagnetic field. In addition, secondaries are produced by interaction of cosmic ray primaries with the spacecraft shielding material. Among this large variety of radiation components in space, it is likely that the heavy ions are the significant species as far as radiobiological effects are concerned. In addition, a synergistic interaction of microgravity and radiation on living systems has been reported in some instances. Based on an admissible risk of 3% mortality due to cancers induced during a working career, radiation protection guidelines have been developed for this radiation environment. (orig.)

  18. Radiation exposure of the crew in commercial air traffic

    International Nuclear Information System (INIS)

    Antic, D.; Markovic, P.; Petrovic, Z.

    1993-01-01

    The routine radiation exposure of the crews in Yugoslav Airlines (JAT) has been studied and some previous results are presented. The flights of four selected groups of pilots (four aircraft types) have been studied during one year. Annual exposures and dose equivalents are presented. Some additional results and discussions are given. (1 fig., 4 tabs.)

  19. Psychiatric disorders after radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Kokai, Masahiro [Hyogo Coll. of Medicine, Nishinomiya (Japan); Soejima, Toshinori; Wang, Shangdong; Shinfuku, Naotaka

    2001-04-01

    This review focuses on the mental and psychological effects of medical radiation exposure, the nuclear accident at Three Mile Island, the Chernobyl disaster, atomic bomb explosions at Nagasaki and Hiroshima, and accidents at nuclear power plants and nuclear waste plants. Studies have shown that anxiety about the adverse effects of radiation in medicine (such as infertility, carcinogenicity, and genotoxicity) and fear for exposure has caused psychiatric disorders. Several studies on the mental health effects of the nuclear accident at Three Mile Island were conducted, and the results indicated that psychiatric distress persisted for a certain period of time, particularly in pregnant women and women who have children, even when no evidence of substantial of radiation exposure is seen clinically. The psychological consequences of the Chernobyl disaster have been investigated continuously, and various problems, e.g., acute stress reaction, neurosis, and psychosis, have been identified, although no physical damage due to the radiation or PTSD have been reported. By contrast, PTSD has been seen in survivors of the Nagasaki and Hiroshima nuclear explosions. A study in Ohio, (United States), which has a nuclear waste plant, investigated PTSD in people living near the plant and found that the symptom level was mild. In general, the most common symptoms among people with mental and psychological disorders due to radiation exposure are depression and anxiety, with many people having associated somatoform disorders, and some people complain of PTSD. Vague anxiety and fear of sequelae, regardless of the exposure dose, appears to cause such psychiatric disorders. Although it is rare for psychiatrists to see such cases of psychiatric disorders due to radiation exposure, their number may increase as psychiatric services become more widely available. (K.H.)

  20. Psychiatric disorders after radiation exposure

    International Nuclear Information System (INIS)

    Kokai, Masahiro; Soejima, Toshinori; Wang, Shangdong; Shinfuku, Naotaka

    2001-01-01

    This review focuses on the mental and psychological effects of medical radiation exposure, the nuclear accident at Three Mile Island, the Chernobyl disaster, atomic bomb explosions at Nagasaki and Hiroshima, and accidents at nuclear power plants and nuclear waste plants. Studies have shown that anxiety about the adverse effects of radiation in medicine (such as infertility, carcinogenicity, and genotoxicity) and fear for exposure has caused psychiatric disorders. Several studies on the mental health effects of the nuclear accident at Three Mile Island were conducted, and the results indicated that psychiatric distress persisted for a certain period of time, particularly in pregnant women and women who have children, even when no evidence of substantial of radiation exposure is seen clinically. The psychological consequences of the Chernobyl disaster have been investigated continuously, and various problems, e.g., acute stress reaction, neurosis, and psychosis, have been identified, although no physical damage due to the radiation or PTSD have been reported. By contrast, PTSD has been seen in survivors of the Nagasaki and Hiroshima nuclear explosions. A study in Ohio, (United States), which has a nuclear waste plant, investigated PTSD in people living near the plant and found that the symptom level was mild. In general, the most common symptoms among people with mental and psychological disorders due to radiation exposure are depression and anxiety, with many people having associated somatoform disorders, and some people complain of PTSD. Vague anxiety and fear of sequelae, regardless of the exposure dose, appears to cause such psychiatric disorders. Although it is rare for psychiatrists to see such cases of psychiatric disorders due to radiation exposure, their number may increase as psychiatric services become more widely available. (K.H.)

  1. Human population exposure to cosmic radiation

    International Nuclear Information System (INIS)

    Bouville, A.; Lowder, W.M.

    1988-01-01

    Critical evaluations of existing data on cosmic radiation in the atmosphere and in interplanetary space have been carried out in order to estimate the exposure of the world's population to this important component of natural background radiation. Data on population distribution and mean terrain heights on a 1 x 1 degree grid have been folded in to estimate regional and global dose distributions. The per caput annual dose equivalent at ground altitudes is estimated to be 270 μSv from charged particles and 50 μSv from neutrons. More than 100 million people receive more than 1 mSv in a year, and two million in excess of 5 mSv. Aircraft flight crews and frequent flyers receive an additional annual dose equivalent in the order of 1 mSv, though the global per caput annual dose equivalent from airplane flights is only about 1 μSv. Future space travellers on extended missions are likely to receive dose equivalents in the range 0.11 Sv, with the possibility of higher doses at relatively high dose rates from unusually large solar flares. These results indicate a critical need for a better understanding of the biological significance of chronic neutron and heavy charged particle exposure. (author)

  2. Annual radiation background in Isfahan city

    International Nuclear Information System (INIS)

    Tavakoli, Mohammad B.

    2002-01-01

    Measurement of environmental exposure is very important from different points of view. It is especially important for human health. It has been measured accurately in many countries. In Iran, it is also measured in some cities especially in high background areas such as Ramsar, but there is not any measurement in Isfahan. Measurement of background radiation in this study is performed using TLD method. The TLDs used are made from CaSO 4 :Dy, which is very sensitive. The locations under investigations in this research were 52 health centers distributed all around Isfahan city. Each TLD badge was put in a special plastic bag and left over the roofs of the selected health center for a month. The procedure was repeated for all 12 months of the year 1379(21 st March 2000 to 20 th March 2001). The results were used to obtain mean and SD in each month and at different places. The maximum and the minimum of obtained results for dose equivalent in different months and locations were 15.9x10 -2 and 6.5x10 -2 mSv. Obtained maximum and minimum of the means between all the locations were 10.5x10 -2 and 8.6x10 2 mSv for the whole year. Monthly mean and SD for Isfahan city for the whole year were 9.7x10 -2 and 1.5x10 -2 respectively therefore mean annual dose equivalent in Isfahan city is 1.16mSv. The results do not show any high background radiation area

  3. Occupational radiation exposure in Germany: many monitored persons = high exposure?

    International Nuclear Information System (INIS)

    Nitschke, J.

    1996-01-01

    Natural radiation affects the entire population in Germany, and most of Germany's inhabitants are exposed to medical radiation in their lifetime. Occupational radiation exposure, however, is a kind of exposure affecting only a limited and well-defined group of the population, and this radiation exposure has been recorded and monitored as precisely as technically possible ever since the radiation protection laws made occupational radiation exposure monitoring a mandatory obligation. Official personal dosimetry applying passive dosemeters in fact does not offer direct protection against the effects of ionizing radiation, as dosemeter read-out and dose calculation is a post-exposure process. But it nevertheless is a rewarding monitoring duty under radiation protection law, as is shown by the radiation exposure statistics accumulated over decades: in spite of the number of monitored persons having been increasing over the years, the total exposure did not, due to the corresponding improvements in occupational radiation protection. (orig.) [de

  4. Occupational radiation exposures in Canada - 1978

    International Nuclear Information System (INIS)

    Ashmore, J.P.; Fujimoto, K.R.; Wilson, J.A.; Grogan, D.

    This 1978 report is the first in a series of annual reports on occupational radiation exposures in Canada. The data are derived from the Radiation Protection Bureau's National Dose Registry which includes dose records for radiation workers in Canada. The report presents average yearly doses by region and occupational category, dose distributions, and variation of average doses with time. Statistical data concerning investigations of overexposures are included and individual cases are briefly summarized where the maximum permissible dose is exceeded. The 1978 data indicate that the gradually decreasing trend of the last two decades may have changed. In a number of areas the overall average doses and the averages for some job categories have increasd over the corresponding values for 1977

  5. Radiation exposure of the dentist

    Energy Technology Data Exchange (ETDEWEB)

    Regulla, D F; Wachsmann, F

    1975-08-01

    The radiation doses per person undergoing dental treatment measured at the trunk is rather considerable, though not alarming. However, the number of people whose hands had been exposed to radiation as well as the individual extent of exposure were unexpectedly high. The radiation doses measured at the hands was about 100 times bigger than the radiation doses determined at the trunk for the whole body. Although these results may be very impressive, it should be borne in mind that the data on which the investigation was based date from 1967/68 and may no longer be fully applicable to the present situation. Whether and to what extent this assumption is justified ought to be found out by control studies regarding radiation doses per person and Roepak programs which are presently being started and whose results will be discussed in this journal.

  6. Application of maximum values for radiation exposure and principles for the calculation of radiation doses

    International Nuclear Information System (INIS)

    2007-08-01

    The guide presents the definitions of equivalent dose and effective dose, the principles for calculating these doses, and instructions for applying their maximum values. The limits (Annual Limit on Intake and Derived Air Concentration) derived from dose limits are also presented for the purpose of monitoring exposure to internal radiation. The calculation of radiation doses caused to a patient from medical research and treatment involving exposure to ionizing radiation is beyond the scope of this ST Guide

  7. Biological monitoring of radiation exposure

    Science.gov (United States)

    Horneck, G.

    1998-11-01

    Complementary to physical dosimetry, biological dosimetry systems have been developed and applied which weight the different components of environmental radiation according to their biological efficacy. They generally give a record of the accumulated exposure of individuals with high sensitivity and specificity for the toxic agent under consideration. Basically three different types of biological detecting/monitoring systems are available: (i) intrinsic biological dosimeters that record the individual radiation exposure (humans, plants, animals) in measurable units. For monitoring ionizing radiation exposure, in situ biomarkers for genetic (e.g. chromosomal aberrations in human lymphocytes, germ line minisatellite mutation rates) or metabolic changes in serum, plasma and blood (e.g. serum lipids, lipoproteins, lipid peroxides, melatonin, antibody titer) have been used. (ii) Extrinsic biological dosimeters/indicators that record the accumulated dose in biological model systems. Their application includes long-term monitoring of changes in environmental UV radiation and its biological implications as well as dosimetry of personal UV exposure. (iii) Biological detectors/biosensors for genotoxic substances and agents such as bacterial assays (e.g. Ames test, SOS-type test) that are highly sensitive to genotoxins with high specificity. They may be applicable for different aspects in environmental monitoring including the International Space Station.

  8. Radiation exposure during equine radiography

    International Nuclear Information System (INIS)

    Ackerman, N.; Spencer, C.P.; Hager, D.A.; Poulos, P.W. Jr.

    1988-01-01

    All personnel present in the X-ray examination room during equine radiography were monitored using low energy direct reading ionization chambers (pockets dosimeters) worn outside the lead apron at neck level. The individuals' task and dosimeter readings were recorded after each examination. Average doses ranged from 0 to 6 mrad per study. The greatest exposures were associated with radiography of the shoulder and averaged less than 4 mrad. The individual extending the horse's limb was at greatest risk although the individual holding the horse's halter and the one making the X-ray exposure received similar exposures. A survey of the overhead tube assembly used for some of the X-ray examinations also was performed. Meter readings obtained indicated an asymetric dose distribution around the tube assembly, with the highest dose occurring on the side to which the exposure cord was attached. Although the exposures observed were within acceptable limits for occupational workers, we have altered our protocol and no longer radiograph the equine shoulder unless the horse is anesthetized. Continued use of the pocket dosimeters and maintenance of a case record of radiation exposure appears to make the technologists more aware of radiation hazards

  9. Occupational radiation exposure in the GDR in 1978

    International Nuclear Information System (INIS)

    Poulheim, K.F.; Rothe, W.; Scheler, R.

    1980-01-01

    In 1978, radiation workers were monitored for external and internal radiation exposure on the basis of film badges (37,980 persons), measurements with a whole-body counter (186 persons) and analyses of biosamples (144 persons). According to the film badge data, the monthly over-exposures (more than 4 mGy) totalled 427. In 13 cases the monthly exposure exceeded 30 mGy, 8 persons received annual doses in the range of 50 to 120 mGy, and the highest annual dose was above 250 mGy. Also, annual collective and annual per caput doses have been given for the exposed population as a whole and some subgroups. Based on model considerations, the internal radiation exposure situation resulting from unintentional intakes of radionuclides has been assessed in terms of committed dose equivalents to members of two selected groups of radiation workers: (a) persons with more-than-average internal contamination levels; (b) persons subjected to frequent individual monitoring. Except for some organ doses, the individual internal radiation exposure was well below one-tenth the maximum permissible dose. (author)

  10. Diagnostic and therapeutic radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Russell, W J [Radiation Effects Research Foundation, Hiroshima (Japan)

    1975-09-01

    Diagnostic and therapeutic radiology were studied as possible contaminants in the evaluations of A-bomb survivors in the ABCC-JNIH Adult Health Study for radiation effects. Hiroshima and Nagasaki subjects received X-ray examinations elsewhere within three months of their ABCC visits at rates of 23 and 12%, respectively. Medical X-ray examinations were more frequent among survivors than comparison subjects. Hiroshima and Nagasaki radiologic practice steadily increased since 1948, and differed markedly by city. From 1946-70 the Hiroshima and Nagasaki X-ray bone marrow doses were 2,300 and 1,000 g-rads, respectively. By 1970, cumulated medical X-ray doses approximated A-bomb doses at distances from the hypocenters of 2,000 m in Hiroshima and 2,800 m in Nagasaki. ABCC X-ray examination doses per subject are routinely updated for comparison with A-bomb doses. Each subject's reported fluoroscopy, photofluorography and radiation therapy exposure elsewhere are for future reference. Dental radiography, though increasing, was not currently an important contributor to survivors' overall exposure. Radiation therapy exposures of 137 subjects were confirmed, and doses estimated for most. Two-thirds the treatments were for malignancies; therapy differed markedly by city; and five cancers possibly arose from earlier radiation therapy. This underscores the importance of considering diagnostic and therapeutic radiology when attributing diseases to the atomic bombs.

  11. Estimation of health risks from radiation exposures

    Energy Technology Data Exchange (ETDEWEB)

    Randolph, M.L.

    1983-08-01

    An informal presentation is given of the cancer and genetic risks from exposures to ionizing radiations. The risks from plausible radiation exposures are shown to be comparable to other commonly encountered risks.

  12. Estimation of health risks from radiation exposures

    International Nuclear Information System (INIS)

    Randolph, M.L.

    1983-08-01

    An informal presentation is given of the cancer and genetic risks from exposures to ionizing radiations. The risks from plausible radiation exposures are shown to be comparable to other commonly encountered risks

  13. Radiation exposure by using unsealed radiation sources

    International Nuclear Information System (INIS)

    Preitfellner, J.

    1999-05-01

    Investigations on patients using radioactive substances are performed on a routinely basis in nuclear medicine facilities at many hospitals in our days. These investigations are performed by administering a radiopharmacon to the patient which, depending on several parameters, remains in the body of the patient for various periods of time. All these investigations have in common a g-ray exposure of the environment by the radioactive substance in the body of the patient. Among others, doctors, technical personnel, cleaning personnel, and accompanying persons of patients are exposed to g-rays. Based on these facts, the degree of danger for persons who get into contact with these patients is repeatedly questioned. An additional problem is the health risk of persons employed at a nuclear medicine facility. To answer the first question, the local dose rate in the environment of 102 patients was evaluated immediately after application of the radioactive substance, in intervals from 30 minutes up to several hours, over a period of up to 2 weeks. Depending on the nature of the investigation, the patients were subdivided into 6 groups of 16-20 persons. From the data measured, the effective and the biological half life as well as the local dose were computed. With the aid of concrete case examples, the possible radiation exposure for contact persons was estimated. Postulating unfavorable local and temporal factors in our estimations, the actual radiation exposure is to be estimated about 10-30 % lower. As a reference value for the danger of persons, the maximum permissible boundary values from the Austrian Regulations for Protection against Radiation were used. Referring to these boundary values, for none of the six nuclear medicine investigation methods a danger for contact persons could be derived, indicating that available security measures offer a sufficient protection for affected contact persons. To answer the question about the risk for persons employed at a nuclear

  14. European studies on occupational radiation exposure - ESOREX

    International Nuclear Information System (INIS)

    Petrova, K.; Frasch, G.

    2005-01-01

    Full text: The ESOREX project was initiated by the European Commission in 1997. The objectives of this European study are: to provide the European Commission and the national competent radiation protection authorities with reliable information on how personal radiation monitoring, reporting and recording of dosimetric results is organized in European countries; to collect reliable and directly comparable data on individual and collective radiation exposure in all occupational sectors where radiation workers are employed. The information about the monitoring of occupational radiation exposure, the levels of individual personal doses of workers in the different work sectors, the changes and trends of these doses over a period of several years and the international comparison of these data are useful information for many stakeholders. The survey consists of two parts. Part I surveys how radiation protection monitoring, recording and reporting is arranged within each of the 30 European countries. Part II collects doses from occupational exposure of classified workers in the participating countries. For each country, information is provided on the number of workers in defined work categories and how annual individual personal doses are distributed. The summary and the conclusions provide tentative recommendations for harmonizing modifications of some of the national monitoring, reporting and recording arrangements. In all ESOREX studies a beneficial, effective and extensive information base about thirty European states has been created. The studies resulted in country reports describing the legislative, administrative, organizational and technical aspects of the national dose monitoring and recording systems for occupationally radiation exposed workers. These reports are standardized, i.e. they have as far as possible an internationally comparable structure. The dose distributions of the radiation workers and the annual average and collective doses in the various work

  15. Prenatal radiation exposure. Dose calculation

    International Nuclear Information System (INIS)

    Scharwaechter, C.; Schwartz, C.A.; Haage, P.; Roeser, A.

    2015-01-01

    The unborn child requires special protection. In this context, the indication for an X-ray examination is to be checked critically. If thereupon radiation of the lower abdomen including the uterus cannot be avoided, the examination should be postponed until the end of pregnancy or alternative examination techniques should be considered. Under certain circumstances, either accidental or in unavoidable cases after a thorough risk assessment, radiation exposure of the unborn may take place. In some of these cases an expert radiation hygiene consultation may be required. This consultation should comprise the expected risks for the unborn while not perturbing the mother or the involved medical staff. For the risk assessment in case of an in-utero X-ray exposition deterministic damages with a defined threshold dose are distinguished from stochastic damages without a definable threshold dose. The occurrence of deterministic damages depends on the dose and the developmental stage of the unborn at the time of radiation. To calculate the risks of an in-utero radiation exposure a three-stage concept is commonly applied. Depending on the amount of radiation, the radiation dose is either estimated, roughly calculated using standard tables or, in critical cases, accurately calculated based on the individual event. The complexity of the calculation thereby increases from stage to stage. An estimation based on stage one is easily feasible whereas calculations based on stages two and especially three are more complex and often necessitate execution by specialists. This article demonstrates in detail the risks for the unborn child pertaining to its developmental phase and explains the three-stage concept as an evaluation scheme. It should be noted, that all risk estimations are subject to considerable uncertainties.

  16. Occupational radiation exposure in the GDR in 1977

    International Nuclear Information System (INIS)

    Poulheim, K.F.; Rothe, W.; Scheler, R.

    1980-01-01

    In 1977, radiation workers were monitored for external and internal radiation exposure on the basis of film badges (37,348 persons), measurements with a whole-body counter (198 persons) and analyses of biosamples (174 persons). According to the film badge data, the monthly over-exposures (more than 4 mGy) totalled 253. In 6 cases the monthly exposure exceeded 30 mGy and the 9 highest annual exposure values were in the range of 50 to 120 mGy. Also, annual collective and annual per caput doses have been given for the exposed population as a whole and some subgroups. Based on model considerations, the internal radiation exposure situation resulting from unintentional intakes of radionuclides has been assessed in terms of committed dose equivalents to members of two selected groups of radiation workers: (a) persons with more-than-average internal contamination levels; (b) persons subjected to frequent individual monitoring. Except for some organ doses, the individual radiation exposure was below one-tenth the maximum permissible dose. (author)

  17. Radiation exposure in diagnostic medicine

    International Nuclear Information System (INIS)

    Haehnel, S.; Michalczak, H.; Reinoehl-Kompa, S.

    1995-01-01

    This volume includes the manuscripts of the papers read at the conference as well as a summary and assessment of its results. The scientific discussions were centred upon the following issues: - International surveys and comparisons of rdiation exposures in diagnostic radiology and nuclear medicine, frequency of the individual diagnostic procedures and age distribution of patients examined; - policies and regulations for the radiation protection of patients, charcteristic dosimetric values and practical usefulness of the effective dose concept during medical examinations; - assessments of the relative benefits and risks and measures to reduce the radiation exposure in the light of quality assurance aspects. The main objective of this conference not only was to evaluate the risks from diagnostic radiology and nuclear medicine but also to encourgage a critical analysis and adjustment of examination routines followed in everyday practice. Among the measures recommended were quality assurance, maintenace of international standards, development of guidelines, introduction of standard doses, improved training and professional education of personnel as well as surveys and analyses of certain examination procedures associated with substantial radiation exposure. (orig./MG) [de

  18. Radiation exposure from civil aviation

    International Nuclear Information System (INIS)

    Schalch, D.

    1994-01-01

    The question as to whether civil air crews and frequent air passengers ought to be classified among the group of occupationally exposed persons has in principle been decided by the recommendations adopted by the ICRP, the competent bodies of the EU, and national authorities. Measurements for more information on the radiation fields involved are planned. The German Radiation Protection Office (BfS) recently published a statement on dose commitments, assuming a maximum annual dose of approx. 8 mSv in addition to the mean value already determined. Legal provisions, which ought to be adopted also on EU level since civil aviation is a transboundary traffic system, have yet to come. (orig./HP) [de

  19. Radiation exposure in monazite industry

    Energy Technology Data Exchange (ETDEWEB)

    Paul, A C [Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.

    1979-04-01

    The monazite present in the beach sands of Kerala and Tamil Nadu (India) is separated in the mineral separation plants at Manavalakurichi and Chavara, operated by M/s Indian Rare Earths Ltd. The physical and chemical processing of the sand involves radiation hazards due to the presence of thorium, uranium and their daughter products in monazite. The paper reviews present status in the light of past experiences and analyses the dose apportionment in different work catagories. The problem of internal contamination and environmental radiation levels are also discussed with the help of the recently available data. Radiation fields in the physical processing of monazite at different stages are presented. Apportionment of doses at different stages of the chemical operation involving 10 tonne lots of monazite is presented in a tabular form. The changing trend in external exposure reflected in the man-rem/t of monazite over the years is illustrated in a graph.

  20. Techniques for controlling radiation exposure

    International Nuclear Information System (INIS)

    Ocken, H.; Wood, C.J.

    1993-01-01

    The US nuclear power industry has been remarkably successful in reducing worker radiation exposure over the past 10 years. There has been more than a fourfold reduction in person-rem per MW-year of electric power generated: from 1.8 person-rems in 1980 to only 0.4 person-rems in 1991. Despite this substantial improvement, challenges for the industry remain. Individual exposure limits have been tightened in the 1990 Recommendations of the International Commission on Radiological Protection, ICRP Publication 60, and there will be more requirements for special maintenance work as plants age, suggesting that vigorous efforts will be required to meet the 1995 industry goals for unit median collective exposure. No one method will suffice, but implementing suitable combinations from this compendium will help utilities to achieve their exposure goals. Radiation reduction is generally cost-effective: Outages are shorter, staffing requirements are reduced, and work quality is improved. Despite up-front costs, the benefits over the following one to three years typically outweigh the expenses

  1. Radiation exposure and chromosome damage

    International Nuclear Information System (INIS)

    Lloyd, D.

    1979-01-01

    Chromosome damage is discussed as a means of biologically measuring radiation exposure to the body. Human lymphocytes are commonly used for this test since the extent of chromosome damage induced is related to the exposure dose. Several hundred lymphocytes are analysed in metaphase for chromosome damage, particularly dicentrics. The dose estimate is made by comparing the observed dicentric yield against calibration curves, previously produced by in vitro irradiation of blood samples to known doses of different types of radiation. This test is useful when there is doubt that the film badge has recorded a reasonable whole body dose and also when there is an absence of any physical data. A case of deliberate exposure is described where the chromosome damage test estimated an exposure of 152 rads. The life span of cell aberrations is also considered. Regular checks on radiotherapy patients and some accidental overdose cases have shown little reduction in the aberration levels over the first six weeks after which the damage disappears slowly with a half-life of about three years. In conclusion, chromosome studies have been shown to be of value in resolving practical problems in radiological protection. (U.K.)

  2. Radiation exposure analysis of female nuclear medicine radiation workers

    International Nuclear Information System (INIS)

    Lee, Ju Young; Park, Hoon Hee

    2016-01-01

    In this study, radiation workers who work in nuclear medicine department were analyzed to find the cause of differences of radiation exposure from General Characteristic, Knowledge, Recognition and Conduct, especially females working on nuclear medicine radiation, in order to pave the way for positive defense against radiation exposure. The subjects were 106 radiation workers who were divided into two groups of sixty-four males and forty-two females answered questions about their General Characteristic, Knowledge, Recognition, Conduct, and radiation exposure dose which was measured by TLD (Thermo Luminescence Dosimeter). The results of the analysis revealed that as the higher score of knowledge and conduct was shown, the radiation exposure decreased in female groups, and as the higher score of conduct was shown, the radiation exposure decreased in male groups. In the correlation analysis of female groups, the non-experienced in pregnancy showed decreasing amount of radiation exposure as the score of knowledge and conduct was higher and the experienced in pregnancy showed decreasing amount of radiation exposure as the score of recognition and conduct was higher. In the regression analysis on related factors of radiation exposure dose of nuclear medicine radiation workers, the gender caused the meaningful result and the amount of radiation exposure of female groups compared to male groups. In the regression analysis on related factors of radiation exposure dose of female groups, the factor of conduct showed a meaningful result and the amount of radiation exposure of the experienced in pregnancy was lower compared to the non-experienced. The conclusion of this study revealed that radiation exposure of female groups was lower than that of male groups. Therefore, male groups need to more actively defend themselves against radiation exposure. Among the female groups, the experienced in pregnancy who have an active defense tendency showed a lower radiation exposure. Thus

  3. Radiation exposure analysis of female nuclear medicine radiation workers

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ju Young [Dept. of Biomedical Engineering Graduate School, Chungbuk National University, Cheongju (Korea, Republic of); Park, Hoon Hee [Dept. of Radiological Technologist, Shingu College, Sungnam (Korea, Republic of)

    2016-06-15

    In this study, radiation workers who work in nuclear medicine department were analyzed to find the cause of differences of radiation exposure from General Characteristic, Knowledge, Recognition and Conduct, especially females working on nuclear medicine radiation, in order to pave the way for positive defense against radiation exposure. The subjects were 106 radiation workers who were divided into two groups of sixty-four males and forty-two females answered questions about their General Characteristic, Knowledge, Recognition, Conduct, and radiation exposure dose which was measured by TLD (Thermo Luminescence Dosimeter). The results of the analysis revealed that as the higher score of knowledge and conduct was shown, the radiation exposure decreased in female groups, and as the higher score of conduct was shown, the radiation exposure decreased in male groups. In the correlation analysis of female groups, the non-experienced in pregnancy showed decreasing amount of radiation exposure as the score of knowledge and conduct was higher and the experienced in pregnancy showed decreasing amount of radiation exposure as the score of recognition and conduct was higher. In the regression analysis on related factors of radiation exposure dose of nuclear medicine radiation workers, the gender caused the meaningful result and the amount of radiation exposure of female groups compared to male groups. In the regression analysis on related factors of radiation exposure dose of female groups, the factor of conduct showed a meaningful result and the amount of radiation exposure of the experienced in pregnancy was lower compared to the non-experienced. The conclusion of this study revealed that radiation exposure of female groups was lower than that of male groups. Therefore, male groups need to more actively defend themselves against radiation exposure. Among the female groups, the experienced in pregnancy who have an active defense tendency showed a lower radiation exposure. Thus

  4. Estimates of radiation doses from various sources of exposure

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This chapter provides an overview of radiation doses to individuals and to the collective US population from various sources of ionizing radiation. Summary tables present doses from various sources of ionizing radiation. Summary tables present doses from occupational exposures and annual per capita doses from natural background, the healing arts, nuclear weapons, nuclear energy and consumer products. Although doses from non-ionizing radiation are not as yet readily available in a concise form, the major sources of non-ionizing radiation are listed

  5. Radiation exposure and radiation hazards of human population. Pt. 1

    International Nuclear Information System (INIS)

    Jacobi, W.

    1982-01-01

    The present Part I provides a survey on the various sources of natural and artificial radiation exposure of human population. Furthermore, biological radiation effects and radiation damages are surveyed. In an appendix, radiation types, radiation doses, and radiation dose units are explained. (orig./GSCH) [de

  6. DOE Basic Overview of Occupational Radiation Exposure_2011 pamphlet

    Energy Technology Data Exchange (ETDEWEB)

    ORAU

    2012-08-08

    This pamphlet focusses on two HSS activities that help ensure radiation exposures are accurately assessed and recorded, namely: 1) the quality and accuracy of occupational radiation exposure monitoring, and 2) the recording, reporting, analysis, and dissemination of the monitoring results. It is intended to provide a short summary of two specific HSS programs that aid in the oversight of radiation protection activities at DOE. The Department of Energy Laboratory Accreditation Program (DOELAP) is in place to ensure that radiation exposure monitoring at all DOE sites is precise and accurate, and conforms to national and international performance and quality assurance standards. The DOE Radiation Exposure Monitoring Systems (REMS) program provides for the collection, analysis, and dissemination of occupational radiation exposure information. The annual REMS report is a valuable tool for managing radiological safety programs and for developing policies to protect individuals from occupational exposure to radiation. In tandem, these programs provide DOE management and workers an assurance that occupational radiation exposures are accurately measured, analyzed, and reported.

  7. Occupational radiation exposures in Cyprus

    Energy Technology Data Exchange (ETDEWEB)

    Kaplanis, Prodromos A; Christofides, Stelios [Medical Physics Department, Nicosia General Hospital, 1450 Nicosia (Cyprus)

    1999-12-31

    For the first time ever the occupational radiation exposure data of all the radiation workers of Cyprus, as obtained by the personnel monitoring service of the Dosimetry Laboratory of the Medical Physics Department of the Ministry of Health, is published and compared with that of other countries. The presented data shows a systematic trend of improvement both with regards to the methodology of monitoring and data recording. The efforts of the past few years in educating and training the users of ionising radiation with regards to the importance of the personnel monitoring service and the hazards of ionising radiation, has paid off and this is evident from the doses recorded in the past three years which are compared favourably with those of other countries, as given by the UNSCEAR 1993 report. The introduction of extremity monitoring, promises even better improvement in the methodology of monitoring the doses received by personnel working in Interventional Radiology, as well as other groups whose hands, unavoidably, come close to radiation sources. (authors) 3 refs., 12 tabs.

  8. Occupational radiation exposure in the GDR in 1980

    International Nuclear Information System (INIS)

    Poulheim, K.F.; Rothe, W.; Scheler, R.

    1982-01-01

    As in the previous year, the centralized monitoring of radiation workers for occupational exposure was carried out on the basis of film badges (38,781 persons), measurements with a whole-body counter and analyses of biosamples (351 persons in all). According to the film data, the monthly exposures exceeding 4 mGy totalled 682 including 48 doses higher than 10 mGy. Four workers received annual doses above 50 mGy, with the highest value being 1410 mGy. For the exposed population as a whole and some sub-groups, annual collective and mean annual doses have been given. In assessing internal exposure situation, use has been made of both data from the centralized monitoring program and those determined by some nuclear facilities themselves under the auspices of the SAAS. The results gave no indication of internal doses exceeding the annual limits of intake. (author)

  9. Occupational radiation exposure in the GDR in 1979

    International Nuclear Information System (INIS)

    Poulheim, K.F.; Rothe, W.; Scheler, R.

    1982-01-01

    As in the previous year, the centralized monitoring of radiation workers for occupational exposure was carried out on the basis of film badges (38,178 persons), measurements with a whole-body counter (247 persons) and analyses of biosamples (318 persons). According to the film data, the monthly exposures exceeding 4 mGy totalled 610 including 92 doses higher than 10 mGy. Six workers received annual doses above 50 mGy, with the highest value being 123 mGy. For the exposed population as a whole and some sub-groups, annual collective and mean annual doses have been given. In assessing the internal exposure situation, use has been made of both data from the centralized monitoring program and those determined by some nuclear facilities themselves under the auspices of the SAAS. The results gave no indication of internal doses exceeding the annual limits of intake. (author)

  10. The global assessment of medical radiation exposures

    International Nuclear Information System (INIS)

    Shannoun, F.

    2010-01-01

    World Health Organization (WHO) is the United Nations specialized agency which acts as a coordinating authority on international public health. It was established in 1948. It has 147 Country Offices, 6 Regional Offices and 193 Member States Ministries of Health Its headquarters is in Geneva. The World Health Assembly (WHA) requested WHO to s tudy the optimum use of ionizing radiation in medicine and the risks to health of excessive or improper use . (WHA, 1971) International Basic Safety Standards BSS) The (BSS) mark the culmination of efforts towards global harmonization of radiation safety requirements. However, the involvement of the health sector in the BSS implementation is still weak and scant. There is a need to mobilize the health sector towards safer and effective use of radiation in medicine. Radiation in Health Care The use of radiation in health care is by far the largest contributor to the exposure of the general population from artificial sources. Annually worldwide there are 3,600 million X-ray exams (> 300 million in children), 37 million nuclear medicine procedures and 7.5 million radiation oncology treatments [UNSCEAR Report 2008]. WHO Global Initiative on Radiation Safety in Health Care Settings Was launched in December 2008 It involved the following:- There was involvement of international organizations and professionals bodies, national health and radiation protection authorities, etc. Its aim is to improve the protection of patients and health care workers through better implementation of the BSS. It complements the International Action Plan for Radiological Protection of Patients established by the IAEA 7 UNSCEAR's medical exposure survey Objectives of UNSCEAR's survey were to facilitate evaluation of: - Global estimates of frequency and levels of exposures, with break-downs by medical procedure, age, sex, health care level, and country; - Trends in practice (including those relatively fast-changing); with supporting contextual

  11. Exposure of the Spanish population to radiation from natural sources

    International Nuclear Information System (INIS)

    Garcia-Talavera, M.; Suarez, E.; Matarranz, J.L.; Salas, R.; Ramos, L.

    2006-01-01

    We have assessed the exposure of the Spanish population to natural radiation sources. The annual average effective dose is estimated to be 2.38 mSv, taking into account contributions from cosmic radiation (13.8%), terrestrial gamma radiation (39%), radon and thoron inhalation (34%) and ingestion (13.2%). Cosmic radiation doses were calculated from town altitude data. Terrestrial gamma ray exposure outdoors was derived from the M.A.R.N.A. (natural gamma radiation map of Spain). Indoor gamma ray exposure was calculated by multiplying the corresponding outdoor value by a conversion factor, which was obtained by a linear least-squares fit of experimental measurements. Radon doses were estimated from national surveys carried out throughout the country. To assess doses by ingestion of water and foodstuffs we considered the results from a detailed study on consumption habits by age and geographical area in Spain, promoted by C.S.N., and average radioactivity values from UNSCEAR. (authors)

  12. Exposure of the Spanish population to radiation from natural sources

    Energy Technology Data Exchange (ETDEWEB)

    Garcia-Talavera, M.; Suarez, E.; Matarranz, J.L.; Salas, R.; Ramos, L. [Consejo de Seguridad Nuclear. Justo Dorado, Madrid (Spain)

    2006-07-01

    We have assessed the exposure of the Spanish population to natural radiation sources. The annual average effective dose is estimated to be 2.38 mSv, taking into account contributions from cosmic radiation (13.8%), terrestrial gamma radiation (39%), radon and thoron inhalation (34%) and ingestion (13.2%). Cosmic radiation doses were calculated from town altitude data. Terrestrial gamma ray exposure outdoors was derived from the M.A.R.N.A. (natural gamma radiation map of Spain). Indoor gamma ray exposure was calculated by multiplying the corresponding outdoor value conversion factor, which was obtained by a linear least-squares fit of experimental measurements. Radon doses were estimated from national surveys carried out throughout the country. To assess doses by ingestion of water and foodstuffs we considered the results from a detailed study on consumption habits by age and geographical area in Spain, promoted by C.S.N., and average radioactivity values from UNSCEAR. (authors)

  13. Unintentional exposure to ultraviolet radiation

    International Nuclear Information System (INIS)

    Sliney, D.H.

    1987-01-01

    To evaluate the risks from unintentional exposure to ultraviolet radiation (UVR), and to consider hazard control regulation, one must face first the problem of their state of scientific knowledge and the public's perception of UVR. Few people in the general public would question the health benefits of sunlight. Many flock to the beaches each summer to develop a healthy tan. Since the 1920's scientists have recognized that most of the benefits--and risks--of sunlight exposure result from the UVR present in sunlight. Dermatologists warn sunbathers to avoid exposure or protect themselves against the intense midday UVR or risk skin cancer. A growing number of scientists warn of hazards to the eye if UVR--perhaps even shorter visible wavelengths--are not filtered by lenses. In addition to any intentional exposure for health or cosmetic purposes, many people are also exposed to UVR without being aware of it or without their intent to be exposed. Outdoor workers are exposed to sunlight, many industrial workers (e.g., welders) are exposed to UVR from arc sources, some UVR penetrates clothing, and people indoors are exposed to UVR from artificial lighting

  14. Radiation hormesis at occupational exposure

    International Nuclear Information System (INIS)

    Georgieva, R.; Rupova, I.; Zaharieva, E.; Acheva, A.

    2007-01-01

    Complete text of publication follows. Objective: The idea in favour of the auspicious effect of low dose ionizing radiation in biological systems exists for years and serves as basis of the radiation hormesis hypothesis. The results in support of this phenomenon are not accepted as reliable by ICRP. The available epidemiological data could only suppose the presence of hormetic effect because of statistics limitations and relatively high spontaneous rate of the examined effects. The present work was aimed at finding appropriate biomarkers applicable in molecular epidemiological surveys of occupationally exposed individuals and/or population to prove radiation hormesis. Methods: Blood samples were taken from more than 400 NPP workers, divided in two groups: from the 'strict regimen' area (exposed) and from the administration staff (control). Two levels of evaluation were used: 1) molecular - spontaneous and induced DNA repair by UDS, protein synthesis evaluated radio-metrically, DNA damage by SCGE - all of them in white blood cells, concentration of malonedialdehyde in blood serum; and 2) cellular - the Ly-subsets by flow cytometry, using a FacScan analyzer and immunofluorescent stained mouse monoclonal antibodies. Results: A significant decrease of potentially lethal damage was found in persons with 'mean annual dose' lower or equal to 5 mSv/a, compared to the control group. The highest repair capacity after a challenging dose of 2,0 Gy gamma rays as well as a significant decrease in the level of oxidative stress was evaluated for persons from the same group. At doses below 200 mSv statistically different decrease of the index of CD3+4+, CD4+25+, CD4+62L+ lymphocyte populations and CD4/CD8 cell ratio was established, and increased levels of NK cells, CD57+8+ , CD8+28+ and CD8+38 were recorded. Conclusion: The present investigation showed that annual doses lower than twice the natural radiation background exert positive effects on DNA damage and repair, increase

  15. Natural and anthropogenic radiation exposure of humans in Germany

    International Nuclear Information System (INIS)

    Koelzer, Winfried

    2016-12-01

    The contribution on natural and anthropogenic radiation exposure in Germany covers the following issues: (1) natural radiation exposure: external radiation exposure - cosmic and terrestric radiation, internal radiation exposure - primordial and cosmogenic radionuclides; radiation exposure due to sola neutrinos and geo-neutrinos. (2) Anthropogenic radiation exposure: radiation exposure in medicine, radioactivity in industrial products, radiation exposure during flights, radiation exposure due to nuclear facilities, radiation exposure due to fossil energy carriers in power generation, radiation exposure due to nuclear explosions, radiation exposure due to nuclear accidents. (3) Occupational radiation exposure in Germany: radiation monitoring with personal dosimeters in medicine and industry, dose surveillance of the aviation personal, working places with increases radiation exposure by natural radiation sources.

  16. Evaluation of diseases associated to occupational exposure to ionizing radiations

    International Nuclear Information System (INIS)

    Suarez, Ileana Frometa

    1997-01-01

    A retrospective investigation of all cases of radiation workers with diseases and injuries, considered as occupational diseases caused by ionizing radiation is presented. The investigation includes all cases registered in the Institute of Occupational Health over five years period (1990-1995). The incidence of that diseases are studied, as well as the correlation between each type of source, time of exposure and annual average equivalent individual dose

  17. Biological characterization of radiation exposure and dose estimates for inhaled uranium milling effluents. Annual progress report April 1, 1982-March 31, 1983

    International Nuclear Information System (INIS)

    Eidson, A.F.

    1984-05-01

    The problems addressed are the protection of uranium mill workers from occupational exposure to uranium through routine bioassay programs and the assessment of accidental worker exposures. Comparisons of chemical properties and the biological behavior of refined uranium ore (yellowcake) are made to identify important properties that influence uranium distribution patterns among organs. These studies will facilitate calculations of organ doses for specific exposures and associated health risk estimates and will identify important bioassay procedures to improve evaluations of human exposures. A quantitative analytical method for yellowcake was developed based on the infrared absorption of ammonium diuranate and U 3 O 8 mixtures in KBr. The method was applied to yellowcake samples obtained from six operating mills. The composition of yellowcake from the six mills ranged from nearly pure ammonium diuranate to nearly pure U 3 O 8 . The composition of yellowcake samples taken from lots from the same mill was only somewhat less variable. Because uranium mill workers might be exposed to yellowcake either by contamination of a wound or by inhalation, a study of retention and translocation of uranium after subcutaneous implantation in rats was done. The results showed that 49% of the implanted yellowcake cleared from the body with a half-time (T sub 1/2) in the body of 0.3 days, and the remainder was cleared with a T sub 1/2 of 11 to 30 days. Exposures of Beagle dogs by nose-only inhalation to aerosols of commercial yellowcake were completed. Biochemical indicators of kidney dysfunction that appeared in blood and urine 4 to 8 days after exposure to the more soluble yellowcake showed significant changes in dogs, but levels returned to normal by 16 days after exposure. No biochemical evidence of kidney dysfunction was observed in dogs exposed to the less soluble yellowcake form. 18 figures, 9 tables

  18. Occupational radiation exposure in nuclear medicine department in Kuwait

    Science.gov (United States)

    Alnaaimi, M.; Alkhorayef, M.; Omar, M.; Abughaith, N.; Alduaij, M.; Salahudin, T.; Alkandri, F.; Sulieman, A.; Bradley, D. A.

    2017-11-01

    Ionizing radiation exposure is associated with eye lens opacities and cataracts. Radiation workers with heavy workloads and poor protection measures are at risk for vision impairment or cataracts if suitable protection measures are not implemented. The aim of this study was to measure and evaluate the occupational radiation exposure in a nuclear medicine (NM) department. The annual average effective doses (Hp[10] and Hp[0.07]) were measured using calibrated thermos-luminescent dosimeters (TLDs; MCP-N [LiF:Mg,Cu,P]). Five categories of staff (hot lab staff, PET physicians, NM physicians, technologists, and nurses) were included. The average annual eye dose (Hp[3]) for NM staff, based on measurements for a typical yearly workload of >7000 patients, was 4.5 mSv. The annual whole body radiation (Hp[10]) and skin doses (Hp[0.07]) were 4.0 and 120 mSv, respectively. The measured Hp(3), Hp(10), and Hp(0.07) doses for all NM staff categories were below the dose limits described in ICRP 2014 in light of the current practice. The results provide baseline data for staff exposure in NM in Kuwait. Radiation dose optimization measures are recommended to reduce NM staff exposure to its minimal value.

  19. DOE 2012 Occupational Radiation Exposure October 2013

    Energy Technology Data Exchange (ETDEWEB)

    Podonsky, Glenn S. [US Dept. of Energy, Washington, DC (United States). Office of Health, Safety and Security

    2012-02-02

    The U.S. Department of Energy (DOE) Office of Analysis within the Office of Health, Safety and Security (HSS) publishes the annual DOE Occupational Radiation Exposure Report to provide an overview of the status of radiation protection practices at DOE (including the National Nuclear Security Administration [NNSA]). The DOE 2012 Occupational Radiation Exposure Report provides an evaluation of DOE-wide performance regarding compliance with Title 10, Code of Federal Regulations (C.F.R.), Part 835, Occupational Radiation Protection dose limits and as low as reasonably achievable (ALARA) process requirements. In addition, the report provides data to DOE organizations responsible for developing policies for protection of individuals from the adverse health effects of radiation. The report provides a summary and an analysis of occupational radiation exposure information from the monitoring of individuals involved in DOE activities. Over the past 5-year period, the occupational radiation exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site. As an indicator of the overall amount of radiation dose received during the conduct of operations at DOE, the report includes information on collective total effective dose (TED). The TED is comprised of the effective dose (ED) from external sources, which includes neutron and photon radiation, and the internal committed effective dose (CED), which results from the intake of radioactive material into the body. The collective ED from photon exposure decreased by 23% between 2011 and 2012, while the neutron dose increased by 5%. The internal dose components of the collective TED decreased by 7%. Over the past 5-year period, 99.99% of the individuals receiving measurable TED have received doses below the 2 roentgen equivalent in man (rems) (20 millisievert [mSv]) TED administrative control level (ACL), which is well below the DOE regulatory limit of 5 rems (50 mSv) TED annually. The

  20. Ionizing radiations used in medical diagnostics as a source of radiation exposure of the Bulgarian population

    International Nuclear Information System (INIS)

    Ingilizova, K.; Vasilev, G.

    1998-01-01

    X-ray and radionuclide application in medical diagnosing is the major sources of Bulgarian population exposure to ionizing radiations exceeding the radiation background. The number of X-ray examination on a nationwide scale shows an increase from 1600 thousand annually in 1950 to 10300 thousand in 1980 and decreases to about 4700 thousand annually for the period 1992-1993. The frequency for the above mentioned time intervals varies in the range 0.22 to 1.17 examinations per capita annually and decreases to 0.56. The roentgenoscopy to roentgenography ratio varies from 2.5:1 to 0.9:1 (1975) and increases to 2.0:1 (1993). The number of radioisotope examinations increased from 34 thousand in 1970 to 170 thousand annually in 1985 and decreased to about thousand annually in 1992-1993 with a number of studies per capita varying from 0.004 to 0.020 and decreasing to 0.010. In 1993 the annual collective effective dose due to X-ray diagnostics amounts to about 7000 man-Sv/a which exceeds the radiation background exposure by 76%. Radioisotope diagnostics in the period reviewed accounted for nearly 700 man-Sv/a with an exposure exceeding the radiation background by 7.7%. The major problems relating to patient protection and benefit/risk ratio improvement are discussed. (author)

  1. Exposure to non ionizing radiations

    International Nuclear Information System (INIS)

    Campanella, L.; Dragone, R.; Pastorelli, A.

    2001-01-01

    In the last years the exposure levels to electric, magnetic and electromagnetic fields of workers and citizens have dramatically increased due to the technological development as in the exemplar case of cellular phones. The object of this research concerns the biological evaluation of the risk from exposure to non ionizing radiations (NIR) by an opportunely designed biosensor based on immobilized Saccharomyces cerevisiae cells and by an amperometric transducer (Clark oxygen electrode). The results have been obtained by comparing the respiratory activities of exposed and not exposed yeast cells to NIR (at 900 MHz, frequency of the first generation cellular phones). The measurements have been performed by irradiation of the cells in a G-TEM chamber. The obtained results clearly show a decrease of the respiration activity of the irradiation cells in comparison with blank. This variation results to be proportional to the exposure time. Concerning reversibility of the damage it seems that the recovery of the initial conditions begins after 4 hours since the end of exposition and is complete within the following 48 hrs [it

  2. Occupational radiation exposure in Germany in 2011. Report of the radiation protection register

    International Nuclear Information System (INIS)

    Frasch, Gerhard; Kammerer, Lothar; Karofsky, Ralf; Mordek, Else; Schlosser, Andrea; Spiesl, Josef

    2013-04-01

    In Germany, persons who are occupationally exposed to ionising radiation are monitored by several official dosimetry services that transmit the dose records about individual radiation monitoring to the Radiation Protection Register of the Federal Office for Radiation Protection (BfS). The purpose of the Radiation Protection Register is to supervise the keeping of the dose limits and to monitor the compliance with the radiation protection principle ''Optimisation'' by performing detailed annual statistical analyses of the monitored persons and their radiation exposure. The annual report of the Radiation Protection Register provides information about status and development of occupational radiation exposure in Germany. In 2011, about 350,000 workers were monitored with dosemeters for occupational radiation exposure. The number increased during the past five years continuously by 10 %. Only 19 % of the monitored persons received measurable personal doses. The average annual dose of these exposed workers was 0.58 mSv corresponding to 3 % of the annual dose limit of 20 mSv for radiation workers. In total, 7 persons exceeded the annual dose limit of 20 mSv, i.e. two cases per 100,000 monitored persons. The collective dose of the monitored persons decreased to 38.5 Person-Sv, the lowest value since the last fifty years of occupational dose monitoring. In 2010, 45 airlines calculated the route doses of 39,000 members of the aircraft crew personnel by using certified computer programmes for dose calculation and sent the accumulated monthly doses via the Federal Office for Civil Aviation (''Luftfahrt-Bundesamt, LBA'') to the BfS. The collective dose of the aircraft crew personnel is 83 person-Sv, and thus significantly higher than the total collective dose of the workers monitored with personal dosemeters (38.5 person-Sv). The annual average dose of aircraft crew personnel was 2.12 mSv and decreased compared to 2010 (2,30 mSv). In 2011, about 70,000 outside-workers were in

  3. Measures to reduce occupational radiation exposure in PET facilities from nurses' point of view

    International Nuclear Information System (INIS)

    Miyazawa, Keiko; Takahashi, Juri; Mochiduki, Yoshikazu

    2006-01-01

    In parallel with the increase in the number of institutions having PET facilities, the number of nurse working in these facilities has also increased, and the issue of occupational radiation exposure has assumed ever greater importance. In our clinic, since nurses have started to administer FDG intravenous injections, their annual radiation exposure has amounted to 4.8 - 7.1 mSv. To reduce their annual radiation exposure to less than 5 mSv, we identified sources of increased exposure and considered countermeasures based on this information. By implementing countermeasures such as improvements in daily working conditions and ways to avoid various troubles, it was possible to reduce the annual radiation exposure of all nurses to less than 5 mSv. Our experience demonstrates that to provide a working environment with a minimum of occupational radiation exposure, educational training and enhancement of knowledge and technical skills are vital. (author)

  4. Occupational radiation exposures at NRC-licensed facilities

    International Nuclear Information System (INIS)

    Brooks, B.G.

    1980-01-01

    For the past ten years, the Nuclear Regulatory Commission and its predecessor, the Atomic Energy Commission, have required certain licensees to routinely submit two types of occupational radiation exposure reports: termination and annual reports. Each licensee engaged in any one of the activities: (1) operation of nuclear power reactors, (2) industrial radiography, (3) fuel fabrication, processing and reprocessing, and (4) large supply of byproduct material, is required to submit an annual statistical report and a termination report for each monitored employee who ends his employment or work assignment. A new regulation now requires all NRC licensees to submit annual reports for the years 1978 and 1979. These reports have been collected, computerized and maintained by the Commission at Oak Ridge, Tennessee. They are useful to the NRC in the evaluation of the risk of radiation exposure associated with the related activities. (author)

  5. 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)

  6. Evaluation of natural radiation exposure of the French population

    International Nuclear Information System (INIS)

    Billon, S.; Morin, A.; Baysson, H.; Gambard, J.P.; Rannou, A.; Tirmarche, M.; Laurier, D.; Caer, S.

    2004-01-01

    Exposure of the French population to ionising radiation is mainly due to natural radiation (i.e. exposure through: inhalation of radon decay products, external radiation of terrestrial and cosmic origin and water and food ingestion). In an epidemiological context, it is necessary to estimate as precisely as possible the population exposure, in order to study its influence on health indicators. In this aim, indicators of population exposure should be created taking into account results of environmental measurements by controlling the different factors that may influence these measurements (dwelling characteristics, seasonal variations, population density). The distribution of these exposures should also be studied at different geographical levels (department, job area). This work updates the estimation of the French population exposure to natural radiation. Radon exposure indicators have been based on concentrations measured in dwellings, corrected on season and dwelling characteristics (departmental range: 19-297 Bq/m 3 ). Indicators of terrestrial gamma ray exposure have been based on measured indoor and outdoor dose rates adjusted on dwelling characteristics (22-95 nSv/h). Cosmic ray exposure has been evaluated from altitude and weighted by population density (0.27-0.38 mSv/yr). Due to these three components, the effective annual dose was estimated to be at 2.2 mSv. (author)

  7. Radiation exposure of airplane crews. Exposure levels

    International Nuclear Information System (INIS)

    Bergau, L.

    1995-01-01

    Even at normal height levels of modern jet airplanes, the flying crew is exposed to a radiation level which is higher by several factors than the terrestrial radiation. There are several ways in which this can be hazardous; the most important of these is the induction of malignant growths, i.e. tumours. (orig./MG) [de

  8. A new radiation exposure record system

    International Nuclear Information System (INIS)

    Lyon, M.; Berndt, V.L.; Trevino, G.W.; Oakley, B.M.

    1993-04-01

    The Hanford Radiological Records Program (HRRP) serves all Hanford contractors as the single repository for radiological exposure for all Hanford employees, subcontractors, and visitors. The program administers and preserves all Hanford radiation exposure records. The program also maintains a Radiation Protection Historical File which is a historical file of Hanford radiation protection and dosimetry procedures and practices. Several years ago DOE declared the existing UNIVAC mainframe computer obsolete and the existing Occupational Radiation Exposure (ORE) system was slated to be redeveloped. The new system named the Radiological Exposure (REX) System is described in this document

  9. Global environment and radiation exposure

    International Nuclear Information System (INIS)

    Okamoto, Kazuto

    1991-01-01

    The present status of investigation of acid rain, stratospheric ozone depletion and greenhouse effect and their relations to radiation exposure are reported. Soil acidification increases transfer rates of radioactivities to plants which increases the population dose. There are two types of ozone depletion, conventional type and ozone hole type and the latter is much more serious than the former. In the greenhouse effect, although there are large uncertainties both in theoretical and observational sides, present predictions about the global warming will not be very far from reality. Environmental effects are wide-ranging and serious. Radon and thoron exhalation rates are affected by the global warming. The influence of the greenhouse effect on ozone depletion is to suppress depletion for conventional type and enhance depletion for ozone hole type. (author) 65 refs

  10. ACREM: A new air crew radiation exposure measuring system

    International Nuclear Information System (INIS)

    Beck, P.; Duftschmid, K.; Kerschbaumer, S.; Schmitzer, C.; Strachotinsky, C.; Grosskopf, A.; Winkler, N.

    1996-01-01

    Cosmic radiation has already been discovered in 1912 by the Austrian Nobel Laureate Victor F. Hess. After Hess up to now numerous measurements of the radiation exposure by cosmic rays in different altitudes have been performed, however, this has not been taken serious in view of radiation protection.Today, with the fast development of modern airplanes, an ever increasing number of civil aircraft is flying in increasing altitudes for considerable time. Members of civil aircrew spending up to 1000 hours per year in cruising altitudes and therefore are subject to significant levels of radiation exposure. In 1990 ICRP published its report ICRP 60 with updated excess cancer risk estimates, which led to significantly higher risk coefficients for some radiation qualities. An increase of the radiation weighting factors for mean energy neutron radiation increases the contribution for the neutron component to the equivalent dose by about 60%, as compared to the earlier values of ICRP26. This higher risk coefficients lead to the recommendation of the ICRP, that cosmic radiation exposure in civil aviation should be taken into account as occupational exposure. Numerous recent exposure measurements at civil airliners in Germany, Sweden, USA, and Russia show exposure levels in the range of 3-10 mSv/year. This is significantly more than the average annual dose of radiation workers (in Austria about 1.5 mSv/year). Up to now no practicable and economic radiation monitoring system for routine application on board exits. A fairly simple and economic approach to a practical, active in-flight dosimeter for the assessment of individual crew exposure is discussed in this paper

  11. Ice-based altitude distribution of natural radiation annual exposure rate in the Antarctica zone over the latitude range 69 degrees S-77 degrees S using a pair-filter thermoluminescence method.

    Science.gov (United States)

    Nakajima, T; Kamiyama, T; Fujii, Y; Motoyama, H; Esumi, S

    1995-12-01

    Both ice-based altitude distributions of natural ionizing radiation exposure and the quasi-effective energy of natural radiation over Antartica over the latitude range 69 degrees S - 77 degrees S during approx. 500 days were measured using thermoluminescent dosimeters. The results shows that dependence on altitude above sea level of the exposure rate increases by almost three-fold with each increase of 2000 m of altitude, thus deviating from the general rule stating that the exposure rate should double with each 2000 m. Although the exposure rate shows a dependence on altitude, altitude dependence of the quasi-effective energy of natural radiation over Antartica is not observed. In the present study it is observed that natural radiation occurring over the ice base of Antartica consists mainly of cosmic rays.

  12. Ice-based altitude distribution of natural radiation annual exposure rate in the Antarctica zone over the latitude range 69 deg S-77 deg S using a pair-filter thermoluminescence method

    International Nuclear Information System (INIS)

    Nakajima, Toshiyuki; Kamiyama, Takayoshi; Fujii, Yoshiyuki; Motoyama, Hideaki; Esumi, Shuuichi

    1995-01-01

    Both ice-based altitude distributions of natural ionizing radiation exposure and the quasi-effective energy of natural radiation over Antarctica over the latitude range 69 o S-77 o S during approx. 500 days were measured using thermoluminescent dosimeters. The results shows that dependence on altitude above sea level of the exposure rate increases by almost three-fold with each increase of 2000 m of altitude, thus deviating from the general rule stating that the exposure rate should double with each 2000 m. Although the exposure rate shows a dependence on altitude, altitude dependence of the quasi-effective energy of natural radiation over Antarctica is not observed. In the present study it is observed that natural radiation occurring over the ice base of Antarctica consists mainly of cosmic rays. (Author)

  13. PET radiation exposure control for nurses

    International Nuclear Information System (INIS)

    Kawabata, Yumiko; Kikuta, Daisuke; Anzai, Taku

    2005-01-01

    Recently, the number of clinical PET centers is increasing all over Japan. For this reason, the monitoring and control of radiation exposure of employees, especially nurses, in PET-dedicated clinics and institutions are becoming very important issues for their health. We measured the radiation exposure doses of the nurses working at Nishidai Diagnostic Imaging Center, and analyzed the exposure data obtained from them. The exposure doses of the nurses were found to be 4.8 to 7.1 mSv between April 2003 and March 2004. We found that the nurses were mostly exposed to radiation when they had to have contact with patients received an FDG injection or they had trouble with the FDG automatic injection system. To keep radiation exposure of nurses to a minimum we reconfirmed that a proper application of the three principles of protection against radiation exposure was vital. (author)

  14. Aircrew radiation exposure: sources-risks-measurement

    International Nuclear Information System (INIS)

    Duftschmid, K.E.

    1994-05-01

    A short review is given on the actual aircrew exposure and its sources. The resulting risks for harmful effects to the health and discuss methods for in-flight measurements of exposure is evaluated. An idea for a fairly simple and economic approach to a practical, airborne active dosimeter for the assessment of individual crew exposure is presented. The exposure of civil aircrew to cosmic radiation, should not be considered a tremendous risk to the health, there is no reason for panic. However, being significantly higher than the average exposure to radiation workers, it can certainly not be neglected. As recommended by ICRP, aircrew exposure has to be considered occupational radiation exposure and aircrews are certainly entitled to the same degree of protection, as other ground-based radiation workers have obtained by law, since long time. (author)

  15. Medical exposure and the effects of radiation

    International Nuclear Information System (INIS)

    Okuyama, Chio

    2011-01-01

    Radiation gives cracks to genes. The influence is divided into deterministic effect with a threshold value, and the stochastic effect (tumor and genetic effect) which increases according to the exposure amount. Although we are put to various non-artificial radiations, which we cannot be avoided, on the earth, the contamination by artificial radiation can be defended. Artificial radioactive exposure includes medical exposure and non-medical exposure for example by nuclear power plant. As to medical examinations using radiation, the inquiry about the radiation exposure is increasing after the occurrence of the first nuclear power plant disaster of Fukushima. While concern about non-medical radioactive exposure increases, the uneasiness to medical irradiation is also increasing. The dose limit by artificial radioactive exposure other than medical exposure is set up in order to prevent the influence on the health. While the dose limit of the public exposure is set to the lower value than the total dose of non-artificial exposure concerning of a safety margin for all people, the dose limit of medical exposure is not defined, since it is thought that medical irradiation has a benefit for those who receive irradiation. Making an effort to decrease the radiation dose in performing the best medical treatment is the responsibility with which we are burdened. (author)

  16. Application of maximum radiation exposure values and monitoring of radiation exposure

    International Nuclear Information System (INIS)

    1996-01-01

    The guide presents the principles to be applied in calculating the equivalent dose and the effective dose, instructions on application of the maximum values for radiation exposure, and instruction on monitoring of radiation exposure. In addition, the measurable quantities to be used in monitoring the radiation exposure are presented. (2 refs.)

  17. Eating habits and internal radiation exposures in Japanese

    International Nuclear Information System (INIS)

    Shiraishi, Kunio

    1995-01-01

    Recently, annual dose equivalent for Japanese was estimated to be 3.75 mSv. Medical radiation exposures (2.25 mSv/y) and exposures from natural sources of radiation (1.48 mSv/y) were the major contributors to this dose. Dietary intakes of both natural and man-made radionuclides directly related to internal exposures. In this paper, internal doses received only through ingestion of radionuclides in food are described; internal doses through inhalation have been excluded. First, the representative intakes of radionuclides for Japanese were estimated from the literature. Second, the annual dose equivalents were calculated according to intakes of individual radionuclides and weighted committed dose equivalents (Sv/Bq) of the International Commission on Radiological Protection Pub. 30. Total annual doses through radiation of natural sources and man-made sources, were estimated as 0.35 mSv and 0.001 mSv, respectively. Furthermore, the effects of imported foods on internal dose in Japanese were calculated preliminarily, because the contribution of imported foods to Japanese eating habits is increasing annually and will not be negligible when assessing internal dose in the near future. (author)

  18. Radiation exposures for DOE and DOE contractor employees, 1990

    International Nuclear Information System (INIS)

    Smith, M.H.; Hui, T.E.; Millet, W.H.; Scholes, V.A.

    1994-03-01

    This is the 23rd in a series of annual radiation exposure reports published by the Department of Energy (DOE) or its predecessors. This report summarizes the radiation exposures received by both employees and visitors at DOE and DOE contractor facilities during 1990. Trends in radiation exposures are evaluated by comparing the doses received in 1990 to those received in previous years. The significance of the doses is addressed by comparing them to the DOE limits and by correlating the doses to health risks based on risk estimated from expert groups. This report is the third that is based on detailed exposure data for each individual monitored at a DOE facility. Prior to 1988, only summarized data from each facility were available. This report contains information on different types of radiation doses, including total effective, internal, penetrating, shallow, neutron, and extremity doses. It also contains analysis of exposures by age, sex, and occupation of the exposed individuals. This report also continues the precedent established in the Twenty-First (1988) Annual Report by conducting a detailed, one-time review and analysis of a particular topic of interest. The special topic for this report is a comparison of total effective, internal, and extremity dose equivalent values against penetrating dose equivalent values

  19. Risk associated with occupational exposure to ionizing radiation kept in perspective

    International Nuclear Information System (INIS)

    Bonnell, J.A.; Harte, G.

    1978-01-01

    The risks associated with exposure to ionizing radiations are placed in perspective by a study of the natural incidence of those diseases in the United Kingdom that can be induced by radiation exposure. It is apparent that at ICRP recommended annual dose equivalent limits the small risks associated with exposure to ionizing radiations are acceptable, bearing in mind the obvious benefits that accrue from activities such as power production. This applies both to genetic and somatic diseases. (author)

  20. Development and implementation of a new radiation exposure record system

    International Nuclear Information System (INIS)

    Lyon, M.; Berndt, V.L.; Trevino, G.W.; Oakley, B.M.

    1993-01-01

    The Hanford Radiological Records Program (HRRP) maintains all available radiation exposure records created since the 1940s for employees of and visitors to the Hanford Site. The program provides exposure status reports to the US Department of Energy Richland Operations Office (DOE-RL) and the Hanford contractors, annual exposure reports to individual employees and visitors, and exposure reports to terminated employees. Program staff respond to offsite requests for exposure data on former employees and supply data and reports for epidemiological and research projects as well as for annual reports required by DOE Orders. Historical files, documenting radiation protection and dosimetry policies, procedures, and practices, and radiological incidents, are also maintained under this program. The program is operated by Pacific Northwest Laboratory for DOE-RL. This paper describes how the record-keeping requirements supported by the HRRP's computerized radiation exposure database were analyzed so that the system could be redeveloped and implemented to (1) accommodate a change in mainframe computer units, and (2) to enhance its automated record-keeping, retrieval, and reporting capabilities in support of the HRRP

  1. Acute radiation syndrome caused by accidental radiation exposure - therapeutic principles

    Directory of Open Access Journals (Sweden)

    Dörr Harald

    2011-11-01

    Full Text Available Abstract Fortunately radiation accidents are infrequent occurrences, but since they have the potential of large scale events like the nuclear accidents of Chernobyl and Fukushima, preparatory planning of the medical management of radiation accident victims is very important. Radiation accidents can result in different types of radiation exposure for which the diagnostic and therapeutic measures, as well as the outcomes, differ. The clinical course of acute radiation syndrome depends on the absorbed radiation dose and its distribution. Multi-organ-involvement and multi-organ-failure need be taken into account. The most vulnerable organ system to radiation exposure is the hematopoietic system. In addition to hematopoietic syndrome, radiation induced damage to the skin plays an important role in diagnostics and the treatment of radiation accident victims. The most important therapeutic principles with special reference to hematopoietic syndrome and cutaneous radiation syndrome are reviewed.

  2. DOE Occupational Radiation Exposure, 2001 report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2001-12-31

    The goal of the U.S. Department of Energy (DOE) is to conduct its operations, including radiological, to ensure the safety and health of all DOE employees, contractors, and subcontractors. The DOE strives to maintain radiation exposures to its workers below administrative control levels and DOE limits and to further reduce these exposures to levels that are “As Low As Reasonably Achievable” (ALARA). The 2001 DOE Occupational Radiation Exposure Report provides a summary and analysis of the occupational radiation exposure received by individuals associated with DOE activities. The DOE mission includes stewardship of the nuclear weapons stockpile and the associated facilities, environmental restoration of DOE, and energy research.

  3. Ionizing radiation exposure of LDEF

    Science.gov (United States)

    Benton, E. V. (Editor); Heinrich, W. (Editor)

    1990-01-01

    The Long Duration Exposure Facility (LDEF) was launched into orbit by the Space Shuttle 'Challenger' mission 41C on 6 April 1984 and was deployed on 8 April 1984. The original altitude of the circular orbit was 258.5 nautical miles (479 km) with the orbital inclination being 28.5 degrees. The 21,500 lb NASA Langley Research Center satellite, having dimensions of some 30x14 ft was one of the largest payloads ever deployed by the Space Shuttle. LDEF carried 57 major experiments and remained in orbit five years and nine months (completing 32,422 orbits). It was retrieved by the Shuttle 'Columbia' on January 11, 1990. By that time, the LDEF orbit had decayed to the altitude of 175 nm (324 km). The experiments were mounted around the periphery of the LDEF on 86 trays and involved the representation of more than 200 investigators, 33 private companies, 21 universities, seven NASA centers, nine Department of Defense laboratories and eight foreign countries. The experiments covered a wide range of disciplines including basic science, electronics, optics, materials, structures, power and propulsion. The data contained in the LDEF mission represents an invaluable asset and one which is not likely to be duplicated in the foreseeable future. The data and the subsequent knowledge which will evolve from the analysis of the LDEF experiments will have a very important bearing on the design and construction of the Space Station Freedom and indeed on other long-term, near-earth orbital space missions. A list of the LDEF experiments according to experiment category and sponsor is given, as well as a list of experiments containing radiation detectors on LDEF including the LDEF experiment number, the title of the experiment, the principal investigator, and the type of radiation detectors carried by the specific experiment.

  4. Radiation exposure of the Yugoslav Airlines crews according to new radiation limits

    International Nuclear Information System (INIS)

    Antic, D.

    1998-01-01

    Radiation exposure of the Yugoslav Airlines (JAT) crews in commercial air traffic has been studied according to the new radiation limits (ICRP 60). Selected pilots make the groups, for different types in use by JAT, and two groups of the co-pilots ('flight engineers' for B-727 and DC-10 aircraft's). Cabin crew members make three groups of pursers and two groups of STW/STD (they include both male and female workers). Annual doses and added risks have been assessed. (author)

  5. Sources of radiation exposure - an overview

    International Nuclear Information System (INIS)

    Mason, G.C.

    1990-01-01

    Sources of radiation exposure are reviewed from the perspective of mining and milling of radioactive ores in Australia. The major sources of occupational and public exposure are identified and described, and exposures from mining and milling operations are discussed in the context of natural radiation sources and other sources arising from human activities. Most radiation exposure of humans comes from natural sources. About 80% of the world average of the effective dose equivalents received by individual people arises from natural radiation, with a further 15-20% coming from medical exposures*. Exposures results from human activities, such as mining and milling of radioactive ores, nuclear power generation, fallout from nuclear weapons testing and non-medical use of radioisotopes and X-rays, add less than 1% to the total. 9 refs., 4 tabs., 10 figs

  6. Radiation protection, 1975. Annual EPA review of radiation protection activities

    International Nuclear Information System (INIS)

    1976-06-01

    The EPA, under its Federal Guidance authorities, is responsible for advising the President on all matters pertaining to radiation and, through this mechanism, to provide guidance to other Federal agencies on radiation protection matters. Highlights are presented of significant radiation protection activities of all Federal agencies which were completed in 1975, or in which noteworthy progress was made during that period, and those events affecting members of the public. State or local activities are also presented where the effects of those events may be more far-reaching. At the Federal level significant strides have been made in reducing unnecessary radiation exposure through the efforts of the responsible agencies. These efforts have resulted in the promulgation of certain standards, criteria and guides. Improved control technologies in many areas make it feasible to reduce emissions at a reasonable cost to levels below current standards and guides. This report provides information on the significant activities leading to the establishment of the necessary controls for protection of public health and the environment. Radiation protection activities have been undertaken in other areas such as medical, occupational and consumer product radiation. In the context of radiation protection, ancillary activities are included in this report in order to present a comprehensive overview of the events that took place in 1975 that could have an effect on public health, either directly or indirectly. Reports of routine or continuing radiation protection operations may be found in publications of the sponsoring Federal agencies, as can more detailed information about activities reported in this document. A list of some of these reports is included

  7. The analysis of radiation exposure of hospital radiation workers

    International Nuclear Information System (INIS)

    Jeong, Tae Sik; Shin, Byung Chul; Moon, Chang Woo; Cho, Yeong Duk; Lee, Yong Hwan; Yum, Ha Yong

    2000-01-01

    This investigation was performed in order to improve the health care of radiation workers, to predict a risk, to minimize the radiation exposure hazard to them and for them to realize radiation exposure danger when they work in radiation area in hospital. The documentations checked regularly for personal radiation exposure in four university hospitals in Pusan city in Korea between January 1, 1993 and December 31, 1997 were analyz ed. There were 458 persons in this documented but 111 persons who worked less then one year were excluded and only 347 persons were included in this study. The average of yearly radiation exposure of 347 persons was 1.52±1.35 mSv. Though it was less than 5OmSv, the limitaion of radiation in law but 125 (36%) people received higher radiation exposure than non-radiation workers. Radiation workers under 30 year old have received radiation exposure of mean 1.87±1.01 mSv/year, mean 1.22±0.69 mSv between 31 and 40 year old and mean 0.97±0.43 mSv/year over, 41year old (p<0.001). Men received mean 1.67±1.54 mSv/year were higher than women who received mean 1.13±0.61 mSv/year (p<0.01). Radiation exposure in the department of nuclear medicine department in spite of low energy sources is higher than other departments that use radiations in hospital (p<0.05). And the workers who received mean 3.69±1.81 mSv/year in parts of management of radiation sources and injection of sources to patient receive high radiation exposure in nuclear medicine department (0<0.01). In department of diagnostic radiology high radiation exposure is in barium enema rooms where workers received mean 3.74±1.74 mSv/year and other parts where they all use fluoroscopy such as angiography room of mean 1.17±0.35 mSv/year and upper gastrointestinal room of mean 1.74±1.34 mSv/year represented higher radiation exposure than average radiation exposure in diagnostic radiology (p<0.01). Doctors and radiation technologists received higher radiation exposure of each mean 1.75±1

  8. Application of maximum radiation exposure values and monitoring of radiation exposure

    International Nuclear Information System (INIS)

    1993-01-01

    According to the Section 32 of the Radiation Act (592/91) the Finnish Centre for Radiation and Nuclear Safety gives instructions concerning the monitoring of the radiation exposure and the application of the dose limits in Finland. The principles to be applied to calculating the equivalent and the effective doses are presented in the guide. Also the detailed instructions on the application of the maximum exposure values for the radiation work and for the natural radiation as well as the instructions on the monitoring of the exposures are given. Quantities and units for assessing radiation exposure are presented in the appendix of the guide

  9. Occupational exposures at nuclear power plants. Fourteenth annual report of the ISOE programme, 2004

    International Nuclear Information System (INIS)

    2006-01-01

    The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from 478 operating and shutdown commercial nuclear power plants participating in the programme (representing some 90% of the world's total operating commercial reactors). The Fourteenth Annual Report of the ISOE Programme summarises achievements made during 2004 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

  10. Occupational exposures at nuclear power plants. Eleventh annual report of the Isoe programme, 2001

    International Nuclear Information System (INIS)

    2002-01-01

    The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 452 commercial nuclear power plants participating in the programme (representing some 90 per cent of the world's total operating commercial reactors). The Eleventh Annual Report of the ISOE Programme summarises achievements made during 2001 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

  11. Minimizing radiation exposure during percutaneous nephrolithotomy.

    Science.gov (United States)

    Chen, T T; Preminger, G M; Lipkin, M E

    2015-12-01

    Given the recent trends in growing per capita radiation dose from medical sources, there have been increasing concerns over patient radiation exposure. Patients with kidney stones undergoing percutaneous nephrolithotomy (PNL) are at particular risk for high radiation exposure. There exist several risk factors for increased radiation exposure during PNL which include high Body Mass Index, multiple access tracts, and increased stone burden. We herein review recent trends in radiation exposure, radiation exposure during PNL to both patients and urologists, and various approaches to reduce radiation exposure. We discuss incorporating the principles of As Low As reasonably Achievable (ALARA) into clinical practice and review imaging techniques such as ultrasound and air contrast to guide PNL access. Alternative surgical techniques and approaches to reducing radiation exposure, including retrograde intra-renal surgery, retrograde nephrostomy, endoscopic-guided PNL, and minimally invasive PNL, are also highlighted. It is important for urologists to be aware of these concepts and techniques when treating stone patients with PNL. The discussions outlined will assist urologists in providing patient counseling and high quality of care.

  12. Radiation exposure of uranium mill workers

    International Nuclear Information System (INIS)

    Jha, Giridhar; Saha, S.C.

    1982-01-01

    The uranium mill workers at Jaduguda were covered by a regular film badge service from 1969 onwards. Since the log normal plot is useful in interpreting occupational exposure, a statistical analysis of the radiation exposure data was attempted. Exposure data for each year has been plotted as cumulative percentage and worker's population with exposure levels in different class intervals. The plot for each of the year under investigation shows an occupational exposure distribution more or less consistent with the log normal distribution function. The analysis shows that more than 98% of radiation workers received less than 200 mrem (2 mSv). (author)

  13. Occupational radiation exposure in work with radioactive materials

    International Nuclear Information System (INIS)

    Georgiev, G.V.

    1975-01-01

    Radiation exposure to personnel dealing with radioactive materials is studied on a national scale. The survey covers any type of radiation work except for mining and milling of radioactive ore, fuel production, and nuclear reactor operation. Assessments are based on a decade's collection of personnel monitoring data obtained by film dosimetry techniques, as well as on data from systematic operational site monitoring. Statistical analysis indicated exposures based on personal records to follow a normal distribution pattern and, hence, arithmetic averages to be representative. Airborne concontrations of radioactive materials and aerosols in working areas are shown to follow a logarithmic normal distribution pattern, so that geometric means are representative. Radiation exposures are generally found to be well below annual maximum permissible doses for radiation workers. However, their distribution among employee groups is nonuniform. Group A, comprising about 700 subjects, received mean annual gonad doses of more than 1000 mrem; group B, about 670 subjects, had doses ranging from 100 to 500 mrem per year; and group C, 1610 subjects, received less than 100 mrem per year. Most of the radiation dose is accounted for by external radiation, which contributed 0.327 mrem to the genetically significant population dose (0.227 from exposure to males, and 0.025 mrem from exposure to females). Analysis of accidental exposures occurring over the period 1963-1973 indicated that the contribution of this source is substantial as compared to routine work (1.0:0.3). Based on the results obtained, a number of preventive measures are developed and introduced into practice to improve radiological safety in work with radioactive materials. (A.B.)

  14. 1999 report on occupational radiation exposures in Canada

    International Nuclear Information System (INIS)

    Sont, W.; Ashmore, J.P.

    1999-01-01

    The report provides statistics on occupational radiation exposures for use by regulatory authorities, organizations and private individuals. Out of a total of 125,883 monitored workers, 4 annual doses exceeded the regulatory limit of 50 mSv in 1998. Out of 43 specified job categories, 18 had a smaller annual average in 1998 than in 1997, 17 had a higher average, and 8 had the same average rounded to 0.01 mSv. The uranium mining job categories are not in this list because the conversion factor for radon progeny exposure to effective dose was changed from 10 to 5 mSv/WLM, precluding a valid comparison of the averages. In all categories of workers, from 1996 to 1997, 19 average annual doses went up, 33 went down, and 4 stayed the same. The figures reflect a sustained effort in keeping the occupational doses low. (author)

  15. Proposed alternatives for a DOE-wide occupational radiation exposure information system

    International Nuclear Information System (INIS)

    Murphy, B.L.; Murphy, D.W.; Fix, J.J.; Selby, J.M.; Vallario, E.J.

    1984-02-01

    The Radiation Exposure Information Reporting System (REIRS) was initiated by the Atomic Energy Commission (AEC) in 1968. While the system has provided a general overview of radiation exposures associated with AEC/ERDA/DOE operations and has satisfied the original intent for a central information system, the need for more detailed information has become evident. The alternatives addressed for a radiation exposure information system were no change in current system, clarification of DOE Order for current system, increased summary information from sites, centralized annual individual dose (exposure) system, and annual dose summary and locator files. A majority of the DOE Ad Hoc Committee has concurred to recommend the annual dose summary and locator files (ADSLF). The acceptance of the ADSLF alternative as the DOE-wide radiation exposure system would give DOE added capability and flexibility in responding to requests for information and would reduce the impact on the sites of special survey requests

  16. External radiation exposure of the public

    International Nuclear Information System (INIS)

    Mehl, J.

    1977-01-01

    Results of several ten thousand measurements on external radiation (outside buildings, in living rooms) are used for illustrating by isodose charts covering the total area of the Federal Republic of Germany the exposure of the public from external radiation originating from natural radiation of the environment. Results of calculations on external radiation exposure of the public due to releases of radioactivity in air from nuclear installations are used for illustrating by coloured isodose charts the exposure of the public in the plant site vicinity. From comparison of the exposure levels it becomes obvious that if exposure levels of several 10 mrem per year are considered to be of real concern to public health, control of natural radoactivity in the environment of man would require more attention than present and foreseeable releases of radioactivity in air from nuclear inst

  17. Occupational radiation exposure to low doses of ionizing radiation and female breast cancer

    International Nuclear Information System (INIS)

    Adelina, P.; Bliznakov, V.; Bairacova, A.

    2003-01-01

    The aim of this study is to examine the relationship between past occupational radiation exposure to low doses of ionizing radiation and cases of diagnosed and registered breast cancer [probability of causation - PC] among Bulgarian women who have used different ionizing radiation sources during their working experience. The National Institute of Health (NIH) in US has developed a method for estimating the probability of causation (PC) between past occupational radiation exposure to low doses of ionizing radiation and cases of diagnosed cancer. We have used this method. A group of 27 women with diagnosed breast cancer has been studied. 11 of them are former workers in NPP - 'Kozloduy', and 16 are from other sites using different sources of ionizing radiation. Analysis was performed for 14 women, for whom full personal data were available. The individual radiation dose for each of them is below 1/10 of the annual dose limit, and the highest cumulative dose for a period of 14 years of occupational exposure is 50,21 mSv. The probability of causation (PC) values in all analyzed cases are below 1%, which confirms the extremely low probability of causation (PC) between past occupational radiation exposure to low doses of ionizing radiation and occurring cases of breast cancer. (orig.)

  18. Exposure to cosmic radiation: a developing major problem in radiation protection

    International Nuclear Information System (INIS)

    Lowder, W.M.; Hajnal, F.

    1992-01-01

    'Full Text:' Cosmic radiation at ground altitudes is usually a relatively minor contributor to human radiation exposure, producing a global collective dose equivalent that is about 10 percent of the total from all natural sources. However, more than a million people living at high altitudes receive annual dose equivalents in excess of 5 mSv. In recent years, there has been increasing concern about the exposure of aircraft flight crews and passengers, for whom annual dose equivalents of up to several mSv have been estimated. Recent EML results indicate the presence of an important high-energy neutron component at jet aircraft altitudes, perhaps producing dose equivalents of the order of 0.1. mSv/h at high latitudes. Finally, space agencies have been long concerned with the potential exposures of astronauts, especially from the rare massive solar flare events. As more people venture into space, this source of human radiation exposure will become increasingly important. Available date on those aspects of cosmic radiation exposure will be reviewed, along with current and anticipated future research activities that may yield and improve assessment of the problem. The question of how such exposures might be controlled will be addressed, but not answered. (author)

  19. Controlling criteria for radiation exposure of astronauts and space workers

    International Nuclear Information System (INIS)

    Katoh, Kazuaki

    1989-01-01

    Space workers likely to suffer from radiation exposure in the outer space are currently limited to the U.S. and Soviet Union, and only a small amount of data and information is available concerning the techniques and criteria for control of radiation exposure in this field. Criteria used in the Soviet Union are described first. The criteria (TRS-75), called the Radiation Safety Criteria for Space Navigation, are tentative ones set up in 1975. They are based on risk assessment. The standard radiation levels are established based on unit flight time: 50rem for 1 month, 80rem for 3 months, 110rem for 6 months and 150rem for 12 months. These are largely different from the emergency exposure limit of 100mSv (10rem) specified in a Japanese law, and the standard annual exposure value of 50mSv (5rem) for workers in nuclear power plants at normal times. For the U.S., J.A. Angelo, Jr., presented a paper titled 'Radiation Protection Issues and Techniques concerning Extended Manned Space Missions' at an IAEA meeting held in 1988. Though the criteria shown in the paper are not formal ones at the national level, similar criteria are expected to be adopted by the nation in the near future. The exposure limits recommended in the paper include a depth dose of 1-4Sv for the whole life span of a worker. (Nogami, K.)

  20. Reduction of radiation exposure in Japanese BWR Nuclear Power Plants

    International Nuclear Information System (INIS)

    Morikawa, Yoshitake

    1995-01-01

    The reduction of occupational exposure to radiation during the annual inspection and maintenance outages of Japanese boiling water reactors (BWR) is one of the most important objectives for stable and reliable operation. It was shown that this radiation exposure is caused by radionuclides, such as Co-60, Co-58 and Mn-54 which are produced from the metal elements Co, Ni, and Fe present in the corrosion products of structural materials that had been irradiated by neutrons. Therefore, to reduce radiation sources and exposures in Japanese BWRs, attempts have been reinforced to remove corrosion products and activated corrosion products from the primary coolant system. This paper describes the progress of the application of these measures to Japanese BWRs. Most Japanese BWR-4 and BWR-5 type nuclear power plants started their commercial operations during the 1970s. With the elapse of time during operations, a problem came to the forefront, namely that occupational radiation exposure during plant outages gradually increased, which obstructed the smooth running of inspections and maintenance work. To overcome this problem, extensive studies to derive effective countermeasures for radiation exposure reduction were undertaken, based on the evaluation of the plants operation data

  1. Reduction of radiation exposure in Japanese BWR Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Morikawa, Yoshitake [ISOGO Nuclear Engineering Center, Yokohama (Japan)

    1995-03-01

    The reduction of occupational exposure to radiation during the annual inspection and maintenance outages of Japanese boiling water reactors (BWR) is one of the most important objectives for stable and reliable operation. It was shown that this radiation exposure is caused by radionuclides, such as Co-60, Co-58 and Mn-54 which are produced from the metal elements Co, Ni, and Fe present in the corrosion products of structural materials that had been irradiated by neutrons. Therefore, to reduce radiation sources and exposures in Japanese BWRs, attempts have been reinforced to remove corrosion products and activated corrosion products from the primary coolant system. This paper describes the progress of the application of these measures to Japanese BWRs. Most Japanese BWR-4 and BWR-5 type nuclear power plants started their commercial operations during the 1970s. With the elapse of time during operations, a problem came to the forefront, namely that occupational radiation exposure during plant outages gradually increased, which obstructed the smooth running of inspections and maintenance work. To overcome this problem, extensive studies to derive effective countermeasures for radiation exposure reduction were undertaken, based on the evaluation of the plants operation data.

  2. Monitoring occupational exposure to ionizing radiation

    Energy Technology Data Exchange (ETDEWEB)

    Button, J.B.C. [Radiation Safety Consultancy, Engadine, NSW (Australia)

    1997-12-31

    A brief overview is presented of methods of monitoring occupational exposure to ionizing radiation together with reasons for such monitoring and maintaining dose histories of radiation occupationally exposed persons. The various Australian providers of external radiation monitoring services and the types of dosemeters they supply are briefly described together with some monitoring results. Biological monitoring methods, are used to determine internal radiation dose. Whole body monitors, used for this purpose are available at Australian Radiation Lab., ANSTO and a few hospitals. Brief mention is made of the Australian National Radiation Dose Register and its objectives. 8 refs., 9 tabs.

  3. Monitoring occupational exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Button, J.B.C.

    1997-01-01

    A brief overview is presented of methods of monitoring occupational exposure to ionizing radiation together with reasons for such monitoring and maintaining dose histories of radiation occupationally exposed persons. The various Australian providers of external radiation monitoring services and the types of dosemeters they supply are briefly described together with some monitoring results. Biological monitoring methods, are used to determine internal radiation dose. Whole body monitors, used for this purpose are available at Australian Radiation Lab., ANSTO and a few hospitals. Brief mention is made of the Australian National Radiation Dose Register and its objectives

  4. Radiation exposure and protection during angiography

    Energy Technology Data Exchange (ETDEWEB)

    Biazzi, L; Garbagna, P [Pavia Univ. (Italy)

    1979-05-01

    The authors describe the radiological techniques during angiography examinations in their hospital. For every technique they measured the radiation exposure and dose to the staff of doctors, assistants and nurses in their standard positions in the room and the radiation dose at various points on their bodies. The results are critically discussed and alternative protection devices are analysed, since there are many difficulties concerning the employ of usual radiation protection systems. Cardiologists, above all, are given some recommendations to reduce radiation exposure without prejudicing the exam results.

  5. Radiation exposure and protection during angiography

    International Nuclear Information System (INIS)

    Biazzi, L.; Garbagna, P.

    1979-01-01

    The authors describe the radiological techniques during angiography examinations in their hospital. For every technique they measured the radiation exposure and dose to the staff of doctors, assistants and nurses in their standard positions in the room and the radiation dose at various points on their bodies. The results are critically discussed and alternative protection devices are analysed, since there are many difficulties concerning the employ of usual radiation protection systems. Cardiologists, above all, are given some recomandations to reduce radiation exposure without prejudicing the exam results [fr

  6. Radiation exposure of children during cardiac catheterisation

    International Nuclear Information System (INIS)

    Popp, W.

    1979-01-01

    It is well known that in adults, cardiac catheterisation involves the highest possible radiation exposure for a single examination. The paper now investigates the radiation exposure in paediatric cardiac cathetrisations. Dosimeters attached to the children during the examination were used as well as phantom measurements under the conditions of cardiac catheterisation. With the aid of the phantom, also the total energy absorption during an examination procedure was determined. This value was estimated to be 80 mJ. In spite of the high individual exposure, the contribution to the population exposure is low due to the small number of cardiac catheterisations. (orig.) 891 AJ/orig. 892 MKO [de

  7. Occupational radiation exposure in Germany in 2006. Report of the radiation protection register

    International Nuclear Information System (INIS)

    Frasch, G.; Fritzsche, E.; Kammerer, L.; Karofsky, R.; Spiesl, J.; Stegemann, R.

    2008-06-01

    In Germany, persons occupationally exposed to radiation are monitored by several official dosimetric services who transmit their records about individual radiation doses to the Radiation Protection Register of the Federal Office for Radiation Protection (BfS). The number of dose recordings reported to the Radiation Protection Register has annually increased to more than three million records per year and thus accumulated to more than 34 million dose records at the end of 2006. The purpose of the Radiation Protection Register is to supervise the keeping of the dose limits by each radiation worker and to monitor the compliance with the radiation protection principle ''optimisation'' by performing detailed annual statistical analyses of the monitored persons and their radiation exposure. Amongst others, the annual report of the Radiation Protection Register provides information about status and development of occupational radiation exposure in Germany. In 2006, about 312,000 workers were monitored with dosimeters for occupational radiation exposure. About 18 % of the monitored persons received a measurable personal dose. The average annual dose of these exposed workers was 0.75 mSv. This value is the lowest average annual dose since dose monitoring for occupational worker was introduced. It remains below the dose limit of 1 mSv for the general public and amounts only 4 % of the annual dose limit of 20 mSv for radiation workers. Since 2003 aircraft crew personnel is subject to dose monitoring if it is employed in accordance with the German employment act and likely to receive an effective dose of at least 1 mSv per year from cosmic radiation during flight operation. This accounts for about 33.000 pilots and flight attendants. 45 airlines report the monthly accumulated dose values of their personnel via the Federal Office for Civil Aviation (''Luftfahrt-Bundesamt, LBA'') to the BfS. The collective dose of the aircraft crew personnel is 71 Person-Sv and thus

  8. Exposures to natural radiation in Switzerland

    International Nuclear Information System (INIS)

    Murith, Ch.; Gurtner, A.

    1999-01-01

    The exposure of human beings to ionising radiation from natural sources is a continuing and inescapable feature of life on earth. There are two main sources that contribute to this exposure: high-energy cosmic-ray particles incident to the earth's atmosphere and radioactive nuclides that originated in the earth's crust and are present everywhere in the environment, including human body itself. Both external and internal exposures to humans arise from these sources. Exposures to natural radiation sources in Switzerland and some of their variations are here summarised and the resulting effective doses are compared to those from man-made sources exposures. It results that the natural background exposures are more significant for the population than most exposures to man-made sources. (authors)

  9. Health consequences of ionizing radiation exposure

    International Nuclear Information System (INIS)

    Dalci, D.; Dorter, G.; Guclu, I.

    2004-01-01

    The increasing use of ionizing radiations all over the world induces an ever increasing interest of the professionals as well as of the whole society in health protection and the risk due to these practices. Shortly after its discovery, it was recognized that ionizing radiation can have adverse health effects and knowledge of its detrimental effects has accumulated. The fact that ionizing radiation produces biological damage has been known for many years. The biological effects of ionizing radiation for radiation protection considerations are grouped into two categories: The deterministic and the stochastic ones. Deterministic radiation effects can be clinically diagnosed in the exposed individual and occur when above a certain 'threshold' an appropriately high dose is absorbed in the tissues and organs to cause the death of a large number of cells and consequently to impair tissue or organ functions early after exposure. A clinically observable biological effect (Acute Radiation Syndromes, ARS) that occurs days to months after an acute radiation dose. ARS is a complex of acute injury manifestations that occur after a sufficiently large portion of a person's body is exposed to a high dose of ionizing radiation. Such irradiation initially injures all organs to some extent, but the timing and extent of the injury manifestations depend upon the type, rate, and dose of radiation received. Stochastic radiation effects are the chronic effects of radiation result from relatively low exposure levels delivered over long periods of time. These are sort of effects that might result from occupational exposure, or to the background exposure levels (includes radioactive pollution). Such late effects might be the development of malignant (cancerous) disease and of the hereditary consequences. These effects may be observed many years after the radiation exposure. There is a latent period between the initial radiation exposure and the development of the biological effect. In this

  10. Electromagnetic radiation-2450 MHz exposure causes cognition ...

    Indian Academy of Sciences (India)

    83

    Electromagnetic radiation-2450 MHz exposure causes cognition deficit with mitochondrial. 1 ... decrease in levels of acetylcholine, and increase in activity of acetyl ...... neuronal apoptosis and cognitive disturbances in sevoflurane or propofol ...

  11. Control of radiation exposure (principles and methods)

    International Nuclear Information System (INIS)

    Agwimah, R. I.

    1999-01-01

    Biological risks are directly related to the tissue radiation dose, so it is very important to maintain personnel doses as low as realistically possible. This goal can be achieved by minimizing internal contamination and external exposure to radioactive sources

  12. Occupational radiation exposure in nuclear medicine

    International Nuclear Information System (INIS)

    Gloebel, B.; Muth, H.; Keller, K.D.; Hector, G.; Lehnen, H.

    1982-01-01

    In a large hospital (University Hospital, Homburg/Saar, 2000 beds) the use of radionuclides was determined with the aim of a balance of the radionuclide flow through the clinic and the resulting radiation exposure for the persons involved. (author)

  13. Annual individual doses for personnel dealing with ionizing radiation sources

    International Nuclear Information System (INIS)

    Poplavskij, K.K.

    1982-01-01

    Data on annual individual doses for personnel of national economy enterprises, research institutes, high schools, medical establishments dealing with ionizing radiation sources are presented. It is shown that radiation dose for the personnel constitutes only shares of standards established by sanitary legislation. Numeral values of individual doses of the personnel are determined by the type, character and scope of using ionizing radiation sources

  14. Estimation of effective dose to public from external exposure to natural background radiation in saudi arabia

    International Nuclear Information System (INIS)

    Khalid, A. A.

    2003-01-01

    The effective dose values in sixteen cities in Saudi Arabia due to external exposure to natural radiation were evaluated. These doses are based on natural background components including external exposure to terrestrial radiation and cosmic rays. The importance of evaluating the effective dose to the public due to external exposure to natural background radiation lies in its epidemiological and dosimetric importance and in forming a basis for the assessment of the level of radioactive contamination or pollution in the environment in the future. The exposure to terrestrial radiation was measured using thermoluminescent dosimeters (TLD). The exposure from cosmic radiation was determined using empirical correlation. The values evaluated for the total annual effective dose in all cities were within the world average values. The highest total annual effective dose measured in Al-Khamis city was 802 μSv/y, as compared to 305 μSv/y in Dammam city, which was considered the lowest value

  15. Radiation exposure and management of medical employes

    International Nuclear Information System (INIS)

    Yamamoto, Chiaki

    1981-01-01

    Medical employes handling medical radiation are increasing in recent years. In connection with the radiation exposure management, it was surveyed how much their cumulative exposure doses are and how many employes distribute in respective exposure levels. The medical employes surveyed are physicians, radiation technicians and nurses, working in the hospitals of educational institutions. The period of survey is every three years, from 1962 to 1977. For X-ray and ν-ray, respectively, the yearly cumulative exposure doses were measured by film badges, stepwise starting from below 500 mrem upward to over 5000 mrem; for the respective groups of employes, the percentage in each dose level was shown. The percentage in the level below 500 mrem was the largest in all groups, and in both X-ray and ν-ray, the percentages in higher levels decreased sharply to less than 7%. The exposure management has been improved in recent years. (J.P.N.)

  16. Radiation exposure and management of medical employes

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, C [Nagoya Univ. (Japan)

    1981-11-01

    Medical employes handling medical radiation are increasing in recent years. In connection with the radiation exposure management, it was surveyed how much their cumulative exposure doses are and how many employes distribute in respective exposure levels. The medical employes surveyed are physicians, radiation technicians and nurses, working in the hospitals of educational institutions. The period of survey is every three years, from 1962 to 1977. For X-ray and ..gamma..-ray, respectively, the yearly cumulative exposure doses were measured by film badges, stepwise starting from below 500 mrem upward to over 5000 mrem; for the respective groups of employes, the percentage in each dose level was shown. The percentage in the level below 500 mrem was the largest in all groups, and in both X-ray and ..gamma..-ray, the percentages in higher levels decreased sharply to less than 7%. The exposure management has been improved in recent years.

  17. Occupational radiation exposure to norms in a gold mine

    International Nuclear Information System (INIS)

    Darko, E. O.; Tetteh, G. K.; Akaho, E. H. K.

    2005-01-01

    Preliminary studies have been conducted into the occupational radiation exposure to NORMS from surface and underground mining operations in a gold mine in the Ashanti Region of Ghana. A brief description of the methods and instrumentation is presented. The annual effective dose has been estimated to be 0.26 ± 0.11 mSv for surface mining and 1.83 ± 0.56 mSv for the underground mines using the ICRP dose calculation method. The results obtained are found to be within the allowable limit of 20 mSv per annum for occupational exposure control recommended by the ICRP. (authors)

  18. Occupational cosmic radiation exposure and cancer in airline cabin crew.

    Energy Technology Data Exchange (ETDEWEB)

    Kojo, K.

    2013-03-15

    Cosmic radiation dose rates are considerably higher at cruising altitudes of airplanes than at ground level. Previous studies have found increased risk of certain cancers among aircraft cabin crew, but the results are not consistent across different studies. Despite individual cosmic radiation exposure assessment is important for evaluating the relation between cosmic radiation exposure and cancer risk, only few previous studies have tried to develop an exposure assessment method. The evidence for adverse health effects in aircrews due to ionizing radiation is inconclusive because quantitative dose estimates have not been used. No information on possible confounders has been collected. For an occupational group with an increased risk of certain cancers it is very important to assess if the risk is related to occupational exposure. The goal of this thesis was to develop two separate retrospective exposure assessment methods for occupational exposure to cosmic radiation. The methods included the assessment based on survey on flight histories and based on company flight timetables. Another goal was to describe the cancer incidence among aircraft cabin crew with a large cohort in four Nordic countries, i.e., Finland, Iceland, Norway, and Sweden. Also the contribution of occupational as well as non-occupational factors to breast and skin cancer risk among the cabin crew was studied with case-control studies. Using the survey method of cosmic radiation exposure assessment, the median annual radiation dose of Finnish airline cabin crew was 0.6 milliSievert (mSv) in the 1960s, 3.3 mSv in the 1970s, and 3.6 mSv in the 1980s. With the flight timetable method, the annual radiation dose increased with time being 0.7 mSv in the 1960 and 2.1 mSv in the 1995. With the survey method, the median career dose was 27.9 mSv and with the timetable method 20.8 mSv. These methods provide improved means for individual cosmic radiation exposure assessment compared to studies where cruder

  19. Occupational cosmic radiation exposure and cancer in airline cabin crew

    International Nuclear Information System (INIS)

    Kojo, K.

    2013-03-01

    Cosmic radiation dose rates are considerably higher at cruising altitudes of airplanes than at ground level. Previous studies have found increased risk of certain cancers among aircraft cabin crew, but the results are not consistent across different studies. Despite individual cosmic radiation exposure assessment is important for evaluating the relation between cosmic radiation exposure and cancer risk, only few previous studies have tried to develop an exposure assessment method. The evidence for adverse health effects in aircrews due to ionizing radiation is inconclusive because quantitative dose estimates have not been used. No information on possible confounders has been collected. For an occupational group with an increased risk of certain cancers it is very important to assess if the risk is related to occupational exposure. The goal of this thesis was to develop two separate retrospective exposure assessment methods for occupational exposure to cosmic radiation. The methods included the assessment based on survey on flight histories and based on company flight timetables. Another goal was to describe the cancer incidence among aircraft cabin crew with a large cohort in four Nordic countries, i.e., Finland, Iceland, Norway, and Sweden. Also the contribution of occupational as well as non-occupational factors to breast and skin cancer risk among the cabin crew was studied with case-control studies. Using the survey method of cosmic radiation exposure assessment, the median annual radiation dose of Finnish airline cabin crew was 0.6 milliSievert (mSv) in the 1960s, 3.3 mSv in the 1970s, and 3.6 mSv in the 1980s. With the flight timetable method, the annual radiation dose increased with time being 0.7 mSv in the 1960 and 2.1 mSv in the 1995. With the survey method, the median career dose was 27.9 mSv and with the timetable method 20.8 mSv. These methods provide improved means for individual cosmic radiation exposure assessment compared to studies where cruder

  20. Radiation exposure in nuclear medicine: real-time measurement

    International Nuclear Information System (INIS)

    Sylvain, Iara; Bok, Bernard; X. Bichat University, Paris

    2002-01-01

    French regulations have introduced the use of electronic dosimeters for personnel monitoring of workers. In order to evaluate the exposure from diagnostic procedures to nuclear medicine staff, individual whole-body doses were measured daily with electronic (digital) personal dosimeters during 20 consecutive weeks and correlated with the work load of each day. Personal doses remained always below 20 mu Sv/d under normal working conditions. Radiation exposure levels were highest to tech staff, nurses and stretcher-bearers. The extrapolated annual cumulative doses for all staff remained less than 10% of the maximum legal limit for exposed workers (2 mSv/yr). Electronic dosimeters are not technically justified for routine survey of staff. The high sensitivity and immediate reading of electronic semiconductor dosimeters may become very useful for exposure control under risky working conditions. It may become an important help for optimising radiation protection. (author)

  1. Saeteilyn kaeyttoe ja muu saeteilytoiminta. Vuosiraportti 1999; Radiation usage and other radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Rantanen, E. [ed.

    2000-05-01

    At the end of 1999, there were 1,753 valid safety licenses in Finland for the use of radiation. In addition, there were 2,054 responsible parties for dental x-ray diagnostics. The registry of STUK - Radiation and Nuclear Safety Authority listed 13,687 radiation sources and 278 radionuclide laboratories. The import of radioactive substances amounted to 7 448,000 GBq and export to 18,300 GBq. Short-lived radionuclides produced in Finland amounted to 52,500 GBq. In the year 1999 there were 10,601 workers monitored for radiation exposure at 1,187 work sites. Of these employees, 21% received an annual dose exceeding the recording level. The annual effective dose limit was not exceeded. The total dose recorded in the dose registry (sum of the individual dosemeter readings) was 4.7 Sv in 1999. During the year radon was monitored at 300 companies.

  2. Exposure of the orthopaedic surgeon to radiation

    Energy Technology Data Exchange (ETDEWEB)

    Katoh, Kiyonobu; Koga, Takamasa; Matsuzaki, Akio; Kido, Masaki; Satoh, Tetsunori [Fukuoka Univ. (Japan). Chikushi Hospital

    1995-09-01

    We monitored the amount of radiation received by surgeons and assistants during surgery carried out with fluoroscopic assistance. The radiation was monitored with the use of MYDOSE MINIX PDM107 made by Aloka Co. Over a one year period from Aug 20, 1992 to Aug 19, 1993, a study was undertaken to evaluate exposure of the groin level to radiation with or without use of the lead apron during 106 operation (Group-1). In another group, radiation was monitored at the breast and groin level outside of the lead apron during 39 operations (Group-2). In Group-1, the average exposure per person during one year was 46.0 {mu}SV and the average exposure for each procedure was 1.68 {mu}SV. The use of the lead apron affirmed its protective value; the average radiation dose at the groin level out-side of the apron was 9.11 {mu}SV, the measured dose beneath the apron 0.61 {mu}SV. The average dose of exposure to the head, breast at groin level outside of the lead apron, were 7.68 {mu}SV, 16.24 {mu}SV, 32.04 {mu}SV respectively. This study and review of the literature indicate that the total amount of radiation exposure during surgery done with fluoroscopic control remains well within maximum exposure limits. (author).

  3. Exposure of the orthopaedic surgeon to radiation

    International Nuclear Information System (INIS)

    Katoh, Kiyonobu; Koga, Takamasa; Matsuzaki, Akio; Kido, Masaki; Satoh, Tetsunori

    1995-01-01

    We monitored the amount of radiation received by surgeons and assistants during surgery carried out with fluoroscopic assistance. The radiation was monitored with the use of MYDOSE MINIX PDM107 made by Aloka Co. Over a one year period from Aug 20, 1992 to Aug 19, 1993, a study was undertaken to evaluate exposure of the groin level to radiation with or without use of the lead apron during 106 operation (Group-1). In another group, radiation was monitored at the breast and groin level outside of the lead apron during 39 operations (Group-2). In Group-1, the average exposure per person during one year was 46.0 μSV and the average exposure for each procedure was 1.68 μSV. The use of the lead apron affirmed its protective value; the average radiation dose at the groin level out-side of the apron was 9.11 μSV, the measured dose beneath the apron 0.61 μSV. The average dose of exposure to the head, breast at groin level outside of the lead apron, were 7.68 μSV, 16.24 μSV, 32.04 μSV respectively. This study and review of the literature indicate that the total amount of radiation exposure during surgery done with fluoroscopic control remains well within maximum exposure limits. (author)

  4. Cancer risks after radiation exposures

    International Nuclear Information System (INIS)

    Voelz, G.L.

    1980-01-01

    A general overview of the effects of ionizing radiation on cancer induction is presented. The relationship between the degree of risk and absorbed dose is examined. Mortality from radiation-induced cancer in the US is estimated and percentages attributable to various sources are given

  5. Ocular ultraviolet radiation exposure of welders.

    Science.gov (United States)

    Tenkate, Thomas D

    2017-05-01

    reference made to the average solar UVR exposure of a Danish outdoor worker being 22 400 J/m 2 per year (min-max 5400 - 66 900 J/m 2 per year) (10). For comparison, taking the mean 8-hour UVR dose within the welding helmets as 15 mJ/cm2 (3), this would equate to an annual ocular/facial UVR dose for welders of 37 500 J/m 2 (at 5 days/week, 50 weeks/year). Even though this value is weighted for the ACGIH action spectrum, and the value for the Danish outdoor workers is weighted for the erythema spectrum, it provides a reasonable comparison and indicates that welders are likely to receive comparable facial/ocular UVR doses to outdoor workers. Slagor et al also state that "it is inferred that welders are not exposed to large amounts of UVR during their work life, in spite of the photokeratoconjunctivitis incidents" (1, p451). I would propose that the UVR dosimetry studies described above (2, 3), taken together with studies on UVR emissions of welding arcs which show that the MPE for many welding arcs can be exceeded in a matter of seconds (11-13), indicate that welders do work in an extreme UVR environment. These studies also suggest that welders are regularly exposed to levels of UVR that exceed the occupational exposure limits at body sites which are thought to be protected (eg, face and eyes) (2, 3). When these exposures are further considered in light of the range of eye conditions reported to occur in welders (14-17), the importance of implementing a comprehensive eye safety strategy for welders and all workers in a welding environment is imperative. References 1. Slagor RM, La Cour M, Bonde JP. The risk of cataract in relation to metal arc welding. Scan J Work Environ Health. 2016;42(5):447-53. https://doi.org/10.5271/sjweh.3572.  2. Shehade SA, Roberts PJ, Diffey BF, Foulds IS. Photodermatitis due to spot welding. Br J Dermatol. 1987;117:117-9. https://doi.org/10.1111/j.1365-2133.1987.tb04100.x.  3. Tenkate TD, Collins MJ. Personal ultraviolet radiation exposure of

  6. Natural background radiation exposures world-wide

    International Nuclear Information System (INIS)

    Bennett, B.G.

    1993-01-01

    The average radiation dose to the world's population from natural radiation sources has been assessed by UNSCEAR to be 2.4 mSv per year. The components of this exposure, methods of evaluation and, in particular, the variations in the natural background levels are presented in this paper. Exposures to cosmic radiation range from 0.26 mSv per year at sea level to 20 times more at an altitude of 6000 m. Exposures to cosmogenic radionuclides ( 3 H, 14 C) are relatively insignificant and little variable. The terrestrial radionuclides 40 K, 238 U, and 232 Th and the decay products of the latter two constitute the remainder of the natural radiation exposure. Wide variations in exposure occur for these components, particularly for radon and its decay products, which can accumulate to relatively high levels indoors. Unusually high exposures to uranium and thorium series radionuclides characterize the high natural background areas which occur in several localized regions in the world. Extreme values in natural radiation exposures have been estimated to range up to 100 times the average values. (author). 15 refs, 3 tabs

  7. Cosmic radiation exposure to airline flight passenger

    International Nuclear Information System (INIS)

    Momose, Mitsuhiro

    2000-01-01

    At the high altitudes, airline flight passengers can be exposed to some levels of cosmic radiation. The purpose of this study was to quantify this radiation exposure. Cosmic radiation was measured during 5 flights using a personal dosimeter (PDM-102, Aloka). Cosmic radiation equivalent dose rates ranged from 0.7 to 1.43 microsieverts per hour, the average rate was 1.08. For the passenger who travels only occasionally, the cosmic radiation levels are well below occupational limits, and the risks are extremely small. (author)

  8. Cosmic radiation exposure to airline flight passenger

    Energy Technology Data Exchange (ETDEWEB)

    Momose, Mitsuhiro [Shinshu Univ., Matsumoto, Nagano (Japan). School of Medicine

    2000-08-01

    At the high altitudes, airline flight passengers can be exposed to some levels of cosmic radiation. The purpose of this study was to quantify this radiation exposure. Cosmic radiation was measured during 5 flights using a personal dosimeter (PDM-102, Aloka). Cosmic radiation equivalent dose rates ranged from 0.7 to 1.43 microsieverts per hour, the average rate was 1.08. For the passenger who travels only occasionally, the cosmic radiation levels are well below occupational limits, and the risks are extremely small. (author)

  9. Bases for establishing radiation exposure limits

    International Nuclear Information System (INIS)

    Pochin, E.E.

    1977-01-01

    It is an essential requirement of good radiation protection that all unnecessary exposure of people should be avoided and that any necessary exposure, whether of workers or of members of the general public, should be minimised. It is, however, an additional requirement that such necessary exposures should not exceed certain stated limits. These principles are based on the possibility that even the smallest exposures may involve some risk of harm, that any risk of harm should be justifiable by the circumstances necessitating it, and that risk should always be limited to an appropriately low level. The bases for establishing exposure limits must therefore involve an assessment of the risk involved in any form of radiation exposure, and an opinion as to the degree of safety that should be ensured in circumstances which necessitate any occupational or public exposure to radiation. There is increasing quantitative evidence on the frequency on which harm, and particularly the induction of malignancies, may be caused in people exposed to radiation at high doses; and somewhat clearer bases than previously for inferring the possible frequencies at low doses. It is therefore easier to assess the degree of safety ensured by restricting radiation exposure to particular levels. The degree of safety which should be regarded as appropriate in different circumstances remains a matter for review, but suggestions are made as to levels which would be advocated by informed opinion, and the exposure limits which would correspond to these. It is clear also that a comparable degree of safety should be ensured whether the radiation exposure involves the whole body more of less uniformly, or individual tissues or organs selectively. Increasing epidemiological evidence is available on the relative sensitivity to radiation induction of malignancies in a number of organs, and to the apparently much lower sensitivity of other organs; and experimental evidence in animals allows a comparable

  10. Occupational radiation exposure risks: a review

    Energy Technology Data Exchange (ETDEWEB)

    Besar, Idris [PUSPATI, Selangor (Malaysia)

    1984-06-01

    This paper presents a review of the health risk as a result of exposure to ionizing radiation. A comparison of occupational risk among workers exposed to radiological and nonradiological harms are also presented. This comparison shows that radiation workers exposed to the current nuclear industry average of 3.4 mSv. per year are among the safest of all industry groupings.

  11. Valuing the radiation detriment of occupational exposure

    International Nuclear Information System (INIS)

    Robb, J.D.; Crick, M.J.

    1989-01-01

    The implications of changes in the radiation risk estimates on the valuation of radiation detriment for use in cost-benefit analysis are being considered at the National Radiological Protection Board. This paper discusses the pertinent factors that are currently being considered for further investigation. An example of relevance to occupational exposure is detailed. (author)

  12. Occupational radiation exposure risks: a review

    International Nuclear Information System (INIS)

    Idris Besar

    1984-01-01

    This paper presents a review of the health risk as a result of exposure to ionizing radiation. A comparison of occupational risk among workers exposed to radiological and nonradiological harms are also presented. This comparison shows that radiation workers exposed to the current nuclear industry average of 3.4 mSv. per year are among the safest of all industry groupings. (author)

  13. Non-occupational exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Snihs, J.O.

    1985-01-01

    An overview of non-occupational exposure is presented. The special problems in connection with assessments of collective doses (time, geographical extension, cut-off, uncertainties) are discussed. Examples of methods and principles for monitoring and dose assessments used for various sources of radiation are given and data on public exposure are presented and discussed. (author)

  14. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-06-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the US Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  15. Radiation exposures in reprocessing facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Hayes, G.; Caldwell, R.D.; Hall, R.M.

    1979-01-01

    Two large reprocessing facilities have been operating at the Savannah River Plant since 1955. The plant, which is near Aiken, South Carolina, is operated for the U.S. Department of Energy by the Du Pont Company. The reprocessing facilities have a work force of approximately 1,800. The major processes in the facilities are chemical separations of irradiated material, plutonium finishing, and waste management. This paper presents the annual radiation exposure for the reprocessing work force, particularly during the period 1965 through 1978. It also presents the collective and average individual annual exposures for various occupations including operators, mechanics, electricians, control laboratory technicians, and health physicists. Periodic and repetitive work activities that result in the highest radiation exposures are also described. The assimilation of radionuclides, particularly plutonium, by the work force is reviewed. Methods that have been developed to minimize the exposure of reprocessing personnel are described. The success of these methods is illustrated by experience - there has been no individual worker exposure of greater than 3.1 rems per year and only one plutonium assimilation greater than the maximum permissible body burden during the 24 years of operation of the facilities

  16. Applied physics of external radiation exposure dosimetry and radiation protection

    CERN Document Server

    Antoni, Rodolphe

    2017-01-01

    This book describes the interaction of living matter with photons, neutrons, charged particles, electrons and ions. The authors are specialists in the field of radiation protection. The book synthesizes many years of experiments with external radiation exposure in the fields of dosimetry and radiation shielding in medical, industrial and research fields. It presents the basic physical concepts including dosimetry and offers a number of tools to be used by students, engineers and technicians to assess the radiological risk and the means to avoid them by calculating the appropriate shields. The theory of radiation interaction in matter is presented together with empirical formulas and abacus. Numerous numerical applications are treated to illustrate the different topics. The state of the art in radiation protection and dosimetry is presented in detail, especially in the field of simulation codes for external exposure to radiation, medical projects and advanced research. Moreover, important data spread in differ...

  17. Radiation exposure modeling and project schedule visualization

    International Nuclear Information System (INIS)

    Jaquish, W.R.; Enderlin, V.R.

    1995-10-01

    This paper discusses two applications using IGRIP (Interactive Graphical Robot Instruction Program) to assist environmental remediation efforts at the Department of Energy (DOE) Hanford Site. In the first application, IGRIP is used to calculate the estimated radiation exposure to workers conducting tasks in radiation environments. In the second, IGRIP is used as a configuration management tool to detect interferences between equipment and personnel work areas for multiple projects occurring simultaneously in one area. Both of these applications have the capability to reduce environmental remediation costs by reducing personnel radiation exposure and by providing a method to effectively manage multiple projects in a single facility

  18. Mean annual and collective radiation doses of Perm' province personnel

    International Nuclear Information System (INIS)

    Poplavskij, K.K.; Rotenberg, L.I.

    1978-01-01

    The average annual and collective doses of radiation received by personnel of radiologic facilities and by the population of the region under study as a whole are estimated. Tabular data on radiation loads are presented according to the age and sex of personnel and to the type of radiation sources used. The procedure employed in this study allows one to evaluate objectively the conditions of work with sources of ionizing radiation

  19. Integrated occupational radiation exposure information system

    International Nuclear Information System (INIS)

    Hunt, H.W.

    1983-06-01

    The integrated (Occupational Radiation Exposure) data base information system has many advantages. Radiation exposure information is available to operating management in a more timely manner and in a more flexible mode. The ORE system has permitted the integration of scattered files and data to be stored in a more cost-effective method that permits easy and simultaneous access by a variety of users with different data needs. The external storage needs of the radiation exposure source documents are several orders of magnitude less through the use of the computer assisted retrieval techniques employed in the ORE system. Groundwork is being layed to automate the historical files, which are maintained to help describe the radiation protection programs and policies at any one point in time. The file unit will be microfilmed for topical indexing on the ORE data base

  20. Atmospheric Ionizing Radiation and Human Exposure

    Science.gov (United States)

    Wilson, John W.; Mertens, Christopher J.; Goldhagen, Paul; Friedberg, W.; DeAngelis, G.; Clem, J. M.; Copeland, K.; Bidasaria, H. B.

    2005-01-01

    Atmospheric ionizing radiation is of interest, apart from its main concern of aircraft exposures, because it is a principal source of human exposure to radiations with high linear energy transfer (LET). The ionizing radiations of the lower atmosphere near the Earth s surface tend to be dominated by the terrestrial radioisotopes. especially along the coastal plain and interior low lands, and have only minor contributions from neutrons (11 percent). The world average is substantially larger but the high altitude cities especially have substantial contributions from neutrons (25 to 45 percent). Understanding the world distribution of neutron exposures requires an improved understanding of the latitudinal, longitudinal, altitude and spectral distribution that depends on local terrain and time. These issues are being investigated in a combined experimental and theoretical program. This paper will give an overview of human exposures and describe the development of improved environmental models.

  1. Atmospheric Ionizing Radiation and Human Exposure

    Science.gov (United States)

    Wilson, J. W.; Goldhagen, P.; Friedberg, W.; DeAngelis, G.; Clem, J. M.; Copeland, K.; Bidasaria, H. B.

    2004-01-01

    Atmospheric ionizing radiation is of interest, apart from its main concern of aircraft exposures, because it is a principal source of human exposure to radiations with high linear energy transfer (LET). The ionizing radiations of the lower atmosphere near the Earth s surface tend to be dominated by the terrestrial radioisotopes especially along the coastal plain and interior low lands and have only minor contributions from neutrons (11 percent). The world average is substantially larger but the high altitude cities especially have substantial contributions from neutrons (25 to 45 percent). Understanding the world distribution of neutron exposures requires an improved understanding of the latitudinal, longitudinal, altitude and spectral distribution that depends on local terrain and time. These issues are being investigated in a combined experimental and theoretical program. This paper will give an overview of human exposures and describe the development of improved environmental models.

  2. Routine medicare and radiation exposure. Introductory remarks

    International Nuclear Information System (INIS)

    Hirata, Hideki; Saito, Tsutomu

    2013-01-01

    As an introduction of the title series, outlines of radiation in physics, chemistry, biochemistry, biological effect and protection are explained from the clinical doctors' aspect of routine medicare, and of radiation exposure in which people's interest is raised after the Fukushima Nuclear Power Plant Accident in 2011. For physics, ionizing effects of radiation are described in relation to its quantum energy transfer and its medical utilization like imaging and radiotherapy. Then mentioned in brief is the radiation from elements consisting of human body, cosmic ray and background radiation from the earth, with reference to natural and standardized limits of exposure doses. Radiations from 226 Rn and 40 K are explained as an instance of environmental natural sources together with the concepts of radioactive decay series/scheme, of internal exposure, of hazard like double strand break (DSB) and of medical use such as boron neutron capture therapy (BNCT). For an artifact radiation source, shown are fission products of 235 U by neutron, first yielded in 1945. Evidence of evolution in biochemical repair mechanisms of DSB is explained with a comparison of irradiated drosophila mutation where linear non-threshold (LNT) hypothesis is proposed, and human non-homologous end joining and homologous recombination. Historical process of occupational, medical, public exposures and their protection is finally described from the discovery of X-ray in 1895 to the first ICRP publication in 1958 via the A-bomb explosion in 1945. (T.T.)

  3. Risks and management of radiation exposure.

    Science.gov (United States)

    Yamamoto, Loren G

    2013-09-01

    High-energy ionizing radiation is harmful. Low-level exposure sources include background, occupational, and medical diagnostics. Radiation disaster incidents include radioactive substance accidents and nuclear power plant accidents. Terrorism and international conflict could trigger intentional radiation disasters that include radiation dispersion devices (RDD) (a radioactive dirty bomb), deliberate exposure to industrial radioactive substances, nuclear power plant sabotage, and nuclear weapon detonation. Nuclear fissioning events such as nuclear power plant incidents and nuclear weapon detonation release radioactive fallout that include radioactive iodine 131, cesium 137, strontium 90, uranium, plutonium, and many other radioactive isotopes. An RDD dirty bomb is likely to spread only one radioactive substance, with the most likely substance being cesium 137. Cobalt 60 and strontium 90 are other RDD dirty bomb possibilities. In a radiation disaster, stable patients should be decontaminated to minimize further radiation exposure. Potassium iodide (KI) is useful for iodine 131 exposure. Prussian blue (ferric hexacyanoferrate) enhances the fecal excretion of cesium via ion exchange. Ca-DTPA (diethylenetriaminepentaacetic acid) and Zn-DTPA form stable ionic complexes with plutonium, americium, and curium, which are excreted in the urine. Amifostine enhances chemical and enzymatic repair of damaged DNA. Acute radiation sickness ranges in severity from mild to lethal, which can be assessed by the nausea/vomiting onset/duration, complete blood cell count findings, and neurologic symptoms.

  4. Radiation Exposure Reduction to Brachytherapy Staff By Using Remote Afterloading

    International Nuclear Information System (INIS)

    Attalla, E.M.

    2005-01-01

    The radiation exposures to the personnel staff from patients with brachytherapy implants in a brachytherapy service were reviewed. Exposures to the brachytherapy personnel, as determined by Thermoluminescence Dosimeter (TLD) monitors, indicates a four-fold reduction in exposures after the implantation of the use of remote afterloading devices. Quarterly TLD monitor data for seven quarters prior to the use of remote afterloading devices demonstrate an average projected annual dose equivalent to the brachytherapy staff of 2543 Μ Sv. After the implantation of the remote afterloading devices, the quarterly TLD monitor data indicate an average dose equivalent per person of 153 Μ Sv. This is 76% reduction in exposure to brachytherapy personnel with the use of these devices

  5. Occupational radiation exposure in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    1979-01-01

    Full text: This symposium forms an essential part of the continuing tradition of subjecting nuclear energy to periodic review to assess the adequacy of radiation protection practices and experiences and to identify those areas needing further study and development. Specifically, the symposium focused on a review of statistical data on radiation exposure experience to workers in the nuclear fuel cycle through 1978. The technical sessions were concerned with occupational exposures: experienced in Member States; in research and development facilities; in nuclear power plants; in nuclear Fuel reprocessing facilities; in waste management facilities; and techniques to minimize doses. A critical review was made of internal and external exposures to the following occupational groups: uranium miners; mill workers; fuel fabricators; research personnel, reactor workers; maintenance staff; hot cell workers; reprocessing plant personnel; waste management personnel. In particular, attention was devoted to the work activities causing the highest radiation exposures and successful techniques which have been used to minimize individual and collective doses. Also there was an exchange of information on the trends of occupational exposure over the lifespan of individual nuclear power plants and other facilities in the nuclear fuel cycle. During the last session there was a detailed panel discussion on the conclusions and future needs highlighted during the symposium. While past symposia on nuclear power and its fuel cycle have presented data on occupational dose statistics, this symposium was the first to focus attention on the experience and trends of occupational exposure in recent years. The papers presented an authoritative account of the status of the levels and trends of the average annual individual dose as well as the annual collective dose for occupational workers in most of the world up to 1979. From the data presented it became evident that considerable progress has been

  6. Bases for establishing radiation exposure limits

    International Nuclear Information System (INIS)

    Pochin, E.E.

    1977-01-01

    It is an essential requirement of good radiation protection that all unnecessary exposure of people should be avoided and that any necessary exposure, whether of workers or of members of the general public, should be minimized. It is, however, an additional requirement that such necessary exposures should not exceed certain stated limits. These principles are based on the possibility that even the smallest exposures may involve some risk of harm, that any risk of harm should be justifiable by the circumstances necessitating it, and that risk should always be limited to an appropriately low level. The bases for establishing exposure limits must therefore involve an assessment of the risk involved in any form of radiation exposure, and an opinion as to the degree of safety that should be ensured in circumstances which necessitate any occupational or public exposure to radiation. There is increasing quantitative evidence on the frequency on which harm, and particularly the induction of malignancies, may be caused in people exposed to radiation at high doses; and somewhat clearer bases than previously for inferring the possible frequencies at low doses. It is therefore easier to assess the degree of safety ensured by restricting radiation exposure to particular levels. It is clear also that a comparable degree of safety should be ensured whether the radiation exposure involves the whole body more of less uniformly, or individual tissues or organs selectively. The ''weighting'' factors appropriate to irradiation of particular tissues from internal emitters can thus be defined in terms of their likely individual contributions to the harm of whole-body irradiation. In this way the limits for different modes of exposure by external or internal radiation can be related so as to ensure that protection should be equally effective for different distributions of absorbed dose in the body. In particular, the over-simplified concept of a single critical organ determining the

  7. Indoor exposure to natural radiation in Denmark

    International Nuclear Information System (INIS)

    Ulbak, K.; Stenum, B.; Soerensen, A.; Majborn, B.; Boetter-Jensen, L.; Nielsen, S.P.

    1988-01-01

    Assessment of the exposures to the Danish population from different natural radiation sources including building materials, drinking water, fly ash etc. has been performed from 1975 and up till now. In 1987 a comprehensive nationwide investigation of the gamma exposures and radon levels in 500 randomly selected Danish dwellings will be concluded by the National Institute of Radiation Hygiene. At the same time the Danish authorities will publish a control strategy for limiting the exposure of the Danish population from natural sources, especially from radon daughter exposure in dwellings. The presentation will outline the main results of the nationwide survey in Danish dwellings together with the main principles behind and the consequences of the initiated control strategy for limiting the exposures from natural radioactive sources

  8. Medical radiation exposure and its impact on occupational practices in Korean radiologic technologists

    International Nuclear Information System (INIS)

    Ko, Seul Ki; Lee, Won Jin

    2016-01-01

    The use of radiology examinations in medicine has been growing worldwide. Annually an estimated 3.1 billion radiologic exams are performed. According to this expansion of medical radiation exposure, it has been hard to pay no attention to the effects of medical radiation exposures in the exposure from different types of radiation source. This study, therefore, was aimed to assess the association of medical and occupational radiation exposure in Korean radiologic technologists and evaluate necessity for its consideration in occupational studies. This study did not show the strong association between medical radiation exposure and occupational radiation exposure except several modalities with specific frequency. These results are preliminary but certainly meaningful for interpretation of epidemiologic finding, therefore, we need further evaluation specially for the repeatedly exposed imaging tests and high dose procedures that presented somewhat weak relationship in this study linked with health outcomes of radiation exposure. This study did not show the strong association between medical radiation exposure and occupational radiation exposure except several modalities with specific frequency. These results are preliminary but certainly meaningful for interpretation of epidemiologic finding, therefore, we need further evaluation specially for the repeatedly exposed imaging tests and high dose procedures that presented somewhat weak relationship in this study linked with health outcomes of radiation exposure.

  9. Medical radiation exposure and its impact on occupational practices in Korean radiologic technologists

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Seul Ki; Lee, Won Jin [Dept. of Preventive Medicine, Korea University College of Medicine, Seoul (Korea, Republic of)

    2016-12-15

    The use of radiology examinations in medicine has been growing worldwide. Annually an estimated 3.1 billion radiologic exams are performed. According to this expansion of medical radiation exposure, it has been hard to pay no attention to the effects of medical radiation exposures in the exposure from different types of radiation source. This study, therefore, was aimed to assess the association of medical and occupational radiation exposure in Korean radiologic technologists and evaluate necessity for its consideration in occupational studies. This study did not show the strong association between medical radiation exposure and occupational radiation exposure except several modalities with specific frequency. These results are preliminary but certainly meaningful for interpretation of epidemiologic finding, therefore, we need further evaluation specially for the repeatedly exposed imaging tests and high dose procedures that presented somewhat weak relationship in this study linked with health outcomes of radiation exposure. This study did not show the strong association between medical radiation exposure and occupational radiation exposure except several modalities with specific frequency. These results are preliminary but certainly meaningful for interpretation of epidemiologic finding, therefore, we need further evaluation specially for the repeatedly exposed imaging tests and high dose procedures that presented somewhat weak relationship in this study linked with health outcomes of radiation exposure.

  10. Radiation exposure after permanent prostate brachytherapy

    International Nuclear Information System (INIS)

    Cattani, Federica; Vavassori, Andrea; Polo, Alfredo; Rondi, Elena; Cambria, Raffaella; Orecchia, Roberto; Tosi, Giampiero

    2006-01-01

    Background and purpose: Limited information is available on the true radiation exposure and associated risks for the relatives of the patients submitted to prostate brachytherapy with permanent implant of radioactive sources and for any other people coming into contact with them. In order to provide appropriate information, we analyzed the radiation exposure data from 216 prostate cancer patients who underwent 125 I or 103 Pd implants at the European Institute of Oncology of Milan, Italy. Patients and methods: Between October 1999 and October 2004, 216 patients with low risk prostate carcinoma were treated with 125 I (200 patients) or 103 Pd (16 patients) permanent seed implantation. One day after the procedure, radiation exposure measurements around the patients were performed using an ionization chamber survey meter (Victoreen RPO-50) calibrated in dose rate at an accredited calibration center (calibration Centre SIT 104). Results: The mean dose rate at the posterior skin surface (gluteal region) following 125 I implants was 41.3 μSv/h (range: 6.2-99.4 μSv/h) and following 103 Pd implants was 18.9 μSv/h (range 5.0-37.3 μSv/h). The dose rate at 50 cm from the skin decreased to the mean value of 6.4 μSv/h for the 125 I implants and to the mean value of 1.7 μSv/h for the 103 Pd implants. Total times required to reach the annual dose limit (1 mSv/year) recommended for the general population by the European Directive 96/29/Euratom and by the Italian law (Decreto Legislativo 241/2000) at a distance of 50 cm from the posterior skin surface of the implanted patient would be 7.7 and 21.6 days for 125 I and for 103 Pd. Good correlation between the measured dose rates and both the total implanted activity and the distance between the most posteriorly implanted seed and the skin surface of the patients was found. Conclusions: Our data show that the dose rates at 50 cm away from the prostate brachytherapy patients are very low and that the doses possibly absorbed by the

  11. Proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management 2006 Nagoya

    International Nuclear Information System (INIS)

    2006-01-01

    This is the program and the proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management held from November 29th through December 1st of 2006. The sessions held are: (1) Radiation Measurement 1, (2) Education Method, (3) Radiation Control, (4) Waste Handling, Contamination Inspection, and Renewal, (5) Exposure Reduction, Radiation Evaluation, and Radioactivity Control (6) Radiation Measurement 2, (7) Operation Environment, (8) Medical Exposure, (9) Radiation Measurement 3, (10) Software, IT Technology, and Data Processing, (11) Emission and Drainage Handling, and (12) Radiation Effect and Contamination Countermeasure. The poster sessions held are: (1) Radiation Measurement, (2) Environmental Radiation, (3) Scattering Rate, Penetration Rate, and Contamination Inspection, (4) Education Method, (5) Medical Exposure, (6) Access Control and Software, and (7) Radiation Control Method and Monitoring. The symposia held are: (1) 'Toward Establishment of Guideline for Safe X-ray Handling Education' and 'International Situation of Radiation Safety'. 2 keynote lectures were also held. (S.K.)

  12. Human exposure to ultraviolet radiation

    International Nuclear Information System (INIS)

    Bernhardt, J.H.; Matthes, R.

    1987-01-01

    Ultraviolet radiation is that part of the electromagnetic spectrum located between the softest ionizing radiation and visible radiation. The lower limit of 100 nm is equivalent to photon energies of 12.4 eV, which corresponds approximately to the limit for the production of ionization in biologically important materials. A historical subdividing of the UV-region takes some of the biological effects into account. In this arrangement the range 400-315 nm, the so-called black light region, is called UV-A. In this wavelength region, fluorescence can be induced in many substances. UV-B covers the range 315-280 nm (the skin erythemal region). Most of the biologically active and potentially harmful UV from the sun reaching the surface of the earth is part of this spectral region. UV-C includes the radiation of wavelengths less than 280 nm (the germicidal region). It should be noted that this classification is somewhat arbitrary, and today it is more usual to evaluate the biological effectiveness of the whole UV-range from 200 to 400 nm

  13. Radiation risk due to occupational exposure

    International Nuclear Information System (INIS)

    Kargbo, A.A

    2012-04-01

    Exposure to ionizing radiation occurs in many occupations. Workers can be exposed to both natural and artificial sources of radiation. Any exposure to ionizing radiation incurs some risk, either to the individual or to the individual's progeny. This dissertation investigated the radiation risk due to occupational exposure in industrial radiography. Analysis of the reported risk estimates to occupational exposure contained in the UNSCEAR report of 2008 in industrial radiography practice was done. The causes of accidents in industrial radiography include: Lack of or inadequate regulatory control, inadequate training, failure to follow operational procedures, human error, equipment malfunction or defect, inadequate maintenance and wilful violation have been identified as primary causes of accidents. To minimise radiation risks in industrial radiography exposure devices and facilities should be designed such that there is intrinsic safety and operational safety ensured by establishing a quality assurance programme, safety culture fostered and maintained among all workers, industrial radiography is performed in compliance with approved local rules, workers engaged have appropriate qualifications and training, available safe operational procedures are followed, a means is provided for detecting incidents and accidents and an analysis of the causes and lessons learned. (author)

  14. Occupational exposures at nuclear power plants. Twelfth annual report of the Isoe programme, 2002

    International Nuclear Information System (INIS)

    2004-01-01

    The Information System on Occupational Exposure (ISOE) was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The ISOE Programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 465 commercial nuclear power plants participating in the Programme (representing some 90 per cent of the world's total operating commercial reactors). The Twelfth Annual Report of the ISOE Programme summarises achievements made during 2002 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

  15. Evaluation of exposure to ionizing radiation among gamma camera operators

    Directory of Open Access Journals (Sweden)

    Agnieszka Anna Domańska

    2013-08-01

    Full Text Available Background: Protection of nuclear medicine unit employees from hazards of the ionizing radiation is a crucial issue of radiation protection services. We aimed to assess the severity of the occupational radiation exposure of technicians performing scintigraphic examinations at the Nuclear Medicine Department, Central Teaching Hospital of Medical University in Łódź, where thousands of different diagnostic procedures are performed yearly. Materials and Methods: In 2013 the studied diagnostic unit has employed 10 technicians, whose exposure is permanently monitored by individual dosimetry. We analyzed retrospective data of quarterly doses in terms of Hp(10 dose equivalents over the years 2001-2010. Also annual and five-year doses were determined to relate the results to current regulations. Moreover, for a selected period of one year, we collected data on the total activity of radiopharmaceuticals used for diagnostics, to analyze potential relationship with doses recorded in technicians performing the examinations. Results: In a 10-year period under study, the highest annual dose recorded in a technician was 2 mSv, which represented 10% of the annual dose limit of 20 mSv. The highest total dose for a 5-year period was 7.1 mSv, less than 10% of a 5-year dose limit for occupational exposure. Positive linear correlation was observed between total activity of radiopharmaceuticals used for diagnostics in the period of three months and respective quarterly doses received by technicians performing examinations. Conclusions: Doses received by nuclear medicine technicians performing diagnostic procedures in compliance with principles of radiation protection are low, which is confirmed by recognizing the technicians of this unit as B category employees. Med Pr 2013;64(4:503–506

  16. Biological effects and hazards of radiation exposure

    International Nuclear Information System (INIS)

    Boas, J.F.; Solomon, S.B.

    1990-01-01

    Radiation induced carcinogenesis and mutagenesis form the main risk to health from exposure to low levels of radiation. This risk effects can be at least qualitatively understood by considering the effects of radiation on cell DNA. Whilst exposure to high levels of radiation results in a number of identifiable effects, exposure to low levels of radiation may result in effects which only manifest themselves after many years. Risk estimates for low levels of radiation have been derived on the basis of a number of assumptions. In the case of uranium mine workers a major hazard arises from the inhalation of radon daughters. Whilst the correlation between radon daughter exposure and lung cancer incidence is well established, the numerical value of the risk factor is the subject of controversy. ICRP 50 gives a value of 10 cases per 10 6 person-years at risk per WLM (range 5-15 x 10 -6 PYR -1 WLM -1 ). The effect of smoking on lung cancer incidence rates amongst miners is also controversial. Nevertheless, smoking by miners should be discouraged

  17. Project Radiation protection, Annual report 1994

    International Nuclear Information System (INIS)

    Ninkovic, M.M.

    1994-12-01

    According to the action plan for the period 1991-1995, the main objective of this project during 1994 was to provide operational basis, methods and procedures for solving the radiation protection problems that might appear under routine working conditions and handling of radiation sources. The aim was also to provide special methods for action in case of accidents that could affect the employed staff and the population. Overall activity was directed to maintaining and providing personnel, instrumentation, and methods for the following special radiation protection measures: operational control of the radiation field and contamination; calibration of the radiation and dosimetry instruments-secondary dosimetry metrology laboratory; instrumentation and measuring systems for radiation protection; control of environmental transfer of radioactive material; medical radiation protection [sr

  18. Radiological protection for medical exposure to ionizing radiation. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    When ionizing radiation was discovered more than 100 years ago its beneficial uses were quickly discovered by the medical profession. Over the years new diagnostic and therapeutic techniques have been developed and the general level of health care has improved. This has resulted in medical radiation exposures becoming a significant component of the total radiation exposure of populations. Current estimates put the worldwide annual number of diagnostic exposures at 2500 million and therapeutic exposures at 5.5 million. Some 78% of diagnostic exposures are due to medical X rays, 21% due to dental X rays and the remaining 1% due to nuclear medicine techniques. The annual collective dose from all diagnostic exposures is about 2500 million man Sv, corresponding to a worldwide average of 0.4 mSv per person per year. There are, however, wide differences in radiological practices throughout the world, the average annual per caput values for States of the upper and lower health care levels being 1.3 mSv and 0.02 mSv, respectively. It should, however, be noted that doses from therapeutic uses of radiation are not included in these averages, as they involve very high doses (in the region of 20-60 Gy) precisely delivered to target volumes in order to eradicate disease or to alleviate symptoms. Over 90% of total radiation treatments are conducted by teletherapy or brachytherapy, with radiopharmaceuticals being used in only 7% of treatments. Increases in the uses of medical radiation and the resultant doses can be expected following changes in patterns of health care resulting from advances in technology and economic development. For example, increases are likely in the utilization of computed tomography (CT), digital imaging and, with the attendant potential for deterministic effects, interventional procedures; practice in nuclear medicine will be driven by the use of new and more specific radiopharmaceuticals for diagnosis and therapy, and there will be an increased demand for

  19. Radiological protection for medical exposure to ionizing radiation. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    When ionizing radiation was discovered more than 100 years ago its beneficial uses were quickly discovered by the medical profession. Over the years new diagnostic and therapeutic techniques have been developed and the general level of health care has improved. This has resulted in medical radiation exposures becoming a significant component of the total radiation exposure of populations. Current estimates put the worldwide annual number of diagnostic exposures at 2500 million and therapeutic exposures at 5.5 million. Some 78% of diagnostic exposures are due to medical X rays, 21% due to dental X rays and the remaining 1% due to nuclear medicine techniques. The annual collective dose from all diagnostic exposures is about 2500 million man Sv, corresponding to a worldwide average of 0.4 mSv per person per year. There are, however, wide differences in radiological practices throughout the world, the average annual per caput values for States of the upper and lower health care levels being 1.3 mSv and 0.02 mSv, respectively. It should, however, be noted that doses from therapeutic uses of radiation are not included in these averages, as they involve very high doses (in the region of 20-60 Gy) precisely delivered to target volumes in order to eradicate disease or to alleviate symptoms. Over 90% of total radiation treatments are conducted by teletherapy or brachytherapy, with radiopharmaceuticals being used in only 7% of treatments. Increases in the uses of medical radiation and the resultant doses can be expected following changes in patterns of health care resulting from advances in technology and economic development. For example, increases are likely in the utilization of computed tomography (CT), digital imaging and, with the attendant potential for deterministic effects, interventional procedures. Practice in nuclear medicine will be driven by the use of new and more specific radiopharmaceuticals for diagnosis and therapy, and there will be an increased demand for

  20. Geothermal energy probes. Increasing the radiation exposures of the population?

    International Nuclear Information System (INIS)

    Melzer, Danica; Wilhelm, Christoph

    2014-01-01

    In Baden-Wuerttemberg 10 private geothermal drilling projects in geologically interesting areas have been accompanied by measurements. During the drillings samples of the excavated earth were taken to determine the concentration of natural nuclides in the bored strata. Before and after finishing the geothermal construction works the airborne radon concentration of surrounding dwellings was measured. On the basis of the obtained measuring data the maximum expected additional effective annual doses received by individuals as a result of geothermal drilling were calculated. The exposure pathways were observed, i.e. air, water, sold - plant - human and terrestrial gamma radiation. In spite of conservative accounts in each case that should be considered as worst case scenario no relevant increase of radiation exposure could be detected. (orig.)

  1. Proposal of radiation exposure index, REXI

    International Nuclear Information System (INIS)

    Katoh, Kazuaki

    2002-01-01

    As a measure of harmful effect of radiation, radiation exposure index (REXI) is proposed. It is an integer expression of logarithmic ratio of radiation dose to a standard value. REXI is a dimensionless quantity and is free from the requirement of additivity, in contrast with dose. Not a few kinds of doses are used in the field of radiation protection and among them the effective dose plays main role, since the main target of radiation control is of the so-called stochastic effect and the effective dose is used as the controlling quantity. Effective dose is a radiation dose, namely, a quantity of caused to describe the effect, but it cannot be a representation of the effect itself. It is nothing but a measure of possibility of the effect. In addition, the LNT (linearity and non threshold) Postulation adopted by ICRP makes it difficult to understand the foreseen associated effect quantitatively. (author)

  2. Determinants of personal ultraviolet-radiation exposure doses on a sun holiday

    DEFF Research Database (Denmark)

    Petersen, B; Thieden, E; Philipsen, P A

    2013-01-01

    A great number of journeys to sunny destinations are sold to the Danish population every year. We suspect that this travel considerably increases personal annual ultraviolet-radiation (UVR) exposure doses. This is important because such exposure is the main cause of skin cancer, and studies have...

  3. Radiation exposure in nucleomedical examinations of children

    International Nuclear Information System (INIS)

    Hahn, K.; Hach, A.; Reber, H.

    1995-01-01

    The problem of radiation exposure must be subjected to particularly careful scrutiny in nuclear diagnostic procedures in children. The contribution provides a survey of factors influencing the radiation exposure of children in the diagnostic use of radionuclides. These include the age of the child examined, the type of radiopharmaceutical used, the dose of the radiopharmaceutical and the procedure followed. Any state-of-the-art renal function study or skeletal examination using radionuclides requires previous measures to ensure that the child is sufficiently hydrated. The tables in the appendix provide estimations of the doses from the individual nucleomedical procedures used in paediatrics. (orig./MG) [de

  4. Radiation exposure from radium-226 ingestion

    International Nuclear Information System (INIS)

    Keefer, D.H.; Fenyves, E.J.

    1980-01-01

    The contribution of radium to total radiation exposure resulting from the consumption of natural levels of 226 Ra in several public water supplies in an Oklahoma county was determined. A pilot-level study of total dietary intake indicated that the culinary use of water anomalously high in radium and the consumption of water-based beverages contributed significantly to radiation exposure. The mean dietary intake of 226 Ra was 20.6 pCi/day in one community and resulted in an estimated bone dose of 310 mrem/year

  5. Haematological and immunological indicators for radiation exposure

    International Nuclear Information System (INIS)

    Dehos, A.

    1990-01-01

    It is examined if haematological and immunological parameters can be used as biological indicators for radiation exposure. Additional criteria for biological indicators, apart from the dose dependence of the effect, are listed here. The state of the art concerning the development of haematological and immunological indicators is discussed. Several haematological indicators are currently used in diagnosis when excess radiation exposure has occurred (e.g., after the Chernobyl accident). However, further research work has to be done in the field of immunological indicators. (orig.) [de

  6. Basic units and concepts in radiation exposures

    International Nuclear Information System (INIS)

    Mlekodaj, R.L.

    1992-01-01

    Some of the most common units, concepts and models in use today in dealing with radiation exposures and the associated risks are presented. Discussions toward a better understanding of some of the basic difficulties in quantifying risks associated with low levels of radiation are presented. The main thrust of this talk is to lay a foundation for better understanding and appreciation of the talks to follow in this symposium

  7. Case of child abuse by radiation exposure

    International Nuclear Information System (INIS)

    Collins, V.P.; Gaulden, M.E.

    1980-01-01

    On 2 May 1974, a father was convicted of castrating his 13-year-old son by exposing him to a 1-curie source of 137 Cs to be used for oil gas well logging. The child was subjected to perhaps eight exposures or attempted exposures over a six-month period. A brief discussion of the medical descriptions of the radiation effects upon the skin and testes and the chromosomal system is included

  8. Radiation Protection Institute - Annual Report 2015

    International Nuclear Information System (INIS)

    2015-01-01

    The Radiation Protection Institute (RPI) of the Ghana Atomic Energy Commission was established to provide the scientific and technical support for executing the operational functions of the Radiation Protection Board. The operational activities of the Institute are listed. Also included in the report are the various research projects, training programmes and publications for the year 2015.

  9. Radiation Research Department annual report 2002

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer. A.; Nielsen, S.P.

    2003-06-01

    The report presents a summary of the work of the Radiation Research Department in 2002. The departments research and development activities are organized in two research programmes: 'Radiation Physics' and 'Radioecology and Tracer Studies'. In addition the department is responsible for the task 'Dosimetry'. Lists of publications, committee memberships and staff members are included. (au)

  10. Natural radiation exposure modified by human activities

    International Nuclear Information System (INIS)

    Fujimoto, Kenzo

    1995-01-01

    We are now living in the radiation environment modified by our technology. It is usually called 'Technologically Enhanced Natural Radiation' and have been discussed in the UNSCEAR Reports as an important source of exposure. The terrestrial radionuclide concentrations as well as the intensity of cosmic rays are considered to have been constant after our ancestors came down from trees and started walking on their two feet. However, we have been changing our environment to be more comfortable for our life and consequently ambient radiation levels are nomore what used to be. In this paper exposures due to natural radiation modified by our following activities are discussed: housing, balneology, cave excursion, mountain climbing, skiing, swimming, smoking and usage of mineral water, well water, coal, natural gas, phosphate rocks and minerals. In the ICRP Publication No. 39, it is clearly mentioned that even natural radiation should be controlled as far as it is controllable. We have to pay more attention to our activities not to enhance the exposure due to unnecessary, avoidable radiation. (author)

  11. DOE occupational radiation exposure 1996 report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The goal of the US Department of Energy (DOE) is to conduct its radiological operations to ensure the health and safety of all DOE employees including contractors and subcontractors. The DOE strives to maintain radiation exposures to its workers below administrative control levels and DOE limits and to further reduce these exposures and releases to levels that are ``As Low As Reasonably Achievable`` (ALARA). The DOE Occupational Radiation Exposure Report, 1996 provides summary and analysis of the occupational radiation exposure received by individuals associated with DOE activities. The DOE mission includes stewardship of the nuclear weapons stockpile and the associated facilities, environmental restoration of DOE and precursor agency sites, and energy research. Collective exposure at DOE has declined by 80% over the past decade due to a cessation in opportunities for exposure during the transition in DOE mission from weapons production to cleanup, deactivation and decommissioning, and changes in reporting requirements and dose calculation methodology. In 1996, the collective dose decreased by 10% from the 1995 value due to decreased doses at five of the seven highest-dose DOE sites. For 1996, these sites attributed the reduction in collective dose to the completion of several decontamination and decommissioning projects, reduced spent fuel storage activities, and effective ALARA practices. This report is intended to be a valuable tool for managers in their management of radiological safety programs and commitment of resources.

  12. DOE occupational radiation exposure 1996 report

    International Nuclear Information System (INIS)

    1996-01-01

    The goal of the US Department of Energy (DOE) is to conduct its radiological operations to ensure the health and safety of all DOE employees including contractors and subcontractors. The DOE strives to maintain radiation exposures to its workers below administrative control levels and DOE limits and to further reduce these exposures and releases to levels that are ''As Low As Reasonably Achievable'' (ALARA). The DOE Occupational Radiation Exposure Report, 1996 provides summary and analysis of the occupational radiation exposure received by individuals associated with DOE activities. The DOE mission includes stewardship of the nuclear weapons stockpile and the associated facilities, environmental restoration of DOE and precursor agency sites, and energy research. Collective exposure at DOE has declined by 80% over the past decade due to a cessation in opportunities for exposure during the transition in DOE mission from weapons production to cleanup, deactivation and decommissioning, and changes in reporting requirements and dose calculation methodology. In 1996, the collective dose decreased by 10% from the 1995 value due to decreased doses at five of the seven highest-dose DOE sites. For 1996, these sites attributed the reduction in collective dose to the completion of several decontamination and decommissioning projects, reduced spent fuel storage activities, and effective ALARA practices. This report is intended to be a valuable tool for managers in their management of radiological safety programs and commitment of resources

  13. Cosmic radiation and air crew exposure

    International Nuclear Information System (INIS)

    Vukovic, B.; Lisjak, I.; Vekic, B.; Planinic, J.

    2005-01-01

    When the primary particles from space, mainly protons, enter the atmosphere, they interact with the air nuclei and induce cosmic-ray shower. When an aircraft is in the air, the radiation field within includes many types of radiation of large energy range; the field comprises mainly photons, electrons, positrons and neutrons. Cosmic radiation dose for crews of air crafts A 320 and ATR 42 was measured using TLD-100 (LiF: Mg, Ti) detectors and the Mini 6100 semiconductor dosimeter; radon concentration in the atmosphere was measured using the Alpha Guard radon detector. The total annual dose estimated for the A 320 aircraft crew, at altitudes up to 12000 meters, was 5.3 mSv (including natural radon radiation dose of 1.1 mSv).(author)

  14. Proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management 2005 Kyoto

    International Nuclear Information System (INIS)

    2005-01-01

    This is the program and the proceedings of the 4th annual meeting of Japanese Society of Radiation Safety Management held from November 23rd through the 25th of 2005. The sessions held were: (1) Medical Exposure, (2) Environmental Measurement and Radiation Source Handling, (3) Radiation Measurement and Influence of Electromagnetic Waves, (4) Utilization of Irradiation, (5) Countermeasures against Contamination and Inspection of Contamination, (6) Imaging Plate, (7) Controlled Measurement and Dose Evaluation, (8) Working Environment Measurement 1, (9) Working Environment Measurement 2, (10) Establishment of Software and System, (11) Radiation Education 1, (12) Radiation Education 2, and (13) Exposure Reduction and Safety Control. The poster sessions held were: (1) Exposure Reduction and Radiation Evaluation, (2) Radiation Measurement and Influence of Electromagnetic Waves, (3) Education Training, (4) Safety Control, (5) Software, Data Handling, and Shielding Calculation, and (6) Environmental Radioactivity. The keynote lectures held were: (1) 'Situation of Medical Exposure' and (2) 'Cosmic Radiation While Boarding on Airplanes'. The symposia held were: (1) 'Food Irradiation' and (2) 'Life Science'. (S.K.)

  15. To the exposure of air crew members to cosmic radiation

    International Nuclear Information System (INIS)

    Spurny, F.; Kovar, I.; Bottollier-Depois, J.F.; Plawinski, L.

    1998-01-01

    According to an ICRP recommendation, the exposure of jet aircraft crew to radiation should be considered as occupational exposure when the annual equivalent doses are liable to exceed 1 mSv. Many new data on this type of exposure collected since 1991 are presented and analyzed. The dose equivalent rates established are fitted as a function of flight altitude. An analysis of data from cosmic ray monitors has shown that the presence of cosmic rays in the Earth's atmosphere is rather stable since early 1992. An estimation was therefore made of the possible influence of the solar cycle phase by means of a transport code. The results obtained are compared with experimental data

  16. Exposure to natural sources of radiation in Spain

    International Nuclear Information System (INIS)

    Quindos, L.S.; Fernandez, P.L.; Soto, J.

    1992-01-01

    Studies carried by us during last three years have produced a map of natural radiation for Spain. The map contains, by administrative region, the respective contributions of terrestrial gamma rays, both outdoors and indoors, cosmic rays and indoor radon. Terrestrial gamma rays have been measured outdoors 'in situ' in more than 1,000 locations. Data for indoor gamma rays were derived from the radioactivity content of more typical spanish building materials as also by 'in situ'measurements in approximately 100 houses. The cosmic ray component is calculated from latitude and altitude. Values for indoor radon exposure have been derived from a national survey and covering more than 2,000 individual measurements employing active and passive detectors. When account is taken of exposures elsewhere, the mean annual effective dose equivalent from these sources is evaluated. Doses from thoron decay products and internal exposure due to natural activity retained in the body from diet are not dealt with in this evaluation. (author)

  17. Realtime radiation exposure monitor and control apparatus

    International Nuclear Information System (INIS)

    Cowart, R.W.

    1981-01-01

    This patent application relates to an apparatus and methods used to obtain image information from modulation of a uniform flux. An exposure measuring apparatus is disclosed which comprises a multilayered detector structure having an external circuit connected to a transparent insulating layer and to a conductive plate a radiation source adapted to irradiate the detector structure with radiation capable of producing electron-hole pairs in a photoconductive layer of the detector wherein the flow of current within the external circuit is measured when the detector is irradiated by the radiation source. (author)

  18. BWR radiation exposure--experience and projection

    International Nuclear Information System (INIS)

    Falk, C.F.; Wilkinson, C.D.; Hollander, W.R.

    1979-01-01

    The BWR/6 Mark III radiation exposures are projected to be about half of those of current average operating experience of 725 man-rem. These projections are said to be realistic and based on current achievements and not on promises of future development. The several BWRs operating with low primary system radiation levels are positive evidence that radiation sources can be reduced. Improvements have been made in reducing the maintenance times for the BWR/6, and further improvements can be made by further attention to cost-effective plant arrangement and layout during detail design to improve accessibility and maintainability of each system and component

  19. Radiation dose evaluation based on exposure scenario during the operation of radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Yoon, Jeong Hyoun; Kim Chang Lak; Choi, Heui Joo; Park, Joo Wan

    1999-01-01

    Radiation dose to worker in disposal facility was calculated by using point kernel MICROSHIELD V5.02 computer code based on exposure scenarios. An conceptual design model for disposal vaults in disposal facility was used for object of shielding calculation model. Selected radionuclides and their activities among radioactive wastes from nuclear power plants were assumed as radiation sources for the exposure calculation. Annual radiation doses to crane workers and to people working on disposal vaults were calculated according to exposure time and distance from the sources with conservative operation scenarios. The scenarios used for this study were based on assumption for representing disposal activities in a future Korean near surface disposal facility. Calculated exposure rates to worker during normal disposal work were very low comparing with annual allowable limit for radiation worker

  20. Verification of radiation exposure using lead shields

    International Nuclear Information System (INIS)

    Hayashida, Keiichi; Yamamoto, Kenyu; Azuma, Masami

    2016-01-01

    A long time use of radiation during IVR (intervention radiology) treatment leads up to an increased exposure on IVR operator. In order to prepare good environment for the operator to work without worry about exposure, the authors examined exposure reduction with the shields attached to the angiography instrument, i. e. lead curtain and lead glass. In this study, the lumber spine phantom was radiated using the instrument and the radiation leaked outside with and without shields was measured by the ionization chamber type survey meter. The meter was placed at the position which was considered to be that for IVR operator, and changed vertically 20-100 cm above X-ray focus by 10 cm interval. The radiation at the position of 80 cm above X-ray focus was maximum without shield and was hardly reduced with lead curtain. However, it was reduced with lead curtain plus lead glass. Similar reduction effects were observed at the position of 90-100 cm above X-ray focus. On the other hand, the radiation at the position of 70 cm above X-ray focus was not reduced with either shield, because that position corresponded to the gap between lead curtain and lead glass. The radiation at the position of 20-60 cm above X-ray focus was reduced with lead curtain, even if without lead glass. These results show that lead curtain and lead glass attached to the instrument can reduce the radiation exposure on IVR operator. Using these shields is considered to be one of good means for IVR operator to work safely. (author)

  1. Exposure to UV radiation and human health

    Science.gov (United States)

    Kimlin, Michael G.

    2005-08-01

    This paper will overview the significant issues facing researchers in relating the impact of exposure to sunlight and human health. Exposure to solar ultraviolet radiation is the major causative factor in most sun-related skin and eye disorders, however, very little is known quantitatively about human UV exposures. Interestingly, human exposure to sunlight also has a nutritional impact, namely the development of pre-Vitamin D, which is an important nutrient in bone health. New research suggest that low vitamin D status may be a causative factor in the development of selective types of cancer and autoimminue diseases, as well as a contributing factor in bone health. The 'health duality' aspect of sunlight exposure is an interesting and controversial topic that is a research focus of Kimlin's research group.

  2. Radiation Research Department annual report 2003

    DEFF Research Database (Denmark)

    Majborn, Benny; Damkjær, A.; Nielsen, Sven Poul

    2004-01-01

    This report presents a summary of the work of the Radiation Research Department in 2003. The main research areas were dosimetry, nuclear emergency preparedness, radioecology, and radioanalytical techniques. List of publications, committee memberships andstaff members are included....

  3. Radiation Research Department annual report 2003

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P. (eds.)

    2004-06-01

    This report presents a summary of the work of the Radiation Research Department in 2003. The main research areas were dosimetry, nuclear emergency preparedness, radioecology, and radioanalytical techniques. Lists of publications, committee memberships and staff members are included. (au)

  4. Radiation Research Department annual report 2002

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Nielsen, S.P. (eds.)

    2003-06-01

    The report presents a summary of the work of the Radiation Research Department in 2002. The departments research and development activities are organized in two research programmes: 'Radiation Physics' and 'Radioecology and Tracer Studies'. In addition the department is responsible for the task 'Dosimetry'. Lists of publications, committee memberships and staff members are included. (au)

  5. A translatable predictor of human radiation exposure.

    Science.gov (United States)

    Lucas, Joseph; Dressman, Holly K; Suchindran, Sunil; Nakamura, Mai; Chao, Nelson J; Himburg, Heather; Minor, Kerry; Phillips, Gary; Ross, Joel; Abedi, Majid; Terbrueggen, Robert; Chute, John P

    2014-01-01

    Terrorism using radiological dirty bombs or improvised nuclear devices is recognized as a major threat to both public health and national security. In the event of a radiological or nuclear disaster, rapid and accurate biodosimetry of thousands of potentially affected individuals will be essential for effective medical management to occur. Currently, health care providers lack an accurate, high-throughput biodosimetric assay which is suitable for the triage of large numbers of radiation injury victims. Here, we describe the development of a biodosimetric assay based on the analysis of irradiated mice, ex vivo-irradiated human peripheral blood (PB) and humans treated with total body irradiation (TBI). Interestingly, a gene expression profile developed via analysis of murine PB radiation response alone was inaccurate in predicting human radiation injury. In contrast, generation of a gene expression profile which incorporated data from ex vivo irradiated human PB and human TBI patients yielded an 18-gene radiation classifier which was highly accurate at predicting human radiation status and discriminating medically relevant radiation dose levels in human samples. Although the patient population was relatively small, the accuracy of this classifier in discriminating radiation dose levels in human TBI patients was not substantially confounded by gender, diagnosis or prior exposure to chemotherapy. We have further incorporated genes from this human radiation signature into a rapid and high-throughput chemical ligation-dependent probe amplification assay (CLPA) which was able to discriminate radiation dose levels in a pilot study of ex vivo irradiated human blood and samples from human TBI patients. Our results illustrate the potential for translation of a human genetic signature for the diagnosis of human radiation exposure and suggest the basis for further testing of CLPA as a candidate biodosimetric assay.

  6. A translatable predictor of human radiation exposure.

    Directory of Open Access Journals (Sweden)

    Joseph Lucas

    Full Text Available Terrorism using radiological dirty bombs or improvised nuclear devices is recognized as a major threat to both public health and national security. In the event of a radiological or nuclear disaster, rapid and accurate biodosimetry of thousands of potentially affected individuals will be essential for effective medical management to occur. Currently, health care providers lack an accurate, high-throughput biodosimetric assay which is suitable for the triage of large numbers of radiation injury victims. Here, we describe the development of a biodosimetric assay based on the analysis of irradiated mice, ex vivo-irradiated human peripheral blood (PB and humans treated with total body irradiation (TBI. Interestingly, a gene expression profile developed via analysis of murine PB radiation response alone was inaccurate in predicting human radiation injury. In contrast, generation of a gene expression profile which incorporated data from ex vivo irradiated human PB and human TBI patients yielded an 18-gene radiation classifier which was highly accurate at predicting human radiation status and discriminating medically relevant radiation dose levels in human samples. Although the patient population was relatively small, the accuracy of this classifier in discriminating radiation dose levels in human TBI patients was not substantially confounded by gender, diagnosis or prior exposure to chemotherapy. We have further incorporated genes from this human radiation signature into a rapid and high-throughput chemical ligation-dependent probe amplification assay (CLPA which was able to discriminate radiation dose levels in a pilot study of ex vivo irradiated human blood and samples from human TBI patients. Our results illustrate the potential for translation of a human genetic signature for the diagnosis of human radiation exposure and suggest the basis for further testing of CLPA as a candidate biodosimetric assay.

  7. [Effects of radiation exposure on human body].

    Science.gov (United States)

    Kamiya, Kenji; Sasatani, Megumi

    2012-03-01

    There are two types of radiation health effect; acute disorder and late on-set disorder. Acute disorder is a deterministic effect that the symptoms appear by exposure above a threshold. Tissues and cells that compose the human body have different radiation sensitivity respectively, and the symptoms appear in order, from highly radiosensitive tissues. The clinical symptoms of acute disorder begin with a decrease in lymphocytes, and then the symptoms appear such as alopecia, skin erythema, hematopoietic damage, gastrointestinal damage, central nervous system damage with increasing radiation dose. Regarding the late on-set disorder, a predominant health effect is the cancer among the symptoms of such as cancer, non-cancer disease and genetic effect. Cancer and genetic effect are recognized as stochastic effects without the threshold. When radiation dose is equal to or more than 100 mSv, it is observed that the cancer risk by radiation exposure increases linearly with an increase in dose. On the other hand, the risk of developing cancer through low-dose radiation exposure, less 100 mSv, has not yet been clarified scientifically. Although uncertainty still remains regarding low level risk estimation, ICRP propound LNT model and conduct radiation protection in accordance with LNT model in the low-dose and low-dose rate radiation from a position of radiation protection. Meanwhile, the mechanism of radiation damage has been gradually clarified. The initial event of radiation-induced diseases is thought to be the damage to genome such as radiation-induced DNA double-strand breaks. Recently, it is clarified that our cells could recognize genome damage and induce the diverse cell response to maintain genome integrity. This phenomenon is called DNA damage response which induces the cell cycle arrest, DNA repair, apoptosis, cell senescence and so on. These responses act in the direction to maintain genome integrity against genome damage, however, the death of large number of

  8. Risk of cardiovascular disease following radiation exposure

    International Nuclear Information System (INIS)

    Trivedi, A.; Vlahovich, S.; Cornett, R.J.

    2001-01-01

    Excess radiation-induced cardiac mortalities have been reported among radiotherapy patients. Many case reports describe the occurrence of atherosclerosis following radiotherapy for Hodgkin's disease and breast cancer. Some case reports describe the cerebral infarction following radiotherapy to neck region, and of peripheral vascular disease of the lower extremities following radiotherapy to the pelvic region. The association of atomic bomb radiation and cardiovascular disease has been examined recently by incidence studies and prevalence studies of various endpoints of atherosclerosis; all endpoints indicated an increase of cardiovascular disease in the exposed group. It is almost certain that the cardiovascular disease is higher among atomic bomb survivors. However, since a heavy exposure of 10-40 Gy is delivered in radiotherapy and the bomb survivors were exposed to radiation at high dose and dose-rate, the question is whether the results can be extrapolated to individuals exposed to lower levels of radiation. Some recent epidemiological studies on occupationally exposed workers and population living near Chernobyl have provided the evidence for cardiovascular disease being a significant late effect at relatively low doses of radiation. However, the issue of non-cancer mortality from radiation is complicated by lack of adequate information on doses, and many other confounding factors (e.g., smoking habits or socio-economic status). This presentation will evaluate possible radiobiological mechanisms for radiation-induced cardiovascular disease, and will address its relevance to radiation protection management at low doses and what the impact might be on future radiation risk assessments. (authors)

  9. Occupational exposure to ionizing radiation in Kenya

    International Nuclear Information System (INIS)

    Shadrack, Anthony Kiti

    2008-01-01

    Full text: This project is based on studies of radiation doses received by radiation workers from sample of radiation facilities in Nairobi, Kenya, using TLD badges. Radiation doses received by workers during performance of a few types of radiological exposures and application of sealed and unsealed radionuclides have been measured at a number of x ray departments (diagnostic radiology), radiotherapy and nuclear medicine and training and research. Radiation dose measurements were based on thermoluminescence dosimetry (TLD) techniques, using the laboratory facilities of the National Radiation Protection Laboratory (NRPL) at KNH, in Nairobi, Kenya. Evaluation of doses from TLD badges exposed to X-rays and radioisotopes are discussed. Nuclear medicine recorded the highest dose as compared to Radiotherapy, Training and research and Diagnostic radiology. Age and gender have no relation with dose absorption. Yearly average dose seems to have been reducing from 2002 to 2005, representing an improvement in radiation protection. Overall, the results show that radiation workers in Kenya are working under safe environments since the doses received are within acceptable limits of radiation protection. The data presented in this research provides a database, which should serve as a useful reference for comparison with similar studies in the future. (author)

  10. Management of cosmic radiation exposure for aircraft crew in Japan

    International Nuclear Information System (INIS)

    Yasuda, H.; Sato, T.; Yonehara, H.; Kosako, T.; Fujitaka, K.; Sasaki, Y.

    2011-01-01

    The International Commission on Radiological Protection has recommended that cosmic radiation exposure of crew in commercial jet aircraft be considered as occupational exposure. In Japan, the Radiation Council of the government has established a guideline that requests domestic airlines to voluntarily keep the effective dose of cosmic radiation for aircraft crew below 5 mSv y -1 . The guideline also gives some advice and policies regarding the method of cosmic radiation dosimetry, the necessity of explanation and education about this issue, a way to view and record dose data, and the necessity of medical examination for crew. The National Inst. of Radiological Sciences helps the airlines to follow the guideline, particularly for the determination of aviation route doses by numerical simulation. The calculation is performed using an original, easy-to-use program package called 'JISCARD EX' coupled with a PHITS-based analytical model and a GEANT4-based particle tracing code. The new radiation weighting factors recommended in 2007 are employed for effective dose determination. The annual individual doses of aircraft crew were estimated using this program. (authors)

  11. Human exposure to low level ionising radiation

    International Nuclear Information System (INIS)

    Paix, David

    1988-01-01

    This paper describes the low-level radiation sources and their effects on human populations, from a global perspective. 'Low-level' means exposures in the range of the natural background to which everybody is exposed. The quoted values are whole-world averages, but individual variations are mentioned in a few cases. (author). 22 refs

  12. Control of radiation exposures by decontamination

    International Nuclear Information System (INIS)

    LeSurf, J.E.

    1981-01-01

    The radiation exposures of workers at light water and heavy water cooled reactors can be reduced by dilute chemical decontamination as exemplified by the CAN-DECON process. The cost effectiveness of the CAN-DECON process is illustrated by actual service experience and by hypothetical cases

  13. Radiation exposure of airline crew members to the atmospheric ionizing radiation environment

    International Nuclear Information System (INIS)

    Angelis, G. De; Ballard, T.; Lagorio, S.; Verdecchia, A.

    2000-01-01

    All risk assessment techniques for possible health effects from low dose rate radiation exposure should combine knowledge both of the radiation environment and of the biological response, whose effects (e.g. carcinogenesis) are usually evaluated through mathematical models and/or animal and cell experiments. Data on human exposure to low dose rate radiation exposure and its effects are not readily available, especially with regards to stochastic effects, related to carcinogenesis and therefore to cancer risks, for which the event probability increases with increasing radiation exposure. The largest source of such data might be airline flight personnel, if enrolled for studies on health effects induced by the cosmic-ray generated atmospheric ionizing radiation, whose total dose, increasing over the years, might cause delayed radiation-induced health effects, with the high-LET and highly ionizing neutron component typical of atmospheric radiation. In 1990 flight personnel has been given the status of 'occupationally exposed to radiation' by the International Commission for Radiation Protection (ICRP), with a received radiation dose that is at least twice larger than that of the general population. The studies performed until now were limited in scope and cohort size, and moreover no information whatsoever on radiation occupational exposure (e.g. dose, flight hours, route haul, etc.) was used in the analysis, so no correlation has been until now possible between atmospheric ionizing radiation and (possibly radiation-induced) observed health effects. Our study addresses the issues, by considering all Italian civilian airline flight personnel, both cockpit and cabin crew members, with about 10,000 people selected, whose records on work history and actual flights (route, aircraft type, date, etc. for each individual flight for each person where possible) are considered. Data on actual flight routes and profiles have been obtained for the whole time frame. The actual dose

  14. Radiation exposure mitigation through food

    International Nuclear Information System (INIS)

    Nishimura, Yoshikazu; Yukawa, Masae; Watanabe, Yoshito; Shiraishi, Kunio; Muramatsu, Yasuyuki; Uchida, Shigeo; Watabe, Teruhisa; Miyazaki, Taeko

    2001-01-01

    137 CsCl 2 was incorporated into plants (tomyao and broccoli) and these homogenized solutions were administered to rats. The whole-body retention was determined with an Armac counter. The whole body retention patterns of 137 Cs incorporated into the plants were not significantly different from that of the 137 CsCl 2 solution. Chitosan is derived from chitin, which is a cellulose-like biopolymer distributed widely in nature, especially in crustaceans, insects, fungi and yeast. The present study was to investigate whether chitosan can be applied to animal and human bodies in order to reduce the bioavailability of radio-iron and -zinc in food. Chitosan inhibits dietary iron absorption only when rats eat on iron-deficient diet. The effectiveness of phytate (myo-inositol 1,2,3,4,5,6-hexakis dihydrogen phosphate) and chitosan in reducing the bioavailability of radio-zinc depend on the concentration of phytate and chitosan. Recently, the share of imported foods increased ca. 40% of Japanese total food consumption. Radioactivities in imported foods must be checked from the viewpoints of internal radiation for Japanese subjects. Concentrations of 232 Th and 238 U in some imported mineral waters were higher than domestic waters. However, internal doses of portable waters are negligible. Individual foodstuffs in major food groups (fish and shellfish, meats, mushrooms, root vegetables and so on), which contributed to some radionuclide intakes in Japanese, were also analyzed to clarify the critical pathway in Japanese subjects. (author)

  15. Cosmic radiation exposure and persistent cognitive dysfunction

    Science.gov (United States)

    Parihar, Vipan K.; Allen, Barrett D.; Caressi, Chongshan; Kwok, Stephanie; Chu, Esther; Tran, Katherine K.; Chmielewski, Nicole N.; Giedzinski, Erich; Acharya, Munjal M.; Britten, Richard A.; Baulch, Janet E.; Limoli, Charles L.

    2016-01-01

    The Mars mission will result in an inevitable exposure to cosmic radiation that has been shown to cause cognitive impairments in rodent models, and possibly in astronauts engaged in deep space travel. Of particular concern is the potential for cosmic radiation exposure to compromise critical decision making during normal operations or under emergency conditions in deep space. Rodents exposed to cosmic radiation exhibit persistent hippocampal and cortical based performance decrements using six independent behavioral tasks administered between separate cohorts 12 and 24 weeks after irradiation. Radiation-induced impairments in spatial, episodic and recognition memory were temporally coincident with deficits in executive function and reduced rates of fear extinction and elevated anxiety. Irradiation caused significant reductions in dendritic complexity, spine density and altered spine morphology along medial prefrontal cortical neurons known to mediate neurotransmission interrogated by our behavioral tasks. Cosmic radiation also disrupted synaptic integrity and increased neuroinflammation that persisted more than 6 months after exposure. Behavioral deficits for individual animals correlated significantly with reduced spine density and increased synaptic puncta, providing quantitative measures of risk for developing cognitive impairment. Our data provide additional evidence that deep space travel poses a real and unique threat to the integrity of neural circuits in the brain. PMID:27721383

  16. Radiation exposure in CT-guided interventions

    Energy Technology Data Exchange (ETDEWEB)

    Kloeckner, Roman, E-mail: Roman.Kloeckner@unimedizin-mainz.de [Department of Diagnostic and Interventional Radiology, Johannes Gutenberg-University, Langenbeckstraße 1, 55131 Mainz (Germany); Santos, Daniel Pinto dos; Schneider, Jens [Department of Diagnostic and Interventional Radiology, Johannes Gutenberg-University, Langenbeckstraße 1, 55131 Mainz (Germany); Kara, Levent [Department of Radiology, Inselspital Bern, Freiburgstraße 18, 3010 Bern (Switzerland); Dueber, Christoph; Pitton, Michael B. [Department of Diagnostic and Interventional Radiology, Johannes Gutenberg-University, Langenbeckstraße 1, 55131 Mainz (Germany)

    2013-12-01

    Purpose: To investigate radiation exposure in computed tomography (CT)-guided interventions, to establish reference levels for exposure, and to discuss strategies for dose reduction. Materials and methods: We analyzed 1576 consecutive CT-guided procedures in 1284 patients performed over 4.5 years, including drainage placements; biopsies of different organs; radiofrequency and microwave ablations (RFA/MWA) of liver, bone, and lung tumors; pain blockages, and vertebroplasties. Data were analyzed with respect to scanner settings, overall radiation doses, and individual doses of planning CT series, CT intervention, and control CT series. Results: Eighy-five percent of the total radiation dose was applied during the pre- and post-interventional CT series, leaving only 15% applied by the CT-guided intervention itself. Single slice acquisition was associated with lower doses than continuous CT-fluoroscopy (37 mGy cm vs. 153 mGy cm, p < 0.001). The third quartile of radiation doses varied considerably for different interventions. The highest doses were observed in complex interventions like RFA/MWA of the liver, followed by vertebroplasty and RFA/MWA of the lung. Conclusions: This paper suggests preliminary reference levels for various intervention types and discusses strategies for dose reduction. A multicenter registry of radiation exposure including a broader spectrum of scanners and intervention types is needed to develop definitive reference levels.

  17. The occupational exposure of radiation workers, 1

    Energy Technology Data Exchange (ETDEWEB)

    Kawasaki, S; Yamada, N; Sakurai, K [Yamaguchi Univ., Ube (Japan). School of Medicine

    1975-03-01

    Because the medical use of x-rays and radioisotopes is gradually increasing for diagnosis and therapy, radiation workers, special doctors, nurses and radiological technicians have occupational exposure. Procedures for monitoring external exposure of personnel include the wearing of a filmbadge or a pocket chamber. The results of filmbadge monitoring in Yamaguchi University Hospital for the last 10 years were described. In 1964, the total number of filmbadges that radiation workers used during a 2 week period of radiological examination and therapy was 610. This has been increasing yearly, and in 1972 it was 1999. Radiological technicians generally had low occupational exposure, and about 90 per cent of their filmbadges were exposed to less than 10 mR. Approximately 65 per cent of the filmbadges that nurses used were less than 10 mR, but some nurses who worked in radium therapy at the isotope ward suffered large doses. Some nurses had occasionally exposure higher than 100 mR in radiological examination. Some doctors sustained an occupational exposure of more than 150 mR. From these data, some problems on radiation monitoring using a filmbadge were discussed.

  18. The occupational exposure of radiation workers, 1

    International Nuclear Information System (INIS)

    Kawasaki, Shoji; Yamada, Norimasa; Sakurai, Koh

    1975-01-01

    Because the medical use of x-rays and radioisotopes is gradually increasing for diagnosis and therapy, radiation workers, special doctors, nurses and radiological technicians have occupational exposure. Procedures for monitoring external exposure of personnel include the wearing of a filmbadge or a pocket chamber. The results of filmbadge monitoring in Yamaguchi University Hospital for the last 10 years were described. In 1964, the total number of filmbadges that radiation workers used during a 2 week period of radiological examination and therapy was 610. This has been increasing yearly, and in 1972 it was 1999. Radiological technicians generally had low occupational exposure, and about 90 per cent of their filmbadges were exposed to less than 10 mR. Approximately 65 per cent of the filmbadges that nurses used were less than 10 mR, but some nurses who worked in radium therapy at the isotope ward suffered large doses. Some nurses had occasionally exposure higher than 100 mR in radiological examination. Some doctors sustained an occupational exposure of more than 150 mR. From these data, some problems on radiation monitoring using a filmbadge were discussed. (author)

  19. DOE occupational radiation exposure 1996 report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1996-12-31

    The U.S. Department of Energy (DOE) Office of Environment, Safety and Health publishes the DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for DOE/DOE contractor managers in their management of radiological safety programs and to assist them in the prioritization of resources. We appreciate the efforts and contributions from the various stakeholders within and outside the DOE and hope we have succeeded in making the report more useful. This report includes occupational radiation exposure information for all DOE employees, contractors, subcontractors, and visitors. The exposure information is analyzed in terms of collective data, dose to individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included in the analysis.

  20. DOE occupational radiation exposure 1997 report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1997-12-31

    The U.S. Department of Energy (DOE) Office of Environment, Safety and Health publishes the DOE Occupational Radiation Exposure Report. This report is intended to be a valuable tool for DOE/DOE contractor managers in managing radiological safety programs and to assist them in prioritizing resources. We appreciate the efforts and contributions from the various stakeholders within and outside DOE and hope we have succeeded in making the report more useful. This report includes occupational radiation exposure information for all monitored DOE employees, contractors, subcontractors, and visitors. The exposure information is analyzed in terms of aggregate data, dose to individuals, and dose by site. For the purposes of examining trends, data for the past 5 years are included in the analysis.

  1. Radiation exposure mitigation through food

    Energy Technology Data Exchange (ETDEWEB)

    Nishimura, Yoshikazu; Yukawa, Masae; Watanabe, Yoshito; Shiraishi, Kunio; Muramatsu, Yasuyuki; Uchida, Shigeo [National Inst. of Radiological Sciences, Chiba (Japan); Watabe, Teruhisa; Miyazaki, Taeko [National Inst. of Radiological Sciences, Hitachinaka, Ibaraki (Japan). Lab. for Radioecology

    2001-12-01

    {sup 137}CsCl{sub 2} was incorporated into plants (tomyao and broccoli) and these homogenized solutions were administered to rats. The whole-body retention was determined with an Armac counter. The whole body retention patterns of {sup 137}Cs incorporated into the plants were not significantly different from that of the {sup 137}CsCl{sub 2} solution. Chitosan is derived from chitin, which is a cellulose-like biopolymer distributed widely in nature, especially in crustaceans, insects, fungi and yeast. The present study was to investigate whether chitosan can be applied to animal and human bodies in order to reduce the bioavailability of radio-iron and -zinc in food. Chitosan inhibits dietary iron absorption only when rats eat on iron-deficient diet. The effectiveness of phytate (myo-inositol 1,2,3,4,5,6-hexakis dihydrogen phosphate) and chitosan in reducing the bioavailability of radio-zinc depend on the concentration of phytate and chitosan. Recently, the share of imported foods increased ca. 40% of Japanese total food consumption. Radioactivities in imported foods must be checked from the viewpoints of internal radiation for Japanese subjects. Concentrations of {sup 232}Th and {sup 238}U in some imported mineral waters were higher than domestic waters. However, internal doses of portable waters are negligible. Individual foodstuffs in major food groups (fish and shellfish, meats, mushrooms, root vegetables and so on), which contributed to some radionuclide intakes in Japanese, were also analyzed to clarify the critical pathway in Japanese subjects. (author)

  2. Assessing unregulated ionizing radiation exposures of U.S. populations from conventional industries

    International Nuclear Information System (INIS)

    Pennington, Charles W.

    2006-01-01

    During the latter twentieth century, the public learned to fear perceived threats from emerging technologies. Concern about ionizing radiation became a persistent fear, causing protracted and often pointless debate. The twenty-first century offers new opportunities for this fear to cause public and political upset. Citizens and politicians know little about 'normal' radiation exposures caused by conventional industries. This paper summarizes ionizing radiation exposure assessments of several such industries, showing they deliver multiples of background radiation annually to millions of people, with even higher subpopulation doses due to lognormally distributed exposures. Such information may be useful in educating the public and in supporting comparative assessments or other forms of research on potential sources of public radiation exposure in the twenty-first century. By exposing people to information about normal radiation, we may hope to avoid some unfortunate policies and unnecessary regulatory responses, while abating needless public fear during this technologically challenging century

  3. Assessment of Human Exposures to Natural Sources of Radiation in Kenya

    International Nuclear Information System (INIS)

    Mustapha, A.O.; Patel, J.P.

    1999-01-01

    Levels of exposures to different components of natural background radiation in Kenya were assessed from measured data and published conversion factors. Among them, the average annual per capital effective dose from terrestrial external radiation is 0.76 mSv and the annual per capital effective dose from external exposure to cosmic radiation at ground levels is 0.41 mSv. The total average annual effective dose is greater than the global average. Also among the measured data, concentrations of radon ( 222 Rn) vary from 5 to 1200 Bq m -3 in indoor air of dwellings, and from 1 to 410 KBq m -3 in drinking water. An unusual pathway to internal exposure was discovered among the female population who engage in consumption of some earth materials, some of which are rich in thorium

  4. Dosimetry for occupational exposure to cosmic radiation

    International Nuclear Information System (INIS)

    Bartlett, D.T.; McAulay, I.R.; Schrewe, U.J.

    1997-01-01

    Aircraft crew and frequent flyers are exposed to elevated levels of cosmic radiation of galactic and solar origin and secondary radiation produced in the atmosphere, aircraft structure, etc. This has been recognised for some time and estimates of the exposure of aircraft crew have been made previously and included in, for example, UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation) publications. The recent increased interest has been brought about by several factors - the consideration that the relative biological effectiveness of the neutron component was being underestimated; the trend towards higher cruising altitudes for subsonic commercial aircraft and business jet aircraft; and most importantly, the recommendations of the International Commission on Radiological Protection (ICRP) in Publication 60, and the revision of the Euratom Basic Safety Standards Directive (BSS). In 1992, the European Dosimetry Group (EURADOS) established a Working Group to consider the exposure to cosmic radiation of aircraft crew, and the scientific and technical problems associated with radiation protection dosimetry for this occupational group. The Working Group was composed of fifteen scientists (plus a corresponding member) involved in this field of study and with knowledge of radiation measurement at aviation altitudes. This paper is based on the findings of this Working Group. (author)

  5. Effects of prenatal exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Miller, R.W.

    1990-01-01

    Prenatal exposure to ionizing radiation induces some effects that are seen at birth and others that cannot be detected until later in life. Data from A-bomb survivors in Hiroshima and Nagasaki show a diminished number of births after exposure under 4 wk of gestational age. Although a wide array of congenital malformations has been found in animal experimentation after such exposure to x rays, in humans only small head size (exposure at 4-17 wk) and mental retardation (exposure primarily at 8-15 wk) have been observed. In Hiroshima, small head size occurred after doses of 0.10-0.19 Gy or more, and an excess of mental retardation at 0.2-0.4 Gy or more. Intelligence test scores were reduced among A-bomb survivors exposed at 8-15 wk of gestational age by 21-29 IQ points per Gy. Other effects of in-utero exposure to atomic radiation include long-lasting complex chromosome abnormalities

  6. Effects of prenatal exposure to ionizing radiation

    Energy Technology Data Exchange (ETDEWEB)

    Miller, R.W. (National Cancer Institute, Bethesda, MD (USA))

    1990-07-01

    Prenatal exposure to ionizing radiation induces some effects that are seen at birth and others that cannot be detected until later in life. Data from A-bomb survivors in Hiroshima and Nagasaki show a diminished number of births after exposure under 4 wk of gestational age. Although a wide array of congenital malformations has been found in animal experimentation after such exposure to x rays, in humans only small head size (exposure at 4-17 wk) and mental retardation (exposure primarily at 8-15 wk) have been observed. In Hiroshima, small head size occurred after doses of 0.10-0.19 Gy or more, and an excess of mental retardation at 0.2-0.4 Gy or more. Intelligence test scores were reduced among A-bomb survivors exposed at 8-15 wk of gestational age by 21-29 IQ points per Gy. Other effects of in-utero exposure to atomic radiation include long-lasting complex chromosome abnormalities.

  7. Modelling of aircrew radiation exposure during solar particle events

    Science.gov (United States)

    Al Anid, Hani Khaled

    In 1990, the International Commission on Radiological Protection recognized the occupational exposure of aircrew to cosmic radiation. In Canada, a Commercial and Business Aviation Advisory Circular was issued by Transport Canada suggesting that action should be taken to manage such exposure. In anticipation of possible regulations on exposure of Canadian-based aircrew in the near future, an extensive study was carried out at the Royal Military College of Canada to measure the radiation exposure during commercial flights. The radiation exposure to aircrew is a result of a complex mixed-radiation field resulting from Galactic Cosmic Rays (GCRs) and Solar Energetic Particles (SEPs). Supernova explosions and active galactic nuclei are responsible for GCRs which consist of 90% protons, 9% alpha particles, and 1% heavy nuclei. While they have a fairly constant fluence rate, their interaction with the magnetic field of the Earth varies throughout the solar cycles, which has a period of approximately 11 years. SEPs are highly sporadic events that are associated with solar flares and coronal mass ejections. This type of exposure may be of concern to certain aircrew members, such as pregnant flight crew, for which the annual effective dose is limited to 1 mSv over the remainder of the pregnancy. The composition of SEPs is very similar to GCRs, in that they consist of mostly protons, some alpha particles and a few heavy nuclei, but with a softer energy spectrum. An additional factor when analysing SEPs is the effect of flare anisotropy. This refers to the way charged particles are transported through the Earth's magnetosphere in an anisotropic fashion. Solar flares that are fairly isotropic produce a uniform radiation exposure for areas that have similar geomagnetic shielding, while highly anisotropic events produce variable exposures at different locations on the Earth. Studies of neutron monitor count rates from detectors sharing similar geomagnetic shielding properties

  8. Air crew exposure to cosmic radiation. New analysis, recommendations EURADOS

    Energy Technology Data Exchange (ETDEWEB)

    Spurny, F; Votockova, I [Academy of the Sciences of Czech Republic, Prague (Czech Republic). Nuclear Physics Institute, Department of Radiation Dosimetry

    1996-12-31

    Cosmic radiation on the board of an aircraft consist of two components: directly ionizing radiation (electron, proton - low LET) and neutrons (high LET). Neither composition nor the energy spectrum of usual on-Earth calibration sources ({sup 60}Co, {sup 252}Cf) do not correspond to the field on a board. Therefore high energy reference fields behind shielding high energy accelerator at CERN and Dubna have been created and intensively studied. Their typical characteristics following from the results of our measurements were obtained. In-flight measurements on the board of commercial aircraft have been realized since 1991 during about 20 flights, Flight routes extended from the 1.3 grad N up to about 65 grad N, flying altitudes varied from 8.2 km to 12.5 km. The exposure level due to galactic cosmic radiation is inversely proportional to the solar activity. Some radiation protection aspects were concluded: (a) The usual limits of annual air crew flight hours correspond at 11.3 km to about 4 mSv per year, with new ICRP conversion factors to about 5 mSv per year; (b) Monthly flight hours limit does not exclude that the exposure of a pregnant women can exceed 1 mSv during this period; (c) The air crew exposure should therefore be checked, controlled a nd administered as conscientiously as for any other group of occupationally exposed persons. A Working group 11 of EURADOS `Exposure of air crew to cosmic radiation` has been formed (1992-1995) to prepare basic analysis and recommendations concerning the topics. (Abstract Truncated)

  9. Diagnostic radiation exposure in pediatric trauma patients.

    Science.gov (United States)

    Brunetti, Marissa A; Mahesh, Mahadevappa; Nabaweesi, Rosemary; Locke, Paul; Ziegfeld, Susan; Brown, Robert

    2011-02-01

    The amount of imaging studies performed for disease diagnosis has been rapidly increasing. We examined the amount of radiation exposure that pediatric trauma patients receive because they are an at-risk population. Our hypothesis was that pediatric trauma patients are exposed to high levels of radiation during a single hospital visit. Retrospective review of children who presented to Johns Hopkins Pediatric Trauma Center from July 1, 2004, to June 30, 2005. Radiographic studies were recorded for each patient and doses were calculated to give a total effective dose of radiation. All radiographic studies that each child received during evaluation, including any associated hospital admission, were included. A total of 945 children were evaluated during the study year. A total of 719 children were included in the analysis. Mean age was 7.8 (±4.6) years. Four thousand six hundred three radiographic studies were performed; 1,457 were computed tomography (CT) studies (31.7%). Average radiation dose was 12.8 (±12) mSv. We found that while CT accounted for only 31.7% of the radiologic studies performed, it accounted for 91% of the total radiation dose. Mean dose for admitted children was 17.9 (±13.8) mSv. Mean dose for discharged children was 8.4 (±7.8) mSv (pcumulative radiation exposure can be high. In young children with relatively long life spans, the benefit of each imaging study and the cumulative radiation dose should be weighed against the long-term risks of increased exposure.

  10. Application of maximum values for radiation exposure and principles for the calculation of radiation dose

    International Nuclear Information System (INIS)

    2000-01-01

    The guide sets out the mathematical definitions and principles involved in the calculation of the equivalent dose and the effective dose, and the instructions concerning the application of the maximum values of these quantities. further, for monitoring the dose caused by internal radiation, the guide defines the limits derived from annual dose limits (the Annual Limit on Intake and the Derived Air Concentration). Finally, the guide defines the operational quantities to be used in estimating the equivalent dose and the effective dose, and also sets out the definitions of some other quantities and concepts to be used in monitoring radiation exposure. The guide does not include the calculation of patient doses carried out for the purposes of quality assurance

  11. Application of maximum values for radiation exposure and principles for the calculation of radiation dose

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The guide sets out the mathematical definitions and principles involved in the calculation of the equivalent dose and the effective dose, and the instructions concerning the application of the maximum values of these quantities. further, for monitoring the dose caused by internal radiation, the guide defines the limits derived from annual dose limits (the Annual Limit on Intake and the Derived Air Concentration). Finally, the guide defines the operational quantities to be used in estimating the equivalent dose and the effective dose, and also sets out the definitions of some other quantities and concepts to be used in monitoring radiation exposure. The guide does not include the calculation of patient doses carried out for the purposes of quality assurance.

  12. Predicted Radiation Exposure from Mining at Kvanefjeld

    DEFF Research Database (Denmark)

    Nielsen, Sven Poul; Roos, Per; Andersson, Kasper Grann

    Baseline surveys of gamma radiation and environmental radioactivity have been carried out by Greenland Minerals and Energy Ltd (GMEL) to show existing levels in the town of Narsaq and in the Kvanefjeld project area. Radiation levels in Narsaq are low but elevated in the project area due the prese......Baseline surveys of gamma radiation and environmental radioactivity have been carried out by Greenland Minerals and Energy Ltd (GMEL) to show existing levels in the town of Narsaq and in the Kvanefjeld project area. Radiation levels in Narsaq are low but elevated in the project area due...... the presence of large uranium and thorium deposits in Kvanefjeld. These deposits are also the reason that radon in outdoor air show elevated concentrations in Narsaq and in the project area. It is recommended that future monitoring of external exposure and radon should be based on measurement techniques using...

  13. Radiation exposure and radiation risk of the population

    International Nuclear Information System (INIS)

    Jacobi, W.; Paretzke, H.G.; Ehling, U.H.

    1981-02-01

    The major scientifically founded results concerning the assessment of the radiation exposure and the analysis and evaluation of the radiationhazards for the population, particularly in the range of low doses, are presented. As to the risk analysis special attention is paid to the rays with low ionization density (X-, γ-, β- and electronrays). Contents: 1) Detailed survey of the results and conclusions; 2) Data on the radiation load of the population; 3) Results to epidemiological questioning on the risk of cancer; 4) Genetical radiation hazards of the population. For quantification purposes of the risk of cancer by γ-radiation the observations with the a-bomb survivors in Japan are taken as a basis, as the available dosimetrical data have to be revised. Appendices: 1) German translation of the UNSCEAR-Report (1977); 2) BEIR-Report (1980); 3) Comments from the SSK on the comparability of the risks of natural-artificial radiation exposure; 4) Comments from the SSK on the importance of synergistical influences for the radiation protection (23.9.1977). (HP) [de

  14. Radiation exposure of the UK population

    International Nuclear Information System (INIS)

    Taylor, F.E.; Webb, G.A.M.

    1978-11-01

    Man is continuously exposed to radiation from many sources, both natural and man-made. The man-made sources include medical irradiation, exposure from radioactive waste disposal, fallout from nuclear weapons tests and various 'miscellaneous sources' which include consumer products. The National Radiological Protection Board (NRPB) keeps these contributions to the radiation exposure of the population under continuous review and publishes reports on the subject periodically. This is the second such report and contains considerably more information than the first published in 1974. The balance of the report reflects the availability of data and the advice given in the sixth report of the Royal Commission on Environmental Pollution. The conclusions are: (a) that the major contribution to the dose to the population is from natural background radiation; (b) that the largest man-made contribution is from medical uses of radiation; (c) that the largest contribution from environmental contamination is still from the residual effects of fallout from nuclear weapons testing; (d) that occupational exposure and irradiation from miscellaneous sources, considered as contributions to the per caput dose to the population, are the next largest components; (e) that radioactive waste disposal is the smallest contributor to the per caput dose to the population. It was also felt useful to review the past trends in the doses resulting from the various sources and the authors have attempted to make some tentative predictions of doses up to the year 2000. (author)

  15. A review of child medical radiation exposure

    International Nuclear Information System (INIS)

    Anon.

    2017-01-01

    During their first year, children may undergo a lot of X-ray exams: of hips at the age of 4 months to detect any deformities, of lungs to detect bronchiolitis, of bones to detect breaks, of jaw (dental panoramic) to prepare for possible medical care in orthodontics. A survey shows that the medical radiation dose received by children is less than 0.35 mSv a year while the average dose for an adult is 4.5 mSv. This figure is reassuring but children exposure needs to be carefully monitored as children are more sensitive to radiation because they are growing. The control of radiation exposure is made through a compulsory survey: every year radiologists must send to the IRSN (Institute for Radioprotection and Nuclear Safety) the radiation doses received by 30 patients for the most common radiological examinations and the IRSN will then define reference doses based on these figures. The feedback over the 2013-2015 period for children exposure is very low. A new methodology must be defined to compensate this lack of data. The strategy is to reduce the global dose by performing only fully justified examinations and to adapt the dose to the real size and weight of the child. (A.C.)

  16. Justification of novel practices involving radiation exposure

    International Nuclear Information System (INIS)

    Webb, G.; Boal, T.; Mason, C.; Wrixon, T.

    2006-01-01

    The concept of 'justification' of practices has been one of the three basic principles of radiation protection for many decades. The principle is simple in essence - that any practice involving radiation exposure should do more good than harm. There is no doubt that the many uses of radiation in the medical field and in industry generally satisfy this principle, yielding benefits that could not be achieved using other techniques; examples include CT scanning and industrial radiography. However, even in the early period after the introduction of the justification principle, there were practices for which the decision on justification was not clear and for which different decisions were made by the authorities in different countries. Many of these involved consumer products such as luminous clocks and watches, telephone dials, smoke detectors, lightning preventers and gas mantles. In most cases, these practices were relatively small scale and did not involve large exposures of either individual workers or members of the public. Decisions on justification were therefore often made by the regulator without extensive national debate. Over recent years, several practices have been proposed and undertaken that involve exposure to radiation for purposes that were generally not envisaged when the current system of radiation protection was created. Some of these practices were reviewed during a recent symposium held in Dublin, Ireland and involve, for example, the x-raying of people for theft detection purposes, for detection of weapons or contraband, for the prediction of physical development of young athletes or dancers, for age determination, for insurance purposes and in cases of suspected child abuse. It is particularly in the context of such novel practices that the need has emerged for clearer international guidance on the application of the justification principle. This paper reviews recent activities of the IAEA with respect to these issues, including the

  17. Justification of novel practices involving radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Webb, G. [Radiation Protection Consul tant, Brighton (United Kingdom); Boal, T.; Mason, C.; Wrixon, T. [International Atomic Energy Agency, Vienna (Austria)

    2006-07-01

    The concept of 'justification' of practices has been one of the three basic principles of radiation protection for many decades. The principle is simple in essence - that any practice involving radiation exposure should do more good than harm. There is no doubt that the many uses of radiation in the medical field and in industry generally satisfy this principle, yielding benefits that could not be achieved using other techniques; examples include CT scanning and industrial radiography. However, even in the early period after the introduction of the justification principle, there were practices for which the decision on justification was not clear and for which different decisions were made by the authorities in different countries. Many of these involved consumer products such as luminous clocks and watches, telephone dials, smoke detectors, lightning preventers and gas mantles. In most cases, these practices were relatively small scale and did not involve large exposures of either individual workers or members of the public. Decisions on justification were therefore often made by the regulator without extensive national debate. Over recent years, several practices have been proposed and undertaken that involve exposure to radiation for purposes that were generally not envisaged when the current system of radiation protection was created. Some of these practices were reviewed during a recent symposium held in Dublin, Ireland and involve, for example, the x-raying of people for theft detection purposes, for detection of weapons or contraband, for the prediction of physical development of young athletes or dancers, for age determination, for insurance purposes and in cases of suspected child abuse. It is particularly in the context of such novel practices that the need has emerged for clearer international guidance on the application of the justification principle. This paper reviews recent activities of the IAEA with respect to these issues, including the

  18. Radiation Protection Institute Annual Report for 2013

    International Nuclear Information System (INIS)

    2013-01-01

    The report covers the activities of the Radiation Protection Institute (RPI) of the Ghana Atomic Energy Commission for the year 2013. The report is grouped under the following headings: establishment, vision and mission; personnel and organization; major activities and research projects; IAEA, Technical Cooperation and AFRA projects; ongoing research projects and programs; income and expenditure statements, physical development and human resource development, training courses, meetings and conferences. (A. B.)

  19. Radiation Protection Institute Annual Report for 2012

    International Nuclear Information System (INIS)

    2012-01-01

    The report covers the activities of the Radiation Protection Institute (RPI) of the Ghana Atomic Energy Commission for the year 2012. It is grouped under the following topics: vision and mission; personnel, major activities, research projects, IAEA Technical Cooperation and AFRA projects; ongoing research projects and programs. Also included are income and expenditure statements, physical and human resource development; IAEA training courses, national and IAEA training courses and meetings hosted; and publications. (A. B.)

  20. Reducing occupational radiation exposures at LWRs

    International Nuclear Information System (INIS)

    Lattanzi, D.; Neri, C.; Papa, C.; Paribelli, S.

    1980-01-01

    The occupational radiation doses received by nuclear power plant personnel during a period of several years of operation are briefly reviewed. Comparisons are made between the data for BWRs and PWRs in order to identify the more ''critical'' reactor type, from a radiological poin; of view. Attention is also devoted to GCRs. Furthermore the areas which contribute most to personnel doses are considered and briefly reviewed. The main steps to be taken in order to reduce occupational radiation exposures at LWRs are discussed. (H.K.)

  1. Distribution of Radiation Exposure from Natural Radiation in Big Cities

    International Nuclear Information System (INIS)

    Udiyani, P.M.; Ahmad, Yus R.

    2000-01-01

    The measurement of radiation exposure from the natural radiation in the big city in Java such as Jakarta, Bandung, Semarang, Yogyakarta, and Surabaya have be done. Based on radiation dose and population at the sample location, the dose collective and risk probability will be know. The maximal exposure at Yogyakarta is 0.291 mSv/year and the minimal exposure at Surabaya is 0.216 mSv/year. Collective dose at Jakarta is 1.649.526 men mSv/year; Bandung 124.844 men mSv/year; Semarang : 64.558 men mSv/year; Yogyakarta 136.188 men mSv/year; and Surabaya 145.152 men mSv/year. The person probability of radiation disease at jakarta is 16.49 person/year, Bandung is 1.24 person/year, Semarang 1.64 person/year, Yogyakarta is 1.36 person/year, and Surabaya is 1.45 person/year

  2. Radiation exposure during air and ground transportation

    International Nuclear Information System (INIS)

    Hsu, P.C.; Weng, P.S.

    1976-01-01

    The results of a one year study program of radiation exposure experienced on both domestic and international flights of the China Airline and the Far East Airline in the Pacific, Southeast Asia and Taiwan areas and on trains and buses on Taiwan island are reported. CaSO 4 :Dy thermoluminescent dosimeters were used. It has been shown that transit exposures may amount to 10 times that on the ground with an altitude varying from 3,050 to 12,200 m. (U.K.)

  3. Personnel radiation exposure in HTGR plants

    International Nuclear Information System (INIS)

    Su, S.; Engholm, B.A.

    1981-01-01

    Occupational radiation exposures in high-temperature gas-cooled reactor (HTGR) plants were assessed. The expected rate of dose accumulations for a large HTGR steam cycle unit is 0.07 man-rem/MW(e)y, while the design basis is 0.17 man-rem/MW(e)y. The comparable figure for actual light water reactor experience is 1.3 man-rem/MW(e)y. The favorable HTGR occupational exposure is supported by results from the Peach Bottom Unit No. 1 HTGR and Fort St. Vrain HTGR plants and by operating experience at British gas-cooled reactor stations

  4. Electromagnetic Radiation Exposure from Cellular Base Station: A ...

    African Journals Online (AJOL)

    Electromagnetic Radiation Exposure from Cellular Base Station: A Concern for Public ... as well as safety guidelines relating to exposure of non-ionizing radiation. Global System for Mobile Communication (GSM) operators claimed that their ...

  5. Radically Reducing Radiation Exposure during Routine Medical Imaging

    Science.gov (United States)

    Exposure to radiation from medical imaging in the United States has increased dramatically. NCI and several partner organizations sponsored a 2011 summit to promote efforts to reduce radiation exposure from medical imaging.

  6. Pediatric radiation exposure from diagnostic nuclear medicine examinations in Tehran

    International Nuclear Information System (INIS)

    Neshandar Asli, I.; Tabeie, F.

    2005-01-01

    As a part of a nationwide survey to estimate population exposure to radiation from diagnostic nuclear medicine in Iran, this paper presents the pediatric population radiation exposure due to nuclear medicine examinations in Tehran. Patients and methods: the effective dose equivalent, H E , was used to calculate the collective effective dose in pediatric patients undergoing nuclear medicine procedures, and the corresponding data were obtained from thirty out of thirty seven active nuclear medicine departments in Tehran. Results: annually about 5.26% of nuclear medicine examinations were performed on patients under 15 years of age in Tehran. The most frequent was renal examinations (38.2%), followed y thyroid (27.4%) and bone (26.7%). The annual collective H E for patients under 15 was 19.03 human-Sv, which contributed 3.96% to the collective H E for all patients. The contribution of renal, bone and thyroid examinations to the pediatric collective H E were 24.6% 48.8% and 13.5% respectively. The mean effective dose equivalent per pediatric patient was 3.75 mSv.Conclusion: Among the three most frequent examinations, the bone with a relative frequency of 27.4% constituted 48.8% of the collective H E , which was the highest absorbed dose per examination. The mean effective dose per examination for patients younger than 15 years was 67.9% of the adults

  7. Contribution of cosmic rays to radiation exposure of the population

    International Nuclear Information System (INIS)

    Sztanyik, L.B.; Nikl, I.

    1982-01-01

    To evaluate the exposure of the Hungarian population to cosmic rays, the absorbed dose rate in air of cosmic radiation was directly measured by high pressure ionization chamber at ground level on the surface of different bodies of water and at various altitudes on the board of an aircraft. From the dose rates measured this way, the outdoor dose equivalent rate from the ionizing components of cosmic radiation to people living at sea level would be 300-325 μSv per year. Taking into account the altitude distribution of the population, the average weighted dose equivalent is about 320 μSv per year. At Kekestetoe, the highest peak of the Matra Mountains, (the highest altitude in Hungary), the annual dose equivalent is about 50 per cent higher than on the Great Hungarian Plain. (author)

  8. Radiation protection programme for existing exposure situation

    International Nuclear Information System (INIS)

    Ramadhani, Hilali Hussein

    2016-04-01

    This study was conducted to develop the Radiation protection Programme (RPP) to ensure that measures are in place for protection of individuals from the existing source of exposure. The study established a number of protective and remedial actions to be considered by the responsible regulatory Authority, licensee for existing exposure in workplace and dwellings. Tanzania is endowed with a number NORMs processing industries with an experience of uncontrolled exploration and extraction of minerals and the use of unsafe mining methods leading to severe environmental damage and appalling living conditions in the mining communities. Some of NORMs industries have been abandoned due to lack of an effect management infrastructure. The residual radioactive materials have been found to be the most import source of existing exposure resulted from NORMs industries. The Radon gas and its progeny have also been found to be a source of existing exposure from natural source as well as the major source of risk and health effects associated with existing exposure situation. The following measures have been discovered to play a pivotal role in avoiding or reducing the source of exposure to individuals such as restriction of the use of the construction materials, restriction on the consumption of foodstuffs and restriction on the access to the land and buildings, the removal of the magnitude of the source in terms of activity concentration as well as improvement of ventilation in dwellings. Therefore, the regulatory body (Tanzania Atomic Energy Commission) should examine the major areas outlined in the established RRP for existing exposure situation resulted from the NORMs industries and natural sources so as to develop strategies that will ensure the adequate protection of members of the public and the environment as well as guiding operating organizations to develop radiation protection and safety measures for workers. (au)

  9. Radiation protection of aviation personnel at exposure by cosmic radiation

    International Nuclear Information System (INIS)

    Vicanova, M.; Pinter, I.; Liskova, A.

    2008-01-01

    For determination of radiation dose of aviation personnel we used the software EPCARD (European Program Package for the Calculation of Aviation Route Doses) developed by National Research Center for Environmental Health - Institute of Radiation Protection (Neuherberg, Germany) and the software CARI 6, developed by the FAA's Civil Aerospace Medical Institute (USA). Both codes are accomplished by the Joint Aviation Authorities. Experimental measurement and estimation of radiation doses of aviation personnel at exposure by cosmic radiation were realised in the period of lowered solar activity. All-year effective dose of pilots, which worked off at least 11 months exceeds the value 1 mSv in 2007. The mean all-year effective dose of member of aviation personnel at exposure by cosmic radiation is 2.5 mSv and maximal all-year effective dose, which we measured in 2007 was 4 mSv. We assumed that in the period of increased solar activity the all-year effective doses may by higher

  10. Population exposure to ionising radiation in India

    International Nuclear Information System (INIS)

    Narayanan, K.K.; Krishnan, D.; Subba Ramu, M.C.

    1991-01-01

    Estimates of exposure from various radiation sources to Indian population are given. The per caput dose from all the identifiable sources, both natural and man-made is estimated to be 2490 μSv per year to the present population of India. 97.9% of this dose is contributed by natural sources which include cosmic and terrestrial radiations, 1.93% by medical sources used for diagnostic and treatment purpose, 0.3% by exposures due to activities related nuclear fuel cycle, nuclear tests and nuclear accidents, and 0.07% by miscellaneous sources such as industrial applications, consumer products, research activities, air travel etc. The monograph is written for the use of the common man. (M.G.B.). 25 refs., 7 tabs., 7 figs

  11. Occupational Exposure to Diagnostic Radiology in Workers without Training in Radiation Safety

    International Nuclear Information System (INIS)

    Gaona, Enrique; Enriquez, Jesus G. Franco

    2004-01-01

    The physicians, technicians, nurses, and others involved in radiation areas constitute the largest group of workers occupationally exposed to man-made sources of radiation. Personnel radiation exposure must be monitored for safety and regulatory considerations, this assessment may need to be made over a period of one month or several months. The purpose of this study was to carry out an exploratory survey of occupational exposures associated with diagnostic radiology. The personnel dosimeters used in this study were thermoluminescent dosimeters (TLDs). The reported number of monitored workers was 110 of different departments of radiology of the Mexican Republic without education in radiation safety, included general fluoscopic/radiographic imaging, computed tomography and mammography procedures. Physicians and X-ray technologist in diagnostic radiology receive an average annual effective dose of 2.9 mSv with range from 0.18 to 5.64 mSv. The average level of occupational exposures is generally similar to the global average level of natural radiation exposure. The annual global per capita effective dose due to natural radiation sources is 2.4 mSv (UNSCEAR 2000 Report). There is not significant difference between average occupational exposures and natural radiation exposure for p < 0.05

  12. Radiation Protection Board. Annual report for the year 1998

    International Nuclear Information System (INIS)

    1999-05-01

    The annual report of the Radiation Protection Board (RPB) of the Ghana Atomic Energy Commission for the year 1998 is presented. The report presents a summary of the RPB's activities grouped under the following headings: regulatory activities; technical services; income and expenditure frame work; research and publications; education and training; problems and conclusion

  13. Controlling occupational radiation exposure. Alternatives to regulation

    International Nuclear Information System (INIS)

    Sagan, L.A.; Squitieri, R.; Wildman, S.S.

    1980-01-01

    The principal strategy adopted for the control of occupational radiation exposure has been the establishment of standards expressed as maximum permissible exposures. The use of such standards is subject to a number of defects, among which is the neglect of the economic impact of imposing such standards. Furthermore, such standards carry the implication of a threshold for radiation effects, a concept now widely challenged. Lastly, the use of standards makes it impossible to evaluate the efficiency of the regulatory agency or to compare its performance with other similar agencies. An alternative to the use of standards, i.e. cost-benefit analysis, is discussed. The advantages of this technique meet many of the objections to the use of standards alone and allow health and safety resources to be allocated in a manner most likely to save the most lives. The greatest disadvantage of cost-benefit analysis has been the difficulty in evaluating the benefit side of the equation. Although the risks of radiation exposure are not known with precision, they are nevertheless well understood. Therefore, the application of cost-benefit analysis to occupational radiation exposure is rational. There are a number of barriers to reform in the use of standards and the adoption of cost-benefit analysis. These attitudinal and institutional constraints are discussed. The nature of private or market systems of control are discussed, i.e. the use of liability and insurance mechanisms. These also have shortcomings that require further development but are seen as potentially more efficient for both employer and employee than is the use of regulatory standards. (author)

  14. Assessment of Aircrew Radiation Exposure by further measurements and model development

    International Nuclear Information System (INIS)

    Lewis, B. J.; Desormeaux, M.; Green, A. R.; Bennett, L. G. I.; Butler, A.; McCall, M.; Saez Vergara, J. C.

    2004-01-01

    A methodology is presented for collecting and analysing exposure measurements from galactic cosmic radiation using a portable equipment suite and encapsulating these data into a semi-empirical model/Predictive Code for Aircrew Radiation Exposure (PCAIRE) for the assessment of aircrew radiation exposure on any flight over the solar cycle. The PCAIRE code has been validated against integral route dose measurements at commercial aircraft altitudes during experimental flights made by various research groups over the past 5 y with code predictions typically within ±20% of the measured data. An empirical correlation, based on ground-level neutron monitoring data, is detailed further for estimation of aircrew exposure from solar particle events. The semi-empirical models have been applied to predict the annual and career exposure of a flight crew member using actual flight roster data, accounting for contributions from galactic radiation and several solar energetic-particle events over the period 1973-2002. (authors)

  15. Consideration on a limit for lifetime occupational radiation exposure

    International Nuclear Information System (INIS)

    Kellerer, A.M.

    1998-01-01

    Annual dose limits in occupational radiation exposure are merely a secondary constraint in addition to the primary rule of dose reduction and justification. The limits may, therefore, be reached only in rare, special cases. However, in principle, there might be cases in which the annual limit is continuously exhausted throughout a working life; a high total dose of 0.8 Sv could then be reached. In view of this possibility, there have been considerations of an added restriction by limiting the lifetime occupational dose to 0.4 Sv. The implications of such lifetime doses are considered, and it is shown that an exposure up to the maximum of 0.8 Sv will lead to the need for compensation, if a leukaemia were to occur in the exposed worker. A lifetime dose of 0.4 Sv equally spread over a working life will not lead to the critical value of the probability of causation in excess of 0.5. Nevertheless, it could cause such critical values when it is accumulated during shorter periods. More decisive than the probabilities of causation are, however, the absolute numbers of excess cases of leukaemia due to the occupational exposure. It is seen that less than one excess case would be expected if a group of 100 workers were all exposed to the maximum of 0.8 Sv. Since lifetime doses of 0.8 or 0.4 Sv will be accumulated in very few cases and only with special justification, there appears to be little need to introduce a further limit of lifetime exposure in addition to the current annual limit. (orig.)

  16. Microwave radiation - Biological effects and exposure standards

    Energy Technology Data Exchange (ETDEWEB)

    Lindsay, I.R.

    1980-06-01

    The thermal and nonthermal effects of exposure to microwave radiation are discussed and current standards for microwave exposure are examined in light of the proposed use of microwave power transmission from solar power satellites. Effects considered include cataractogenesis at levels above 100 mW/sq cm, and possible reversible disturbances such as headaches, sleeplessness, irritability, fatigue, memory loss, cardiovascular changes and circadian rhythm disturbances at levels less than 10 mW/sq cm. It is pointed out that while the United States and western Europe have adopted exposure standards of 10 mW/sq cm, those adopted in other countries are up to three orders of magnitude more restrictive, as they are based on different principles applied in determining safe limits. Various aspects of the biological effects of microwave transmissions from space are considered in the areas of the protection of personnel working in the vicinity of the rectenna, interactions of the transmitted radiation with cardiac pacemakers, and effects on birds. It is concluded that thresholds for biological effects from short-term microwave radiation are well above the maximal power density of 1 mW/sq cm projected at or beyond the area of exclusion of a rectenna.

  17. Radiation exposures due to fossil fuel combustion

    Science.gov (United States)

    Beck, Harold L.

    The current consensus regarding the potential radiation exposures resulting from the combustion of fossil fuels is examined. Sources, releases and potential doses to humans are discussed, both for power plants and waste materials. It is concluded that the radiation exposure to most individuals from any pathway is probably insignificant, i.e. only a tiny fraction of the dose received from natural sources in soil and building materials. Any small dose that may result from power-plant emissions will most likely be from inhalation of the small insoluble ash particles from the more poorly controlled plants burning higher than average activity fuel, rather than from direct or indirect ingestion of food grown on contaminated soil. One potentially significant pathway for exposure to humans that requires further evaluation is the effect on indoor external γ-radiation levels resulting from the use of flyash in building materials. The combustion of natural gas in private dwellings is also discussed, and the radiological consequences are concluded to be generally insignificant, except under certain extraordinary circumstances.

  18. Lung cancer following exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Blot, W.J.

    1985-01-01

    A case-control study of lung cancer was conducted in Hiroshima and Nagasaki, Japan, to evaluate risk factors for this common neoplasm, with special attention given to assessing the potentially interactive roles of cigarette smoking and atomic radiation. The investigation involved interviews with 428 patients with primary lung cancer and 957 matched controls, or with their next of kin in the event of death or disability. The interview information was supplemented by data on atomic bomb radiation exposure for each individual and on smoking and other factors from prior surveys of subsets of the population studied. Separate effects of smoking and high dose (greater than 100 rad) radiation were found, with the two exposures combining to affect lung cancer risk in an approximate additive fashion. The additive rather than multiplicative model was favored whether the smoking variable was dichotomized (ever vs. never smoked), categorized into one of several groups based on amount smoked, or treated as a discrete variable. The findings are contrasted with those for Colorado uranium miners and other cohorts occupationally exposed to radon and its daughter products, where smoking and radiation have been reported to combine multiplicatively to enhance lung cancer risk

  19. Unjustified prenatal radiation exposure in medical applications

    International Nuclear Information System (INIS)

    Cardenas Herrera, J.; Lamadrid, A.I.; Garcia Lima, O.; Diaz Bernal, E.; Freixas, V.; Lopez Bejerano, G.; Sanchez, R.

    2001-01-01

    The exposure to the radiation ionising of pregnant women, frequently constitutes motive of preoccupation for the expectant mother and the medical professionals taken the responsibility with its attention. The protection of the embryo-fetus against the ionising radiation is of singular importance due to its special vulnerability to this agent. On the other hand the diagnosis or treatment with radiations ionising beneficial for the expectant mother, are only indirectly for the embryo-fetus that is exposed to a hazard without perceiving anything. The present paper presents the experience obtained in the clinical and dosimetric evaluation from twenty-one pregnant patients subjected to diverse radiodiagnostic procedures or nuclear medicine during the years 1999-2000. The obtained results evidence that 24% of the patients was subjected to procedures of nuclear medicine with diagnostic purposes. While the period of pregnancy of the patients ranged between 4 and 12 weeks, it could be concluded that in all the cases the doses received by the patients in the whole body did not exceed 2 mSv. When conjugating the period of pregnancy of the patients with the doses received, there is no evidence of significant risk for the embryo-fetus. Paradoxically the physicians of assistance suggested to their patients in all the cases to carry out the interruption of the pregnancy, demonstrating with this decision ignorance on the biological effects of the ionizing radiations during the prenatal exposures. (author)

  20. The natural sources of ionizing radiation exposure

    International Nuclear Information System (INIS)

    Maximilien, R.

    1982-01-01

    Natural sources of ionizing radiation include external sources (cosmic rays, natural radionuclides present in the crust of the earth and in building materials) and internal sources (naturally occuring radionuclides in the human body, especially the potassium 40 and radon short lived decay products). The principal ways of human exposure to theses different components in ''normal'' areas are reviewed; some examples of the variability of exposure with respect to different regions of the world or the habits of life are given. Actual estimations of the doses delivered to the organs are presented; for the main contributors to population exposure, the conversion into effective dose equivalent has been made for allowing a better evaluation of their respective importance [fr

  1. Annual individual hygienic assessment of natural exposure doses of the Altai territory model areas population

    Directory of Open Access Journals (Sweden)

    N. Yu. Potseluev

    2016-01-01

    Full Text Available The goal is to determine ionizing radiation natural sources exposure regularities of Altai Territory model areas population. The materials and methods. 11376 radon measurements, 1247 gamma radiation meas-urements in an open area and in residential and office buildings were performed, selection of 189 drinking water tests was carried out. Results. Complex radiation and hygienic examination of the region with the most large municipalities number with model areas allocation was conducted. The assessment of the Altai Territory population’s individual annual radiation doses from natural radionuclides has revealed a number of the regularities depending on the terrain’s ecological and geographical type. Following the research results, ranging the region territories taking into account of annual effective doses of the population from natural sources for 2009-2015 was carried out. The annual individual effective dose of the Altai Territory upland areas population presented by the highest values and ranges from 7.36 mSv / year to 8.19 mSv / year. Foothill regions of Altai and in Salair ridge are characterized by increased population exposure from natural sources. Here the dose ranges from 5.09 mSv / year to 6.22 mSv / year. Steppe and forest-steppe territories are characterized by the lowest level of the natural radiation which is ranging from 3.23 mSv / year to 4.11 mSv / year, that doesn’t exceed the all-Russian levels. Most of the hygienic radon equivalent equilibrium volume activity standards exceedances were registered in mountain and foothill areas buildings. A number of radon anomalies is revealed also in steppe areas. Med exceedances ranged from 203 ± 17.8 Bq / m3 to 480 ± 37.9 Bq / m3. Given the fact that most of these buildings belong to the administrative or educational institutions with an eight-hour working day, the dose of radiation for people there can be up to 10 mSv / year. Conclusion. Spreading of individual annual effective

  2. Monitoring and control of occupational radiation exposure in Switzerland

    International Nuclear Information System (INIS)

    Moser, M.

    1997-01-01

    Occupational exposure is the most prominent example for the prolonged exposure to low level ionizing radiation characterized by low doses and dose rates. In this paper the occupational exposure in Switzerland is presented and the regulatory control of this exposure in the framework of the new radiation protection regulations is discussed. (author)

  3. Sports injuries, drowning and exposure to radiation concern Canada Safety Council meeting

    International Nuclear Information System (INIS)

    Oliver, Caroline.

    1979-01-01

    Hazards associated with surface sports, aquatic sports and exposure to radiation were considered at a meeting of the Canada Safety Council in late 1979. The session on radiation noted that 6 of 20000 radiation workers wearing dosimeters were exposed to a dose in excess of 5 rem, the annual limit set by the Atomic Energy Control Board. Radiographers were in the job classification receiving the highest doses of ionizing radiation. Concern was expressed for the emission of damaging radiation from broken mercury vapour lamps. Increased regulation rather than training was seen as the most effective solution. (T.I.)

  4. The radiation exposure regulation for XXI century

    International Nuclear Information System (INIS)

    Keirim-Markus, I.B.

    2000-01-01

    The regulation of the people radiation exposure by the ICRP and IAEA is subject to well-founded criticism for the excessive severity and complexity. In Russia these shortcomings adversely affected at the removal of consequences of the Chernobyl accident. The future regulation system must be better coordinated with the other sources of human life risks. In the advanced countries the death probability from the all reasons is equal 1-2·10 -2 year -1 with the age variation from 5·10 -4 to 2·10 -1 . Therefore it is reasonable to consider that death risk from radiation less than 1·10 -5 - 1·10 -3 depending on age, as an insignificant, but not 1·10 -6 as it is accepted now. Whatever heritable effects of human irradiation are not revealed by the observation during a half on century. Therefore, there is no any reason to account them. As concern the dose dependence of the stochastic effects of radiation the new information is already demonstrating that more than an a half of the whole human's radiation cancers are submitted to dependence with the threshold from 0.3 to tens of sievert at the low dose rate. Therefore, the linear nonthreshold dependence is not true. This fact is undermining the modern system of irradiation regulation institution. One can't use the effective dose. One hasn't to fear of the radiation exposure in small doses. There isn't the necessity in optimization of such exposure all the more the balance detriment-benefit depends on not only dose but even not so much on dose. It is reasonable to base the future system regulation of radiation exposure with the only one principle: one mustn't exceed the limit of the personal life-span dose, which must be set at the level 2.5 Sv for the staff. The limit equal to 0.5 Sv during every 10 consecutive years will ensure that. For the population, the limit as 50-70 mSv during every 10 consecutive years will ensure the level 0.35-05 Sv for life-span. Equally, with the half century dose it is necessary to regulate

  5. Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2001

    International Nuclear Information System (INIS)

    Meyer, H.; Stippler, R.

    2002-01-01

    The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an unsignificant contribution. (orig./CB) [de

  6. Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2000

    International Nuclear Information System (INIS)

    Meyer, H.; Stippler, R.

    2001-01-01

    The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an unsignificant contribution. (orig./CB) [de

  7. Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 1999

    International Nuclear Information System (INIS)

    Meyer, H.; Stippler, R.

    2000-01-01

    The measuring activities for radiological monitoring in the mine and the surrounding area have been continued as usual, in compliance with the relevant programmes. As in previous years, low amounts of the nuclides H 3, C 14, Pb 210 and Rn 222, including Rn 220, and the short-life radon daughter products have been detected. In some cases, the nuclide-specific concentrations in ambient air derived from the annual average were below the mean natural concentrations of those nuclides. The relevant exposure data at the most affected measuring points remained far below the maximum permissible doses given in the Radiation Protection Ordinance. As compared to the natural and anthropogenic ambient radiation levels, the radiation exposure of the population in the area and the personnel on site, emanating from radioactive waste storage and performance of research projects in the Asse mine, represent an insignificant contribution. (orig./CB) [de

  8. Perinatal radiation exposure due to nuclear medical use of radioactive compounds

    International Nuclear Information System (INIS)

    Gloebel, B.

    1982-01-01

    When the pregnancy is yet undetected, radiation doses were only relevant when given within therapeutic application. Only Hg 203-chloromerodrine and J 131-iodide are relevant for newborns as they cause radiation doses of 40-70 rad. in the organ concerned. As a result of nuclear medicine and the application of radio nuclides not only patients but also ''occupationally exposed'' persons and parts of the population are exposed to radiation. Pregnant women are not admitted in control areas but can only be forbidden to enter when the pregnancy has been established. This is the case after six weeks. The occupational perinatal exposure is therefore about 11% of the annual dose. Evaluation of the figures for exposure to radiation can be done by either comparing them with natural exposure or by estimating the risks. The somatic radiation risk per rad is of the 5th order, the genetic risk of the 4th to 6th order as compared with a spontaneous genetic risk of the 2nd order. According to surveys of STIEVE (1976) the risk involved in various diagnostic and therapeutic measures of complications not due to radiation exposure is of 2nd to fifth order. On an average, the risks of diagnostic measures in nuclear medicine are small in comparison to the radiation risk. A comparison with the range of natural radiation exposure also indicated that only exposures which exceed natural exposure of 0.4 rad have to be considered. (orig.) [de

  9. Environmental radioactivity and radiation exposure in 2013; Umweltradioaktivitaet und Strahlenbelastung im Jahr 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    The report on the environmental radioactivity and radiation exposure in 2013 covers the natural radiation exposure due to radon, food, cosmic and terrestric radiation and the radiation exposure due to nuclear medicine nuclear facilities, mining, industry household and fallout. Special issues are the occupational radiation exposure the medical radiation exposure and the exposure to non-ionizing radiation.

  10. Cosmic Radiation Exposure of Future Hypersonic Flight Missions.

    Science.gov (United States)

    Koops, L

    2017-06-15

    Cosmic radiation exposure in air traffic grows with flight altitude, geographical latitude and flight time. For future high-speed intercontinental point-to-point travel, the trade-off between reduced flight time and enhanced dose rate at higher flight altitudes is investigated. Various representative (partly) hypersonic cruise missions are considered and in dependence on solar activity the integral route dose is calculated for envisaged flight profiles and trajectories. Our results are compared to those for corresponding air connections served by present day subsonic airliners. During solar maximum, we find a significant reduction in route dose for all considered high-speed missions compared to the subsonic reference. However, during solar minimum, comparable or somewhat larger doses result on transpolar trajectories with (partly) hypersonic cruise at Mach 5. Both solar activity and routing are hence found to determine, whether passengers can profit from shorter flight times in terms of radiation exposure, despite of altitude-induced higher dose rates. Yet, aircrews with fixed number of block hours are always subject to larger annual doses, which in the considered cases take values up to five times the reference. We comment on the implications of our results for route planning and aviation decision-making in the absence of radiation shielding solutions. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  11. Cosmic radiation exposure of future hypersonic flight missions

    International Nuclear Information System (INIS)

    Koops, L.

    2017-01-01

    Cosmic radiation exposure in air traffic grows with flight altitude, geographical latitude and flight time. For future high-speed intercontinental point-to-point travel, the trade-off between reduced flight time and enhanced dose rate at higher flight altitudes is investigated. Various representative (partly) hypersonic cruise missions are considered and in dependence on solar activity the integral route dose is calculated for envisaged flight profiles and trajectories. Our results are compared to those for corresponding air connections served by present day subsonic airliners. During solar maximum, we find a significant reduction in route dose for all considered high-speed missions compared to the subsonic reference. However, during solar minimum, comparable or somewhat larger doses result on transpolar trajectories with (partly) hypersonic cruise at Mach 5. Both solar activity and routing are hence found to determine, whether passengers can profit from shorter flight times in terms of radiation exposure, despite of altitude-induced higher dose rates. Yet, air crews with fixed number of block hours are always subject to larger annual doses, which in the considered cases take values up to five times the reference. We comment on the implications of our results for route planning and aviation decision-making in the absence of radiation shielding solutions. (author)

  12. Radiation exposure assessment for Portsmouth Naval Shipyard health studies

    International Nuclear Information System (INIS)

    Daniels, R. D.; Taulbee, T. D.; Chen, P.

    2004-01-01

    Occupational radiation exposures of 13,475 civilian nuclear shipyard workers were investigated as part of a retrospective mortality study. Estimates of annual, cumulative and collective doses were tabulated for future dose-response analysis. Record sets were assembled and amended through range checks, examination of distributions and inspection. Methods were developed to adjust for administrative overestimates and dose from previous employment. Uncertainties from doses below the recording threshold were estimated. Low-dose protracted radiation exposures from submarine overhaul and repair predominated. Cumulative doses are best approximated by a hybrid log-normal distribution with arithmetic mean and median values of 20.59 and 3.24 mSv, respectively. The distribution is highly skewed with more than half the workers having cumulative doses 95% having doses <100 mSv. The maximum cumulative dose is estimated at 649.39 mSv from 15 person-years of exposure. The collective dose was 277.42 person-Sv with 96.8% attributed to employment at Portsmouth Naval Shipyard. (authors)

  13. RISKAP, Risk Assessment of Radiation Exposure for Population

    International Nuclear Information System (INIS)

    1992-01-01

    1 - Description of program or function: RISKAP estimates risk to a population exposed to radioactivity. Risk is measured in terms of the expected number of premature deaths resulting from radiogenic cancers, the number of years of life lost as a result of these deaths, and the average number of years of life lost per premature death. RISKAP accommodates latency and plateau periods that vary with age at exposure and risk functions that vary with age at exposure as well as time after exposure. 2 - Method of solution: The user defines a population by specifying its size and age distribution at reference time zero, its subsequent age-specific mortality rates assuming no radiogenic deaths, and its subsequent birth rates. Radiation doses that may vary with age and time are also assigned by the user. These doses are used to compute an annual, age-specific risk of premature cancer death, based on a dose-response function selected by the user. Calculations of premature radiation deaths, deaths from all causes, and new age distribution of the population are performed for one-year intervals. The population is tracked over any specified period. This version of RISKAP allows the use of a linear, quadratic, or linear-quadratic dose-response function. The user may substitute any preferred dose-response function by editing the code. 3 - Restrictions on the complexity of the problem: None noted

  14. Radiation related cancer risk after ionization radiation exposure to the Bulgarian population

    International Nuclear Information System (INIS)

    Chobanova, N.; Vasilev, G.; Hadjieva, T.

    2008-01-01

    Average annual individual effective dose of natural radiation background (NRB) for the Bulgarian population is estimated to be 2.33 mSv.a -1 (from 1.60 to 3.06). NRB has been considered nearly constant in time, but during the 20th century the radiation above NRB has gradually increased. It was mainly caused by the medical X-ray and radionuclide diagnostics, radiation treatment, occupational radiation, global radioactive fallout, Chernobyl accident, exploitation of thermal power and nuclear power stations, etc. For the years 1950-2000 collective dose from NRB represents 965 000 man.Sv and radiation over NRB gives 1 042 800 man.Sv. Population risk following radiation exposure is estimated mainly on stochastic health effect by implementation of the so-called Linear non-threshold model (LNM) dose-effect. It postulates no dose threshold for radiation-induced health effects. Using different models, assumptions and assessments, authors have determined the contribution of lethal radiogenic cancer to Bulgarian spontaneous cancer rate to be from 3.7% to 20.6%. Numerous contradictions and concepts about the LNM still persist, because from statistical point of view, LNM can neither be proved nor rejected. (authors)

  15. Annual cycle of solar radiation in a deciduous forest

    International Nuclear Information System (INIS)

    Hutchison, B.A.; Matt, D.R.

    1977-01-01

    Periodic solar radiation measurements within and above an east Tennessee Liriodendron forest and continuous records of insolation from a nearby NOAA weather station were used to derive an approximation of the animal radiation regime within and above the deciduous forest. The interaction of changing solar elevations, insolation, and forest phenology are shown to control the radiation climate within the forest. Maximum radiation penetrates the forest in early spring as solar paths rise higher in the sky each day just prior to leaf expansion. After leaf expansion begins, average radiation received within the forest decreases rapidly despite continued increases in solar elevations and daily insolation. This forest attains full leaf in early June and from then until the advent of leaf abscission near the autumnal equinox, forest structure remains relatively static. Solar elevations and daily insolation decline following the summer solstice, however, and as a result, average radiation penetrating the forest slowly declines throughout the summer reaching an annual minimum in early autumn. With leaf fall, slightly increased amounts of radiation penetrate the forest but as within-forest solar paths continue to lengthen, radiation within the forest again declines. Minimum amounts of solar radiation penetrate the leafless forest around the winter solstice

  16. Radiation protection and environmental monitoring in the area of the Asse shaft plant. Annual report 1987

    International Nuclear Information System (INIS)

    Mueller-Lyda, I.; Meyer, H.

    1988-07-01

    Personnel monitoring has been carried through in compliance with the Radiation Protection Ordinance. Environmental monitoring including measurement of local doses, local dose rates, and airborne radioactivity in the shaft has been made according to the provisions for radiation protection at the place of work. Maximum permissible personal doses or activity levels for occupationally exposed persons have not been exceeded in the reporting period. Exhaust air monitoring detected the nuclides H-3, C-14, Pb-210, and the short-lived daughter products of Rn-222 and Rn-220. The activity concentrations in the environment, determined from the measured annual release values, for some part have been lower than the average of natural concentrations of said nuclides. The radiation exposure due to emissions, measured at the least favourable point in the environment, has been far below the limits set by the Radiation Protection Ordinance. In conclusion: The radiation exposure of the personnel and of the population in the area of the Asse shaft plant due to the storage of radioactive is low, compared to the natural radiation exposure. (orig.) [de

  17. Report on emergency exposure to external radiation

    International Nuclear Information System (INIS)

    Pochin, E.E.; Rock Carling, Ernest; Court Brown, W.M.

    1960-01-01

    The Medical Research Council has continued a study of the effects on the health of persons in the neighbourhood of atomic energy installations should there be a release of radioactive material as a result of fires or other incidents. The Council's Committee on Protection against Ionizing Radiations has already reported (Medical Research Council, 1959) on the maximum permissible dietary contamination for iodine 131, strontium 89, strontium 90 and caesium. 137, since it was considered that for the members of the public normally resident in the area affected ingestion of contaminated food would generally be the limiting source of hazard after any such accident and that intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances The present report deals with the problem of exposure from the exterior, namely, from external sources of beta and gamma radiation. This exposure might be derived from two sources, one of relatively short duration from the passage of a cloud of radioactive material, the other of longer duration from deposited material

  18. Patient radiation exposure in computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Pavlov, V [Meditsinska Akademiya, Sofia (Bulgaria)

    1980-01-01

    Radiation exposure to patients undergoing axial computerized tomography as a tool of neurological X-ray diagnostics was studied. Doses thereby delivered were compared with those from routine head films at X-ray tube parameters 200 W, 70 kV, and 70 cm target-to-patient distance. Radiation exposures were analyzed with a view to improving shielding and procedural techniques. Comparisons were made using LiF TLD measurements with an Alderson phantom (standard for axial computer tomography). Skin and intracranial space doses were compared using two computers, Siretom I and Siretom 2000, for various positionings: frontal, fronto-lateral, temporal, temporo-occipital, and occipital. In addition, patient body doses with or without shielding and doses to subjects attending sick children or restless adults were examined. Achievable protection was estimated for lead shields of 0.5 mm lead equivalent. It was concluded that radiation doses delivered to neurologic patients undergoing axial computer tomography are smaller than those resulting from conventional X-ray examinations.

  19. Report on emergency exposure to external radiation

    Energy Technology Data Exchange (ETDEWEB)

    Pochin, E E; Rock Carling, Ernest; Court Brown, W M [Medical Research Council, Committee on Protection against Ionizing Radiations, London (United Kingdom); and others

    1960-12-01

    The Medical Research Council has continued a study of the effects on the health of persons in the neighbourhood of atomic energy installations should there be a release of radioactive material as a result of fires or other incidents. The Council's Committee on Protection against Ionizing Radiations has already reported (Medical Research Council, 1959) on the maximum permissible dietary contamination for iodine 131, strontium 89, strontium 90 and caesium. 137, since it was considered that for the members of the public normally resident in the area affected ingestion of contaminated food would generally be the limiting source of hazard after any such accident and that intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances The present report deals with the problem of exposure from the exterior, namely, from external sources of beta and gamma radiation. This exposure might be derived from two sources, one of relatively short duration from the passage of a cloud of radioactive material, the other of longer duration from deposited material.

  20. Radiation protection programme for emergency exposure situations

    International Nuclear Information System (INIS)

    Amoah, Peter Atta

    2016-04-01

    An assessment of the Radiation Protection of Emergency Exposure Situations in Ghana was carried out in relation to documents provided by the International Atomic Energy Agency (IAEA). As realized in the document of the “Method for Developing Arrangements for Response to a Nuclear or Radiological Emergency” of the IAEA, the National Nuclear and Radiological Emergency Response Plan (NNRERP) of Ghana also discusses the Infrastructural and Functional Requirements necessary for the intervention of a nuclear or radiological emergency. The NNRERP describes the concept of operations for a response designed to facilitate the delivery of coordinated assistance to government authorities such as the National Disaster Management Organisation (NADMO), the Radiation Protection Board (RPB) and other participating organizations. From the NNRERP, practices in Ghana, fall into emergency planning category III and IV. As part of the planning measures, one of Ghana Atomic Energy Commission’s primary functions is to provide technical support with a mechanism for timely, interagency coordination of advice and recommendations to NADMO concerning protective actions, environmental concerns, health matters and other related matters. It has been realized from this assessment that there is an urgent need to upgrade infrastructure with logistics for training, exercises and drills to achieve its optimum expectations which will eventually lead to high level of confidence in meeting the standard of a Radiation Protection Programme in Emergency Exposure Situations. (au)

  1. Radiation Exposure to Concrete in Israel

    International Nuclear Information System (INIS)

    Haquin, G.; Kovler, K.; Yungrais, G. Z.; Lavi, N.

    2014-01-01

    Most building materials of terrestrial origin contain small amounts of radionuclides of natural origin, mainly from the Uranium (238U) and Thorium (232Th) decay chains and the radioactive isotope of potassium, 40K. The external radiation exposure is caused by gamma emitting radionuclides, which in the uranium series mainly belong to the decay chain segment starting with Radium (226Ra). The internal (by inhalation) radiation exposure is due to Radon (222Rn), and its short lived decay products, exhaled from building materials into the room air. Due to economical and environmental reasons there is an increased tendency to use industrial by-products containing relatively high concentrations of radionuclides of natural origin in the building material industry. Fly ash (FA), produced as by-product in the combustion of coal, is extensively used in Israel since mid eighties of the last century in concrete and as an additive to cement . The increase of 226Ra activity concentration, the mineralogical characteristics of the FA and of the concrete may influence on the radon exhalation rate and consequently on the radon exposure of the public. The recently published Israeli Standard 5098 (IS 5098) 'Content of natural radioactive elements in building products' limits the content of natural radionuclides as well as the radon emanation from concrete. This paper presents a compilation of three studies conducted at Soreq Nuclear Research Centre (SNRC), Technion, NRG and Environmental Lab BGU (ELBGU) to investigate and quantify the influence of FA addition in concrete

  2. Radiation exposure in medicare-occupational and medical exposure

    International Nuclear Information System (INIS)

    Morozumi, Kunihiko

    2012-01-01

    Recent cases of the occupational and medical exposures are discussed in relation to the justification of practice, optimization of protection and effort to reduce the dose. Instances of the occupational exposure in doctors and nurses like 26.5 mSv/15 mo and 53.9 mSv/y, and of skin cancer were reported in newspapers of 1999-2004, which might have had been prevented by their self evaluation of daily and monthly exposed dose. For reasonably lowering the occupational dose and number of exposed stuff in the present law, the prior radiation protection measures are to be taken in consideration of social/economical factors to conduct beneficial radiation medicare without restriction of practice under safest conditions, protecting personal determinative hazard and preventing stochastic effect. Medical stuff must be equipped with personal dosimeter. Further, recent media also commented such cases as unwished abortions after careless X-CT of pregnant women, and risk of increased cancer prevalence (3.2% in Japan) due to medical exposure, etc (200-2010). The prevalence is calculated on the linear non-threshold (LNT) hypothesis and is probably overestimated, possibly causing patient's fear. There has been a history of proposal by IAEA (1996) of the guidance levels of the ordinary roentgenography and in vivo nuclear medical test, and introduction of the concept of dose constraint by ICRP (Pub. 60). The incident dose rate to the patient under fluoroscopy defined by Japan Medical Service Law (2001) is, as an air-kerma rate, 15,600 residents for their contamination as well as remains, and measured the ambient dose rate of cities nearby. (T.T.)

  3. Exposure of Finnish population to ultraviolet radiation and radiation measurements

    International Nuclear Information System (INIS)

    Hoikkala, M.; Lappalainen, J.; Leszczynski, K.; Paile, W.

    1990-01-01

    This report is based on a survey of the literature on radiation risks involved in sunbathing and the use of solaria. The purpose of the report is to provide background information for the development of regulations on solaria and for informing the public about the risks posed by solaria and the sun. The report gives an overview of the properties and biological effects of ultraviolet radiation. The most important regulations and recommendations issued in various countries are presented. The connection between ultraviolet radiation and the risks of skin cancer is examined both on a general level and in reference to information obtained from the Finnish Cancer Registry. In Finland, the incidence of melanomas nearly tripled between 1960 and 1980. The most important cause is considered to be the population's increased exposure to the su's ultraviolet radiation. There are no reliable data on the connection between the use of solaria and the risks of skin cancer. It is estimated, however, that solaria account for less than 10 per cent of the skin cancer risk of the whole population. There are some difficult physical problems associated with the measurement of ultraviolet radiation emitted by both natural sources and solaria. A preliminary study of these problems has been undertaken by means of a survey of the available literature, supplemented by a review of measurements performed by the Finnish Centre For Radiation and Nuclear Safety. The estimated inaccuracy of the Optronic 742 spectroradiometer used by the Centre in the measurement of ultraviolet radiation emitted by the sun and solaria is about +-14%

  4. 10 years after Chernobyl, radiation exposure, health effects, safety aspects

    International Nuclear Information System (INIS)

    Mueck, K.

    1996-11-01

    This report sums up the various conferences and symposia which were prompted by the tenth anniversary of the accident in the nuclear power plant of Chernobyl. It was shown that by the accident up to now 31 casualties among the emergency and rescue personal at the site. Offsite no increased number of casualties caused by the accident was observed up to now. In the countries with the highest impact Ukraine, Belarus and Russia, however, an increased number of infant thyroid cancer is observed which is substantially higher than after the nuclear detonations over Japanese cities. Contrary to often published media reports, however, up to now no increases in leukemia or other malignant deceases were observed, neither in the population of the concerned regions nor among the liquidators. The high 137 Cs activity concentration in the environment close to the power plant result in exclusion zone even today. The deposition values in Kiev, however, amount to only 30 kBq/m 2 , in large areas of Ukraine they are below the average values in Austria of 22 kBq/m 2 . For these areas as well as those outside the former Soviet Union the average doses were less than 1 mSv in the first year, a value which is less than one third of natural annual radiation exposure. Since the reactor accident the activity concentration has significally decreased resulting in an exposure as consequence of the reactor accident of less than 0,8 % of the exposure in the first year. In Austria the exposure in 1996 amounts to less than 0,3 % of natural radiation exposure. (author)

  5. Assessing exposure to cosmic radiation aboard aircraft: the SIEVERT system

    International Nuclear Information System (INIS)

    Bottolier-Depois, J.F.; Clairand, I.; Blanchard, P.; Dessarps, P.; Lantos, P.

    2005-01-01

    Full text: The study of naturally-occurring radiation and its associated risk is one of the preoccupations of bodies responsible for radiation protection. Cosmic particle flux is significantly higher on board aircraft that at ground level. Furthermore, its intensity depends on solar activity and eruptions. Due to their professional activity, flight crews and frequent flyers may receive an annual dose of some milliSieverts. This is why the European directive adopted in 1996 requires the aircraft operators to assess the dose and to inform their flight crews about the risk. The effective dose is to be estimated using various experimental and calculation means. In France, the computerized system for flight assessment of exposure to cosmic radiation in air transport (SIEVERT) is delivered to airlines for assisting them in the application of the European directive. This dose assessment tool was developed by the French General Directorate of Civil Aviation (DGAC) and partners: the Institute for Radiation Protection and Nuclear Safety (IRSN), the Paris Observatory and the French Institute for Polar Research - PaulEmile Victor (IPEV). This professional service is available since more than two years on an Internet server accessible to companies with a public section. The system provides doses that consider the routes flown by aircraft. Various results obtained are presented: experimental validation, in particular for the ground level event model (large solar eruption), and statistics on routes and personal doses. (author)

  6. Assessing exposure to cosmic radiation aboard aircraft: the Sievert system

    International Nuclear Information System (INIS)

    Bottollier-Depois, J.F.; Biau, A.; Clairand, I.; Saint-Lo, D.; Valero, M.; Blanchard, P.; Dessarps, P.; Lantos, P.

    2003-01-01

    The study of naturally-occurring radiation and its associated risk is one of the preoccupations of bodies responsible for radiation protection. Cosmic particle flux is significantly higher on board aircraft that at ground level. Furthermore, its intensity depends on solar activity and eruptions. Due to their professional activity, flight crews and frequent flyers may receive an annual dose of some milli-sieverts. This is why the European directive adopted in 1996 requires the aircraft operators to assess the dose and to inform their flight crews about the risk. The effective dose is to be estimated using various experimental and calculation means. In France, the computerized system for flight assessment of exposure to cosmic radiation in air transport (SIEVERT) is delivered to airlines for assisting them in the application of the European directive. This dose assessment tool was developed by the French General Directorate of Civil Aviation (DGAC) and partners: the Institute for Radiation Protection and Nuclear Safety (IRSN), the Paris Observatory and the French Institute for Polar Research - Paul-Emile Victor (IPEV). This professional service is available on an Internet server accessible to companies with a public section. The system provides doses that consider the routes flown by aircraft Various results obtained are presented. (authors)

  7. Radiation exposure to skin following radioactive contamination

    International Nuclear Information System (INIS)

    Baumann, H.; Beyermann, M.; Kraus, W.

    1989-01-01

    In the case of skin contamination intensive decontamination measures should not be carried out until the potential radiation exposure to the basal cell layer of the epidermis was assessed. Dose equivalent rates from alpha-, beta- or photon-emitting contaminants were calculated with reference to the surface activity for different skin regions as a function of radiation energy on the condition that the skin was healthy and uninjured and the penetration of contaminants through the epidermis negligible. The results have been presented in the form of figures and tables. In the assessment of potential skin doses, both radioactive decay and practical experience as to the decrease in the level of surface contamination by natural desquamation of the stratum corneum were taken into account. 9 figs., 5 tabs., 46 refs. (author)

  8. Scatter radiation exposure during knee arthrography

    International Nuclear Information System (INIS)

    Light, M.C.; Molloi, S.Y.; Yandow, D.R.; Ranallo, F.N.

    1987-01-01

    Knee arthrography, as performed at the authors' institution, was simulated and scattered radiation exposure to a radiologist's gonads, thyroid, and eye lens was measured with a sensitive ionization chamber. Results show that radiologists who regularly conduct knee arthrography examinations can incur doses to the gonads that are less than 6% of the U.S. limits, and to the thyroid and eye that are approximately 10% of the U.S. limits. Since the scatter radiation from overhead imaging of stress views constituted most (greater than or equal to 60%) of the dose to the lens of the eye and the thyroid, spot imaging was evaluated as a substitute for overhead imaging in the assessment of the anterior cruciate ligament. This substitution resulted in no loss of clinical information and has now completely replaced overhead imaging of stress views at this institution

  9. Occupational radiation exposures at Canadian CANDU nuclear power stations

    International Nuclear Information System (INIS)

    LeSurf, J.E.; Taylor, G.F.

    1982-09-01

    In Canada, methods to reduce the radiation exposure to workers at nuclear power reactors have been studied and implemented since the early days of the CANDU reactor program. Close collaboration between the designers, the operators, and the manufacturers has reduced the total exposure at each station, the dose requirement to operate and maintain each successive station compared with earlier stations, and the average annual exposure per worker. Specific methods developed to achieve dose reduction include water chemistry; corrosion resistant materials; low cobalt materials; decontamination; hot filtration, improved equipment reliability, maintainability, and accessibility; improved shielding design and location; planning of work for low exposure; improved operating and maintenance procedures; removal of tritium from D 2 O systems and work environments; improved protective clothing; on-power refuelling; worker awareness and training; and many other small improvements. The 1981 occupational dose productivity factors for Pickering A and Bruce A nuclear generating stations were respectively 0.43 and 0.2 rem/MW(e).a

  10. Radiation exposure during cardiac catheterization procedures

    International Nuclear Information System (INIS)

    Kicken, P.J.H.; Huyskens, C.J.; Michels, H.R.

    1988-01-01

    For some time there has been an increased interest in more information about radiation exposure during cardiac catheterization because of: relatively high doses to workers and patient; rapid increase of numbers of examinations; introduction of new procedure-types (e.g. Percutaneous Transluminal Coronary Angiography, PTCA) and introduction of new techniques (e.g. Digital Subtraction Angiography, DSA). This paper reports about a study on the exposure to medical personnel and patient in two major hospitals in the Netherlands. The Total number of cardiac catheterization procedures in both hospitals amounts to circa 3000 per year (approximately 10% of all cardiac procedures c.q. 20% of all PTCA procedures in the Netherlands). This study is related to 1300 cardiac examinations

  11. New radiation limits and air crew exposure

    International Nuclear Information System (INIS)

    Antic, D.

    1999-01-01

    Commercial aircraft have optimum cruising speed of 800 - 900 km/h and the cruising altitude near 13 km.The flight paths are assigned according to airway corridors and safety requirements.The relatively high dose-equivalent rates at cruising altitudes near 13 km (about 0.5-2 mSv/h, and the shielding effect of the atmosphere corresponds to about 2 M of water) can cause exposures greater than 5 mSv/y, for a crew with full-time flight (500-600 h/y).The radiation exposure of the crew in commercial air traffic has been studied for the associations of the crews and airline management and published, and regulatory authorities are slowly accepting the fact that there indeed is a problem which needs investigations and protective regulation

  12. DOE 2008 Occupational Radiation Exposure October 2009

    International Nuclear Information System (INIS)

    2009-01-01

    A major priority of the U.S. Department of Energy (DOE) is to ensure the health, safety, and security of DOE employees, contractors, and subcontractors. The Office of Health, Safety and Security (HSS) provides the corporate-level leadership and strategic vision necessary to better coordinate and integrate health, safety, environment, security, enforcement, and independent oversight programs. One function that supports this mission is the DOE Corporate Operating Experience Program that provides collection, analysis, and dissemination of performance indicators, such as occupational radiation exposure information. This analysis supports corporate decision-making and synthesizes operational information to support continuous environment, safety, and health improvement across the DOE complex.

  13. A radiopharmacological study without human radiation exposure

    International Nuclear Information System (INIS)

    Loew, D.; Graul, E.H.; Kunkel, R.

    1984-01-01

    The development, study and control of new drugs today is hardly conceivable without nuclear medicine studies. Nuclear physicians on ethical commissions bear great responsibility in the planning and execution of such studies. In order to protect subjects and patients those nuclear techniques are therefore to be welcome which do not include exposure to radiation. Nuclear techniques used in in-vitro diagnostics (RIA) and the determination of naturally occurring nuclides incorporated in the human body belong to this category. With the aid of a clinico-pharmacological study of a new combination of diuretics it is shown that both methods supply valuable pharmacodynamic evidence. (orig.) [de

  14. Radiation exposure monitoring: a new IHE profile

    International Nuclear Information System (INIS)

    O'Donnell, Kevin

    2011-01-01

    A method is described for gathering and distributing radiation exposure data from X-ray-based imaging procedures such as CT, angiography, fluoroscopy, mammography and digital X-ray systems with integrated generators. The data are recorded in a standard format as a DICOM dose object and are managed in a similar fashion to the DICOM images produced by the procedure. The Integrating the Healthcare Enterprise (IHE) process for standardizing such methods is presented and applications of such data for activities, such as dose QA and national dose repositories, are also discussed. (orig.)

  15. Radiation-induced taste aversion: effects of radiation exposure level and the exposure-taste interval

    International Nuclear Information System (INIS)

    Spector, A.C.; Smith, J.C.; Hollander, G.R.

    1986-01-01

    Radiation-induced taste aversion has been suggested to possibly play a role in the dietary difficulties observed in some radiotherapy patients. In rats, these aversions can still be formed even when the radiation exposure precedes the taste experience by several hours. This study was conducted to examine whether increasing the radiation exposure level could extend the range of the exposure-taste interval that would still support the formation of a taste aversion. Separate groups of rats received either a 100 or 300 R gamma-ray exposure followed 1, 3, 6, or 24 h later by a 10-min saccharin (0.1% w/v) presentation. A control group received a sham exposure followed 1 h later by a 10-min saccharin presentation. Twenty-four hours following the saccharin presentation all rats received a series of twelve 23-h two-bottle preference tests between saccharin and water. The results indicated that the duration of the exposure-taste interval plays an increasingly more important role in determining the initial extent of the aversion as the dose decreases. The course of recovery from taste aversion seems more affected by dose than by the temporal parameters of the conditioning trial

  16. Intrauterine radiation exposures and mental retardation

    International Nuclear Information System (INIS)

    Miller, R.W.

    1988-01-01

    Small head size and mental retardation have been known as effects of intrauterine exposure to ionizing radiation since the 1920s. In the 1950s, studies of Japanese atomic-bomb survivors revealed that at 4-17 wk of gestation, the greater the dose, the smaller the brain (and head size), and that beginning at 0.5 Gy (50 rad) in Hiroshima, mental retardation increased in frequency with increasing dose. No other excess of birth defects was observed. Otake and Schull (1984) pointed out that the period of susceptibility to mental retardation coincided with that for proliferation and migration of neuronal elements from near the cerebral ventricles to the cortex. Mental retardation could be the result of interference with this process. Their analysis indicated that exposures at 8-15 wk to 0.01-0.02 Gy (1-2 rad) doubled the frequency of severe mental retardation. This estimate was based on small numbers of mentally retarded atomic-bomb survivors. Although nuclear accidents have occurred recently, new cases will hopefully be too rare to provide further information about the risk of mental retardation. It may be possible, however, to learn about lesser impairment. New psychometric tests may be helpful in detecting subtle deficits in intelligence or neurodevelopmental function. One such test is PEERAMID, which is being used in schools to identify learning disabilities due, for example, to deficits in attention, short- or long-term memory, or in sequencing information. This and other tests could be applied in evaluating survivors of intrauterine exposure to various doses of ionizing radiation. The results could change our understanding of the safety of low-dose exposures

  17. Ionizing radiation occupational exposure in the hemodynamics services

    International Nuclear Information System (INIS)

    Gronchi, Claudia Carla

    2004-01-01

    The purpose of this research is to study the ionizing radiation occupational exposure in the hemodynamic services of two large scale hospitals (Hospital A and Hospital B) of the Sao Paulo city. The research looked into annual doses that 279 professionals of the hemodynamic services were exposed to between 1991 and 2002. The data analyzed was collected from the database of the Instituto de Pesquisas Energeticas e Nucleares (IPEN) for Hospital A, and from the Radiological Protection Department of Hospital B. Besides this, measures of hands and crystalline lens equivalent doses were performed during hemodynamic procedures of the physicians, assistant physicians and nursing assistants with TL dosimeters (CaSO 4 :Dy + Teflon R) produced at IPEN. The safety procedures adopted by the hospitals were verified with the aid of a specific questionnaire for the hemodynamic services. Finally, a profile of the professionals that work in cardiac catheterism laboratories of the hemodynamic services was delineated, considering the variables of individual monitoring time, age and sex. This study allowed for observation of the behavior of the professionals' annual doses of these hemodynamic services in relation to the Comissao Nacional de Energia Nuclear and the Secretaria de Vigilancia Sanitaria limits. It showed that the annual doses of the same specialized occupations would vary from one hospital to another. It further showed the need of individual monitoring of the physicians' unprotected body parts (hands and crystalline lens) during the hemodynamic procedures. (author)

  18. Cosmic radiation exposure on Canadian-based commercial airline routes

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, B.J.; Tume, P.; Bennett, L.G.I.; Pierre, M.; Green, A.R

    1998-07-01

    As a result of the recent recommendations of the ICRP-60 and in anticipation of possible regulation on occupational exposure of commercial aircrew, a two-phase investigation was carried out over a one-year period to determine the total dose equivalent on representative Canadian-based flight routes. In the first phase of the study, dedicated scientific flights on a Northern round-trip route between Ottawa and Resolute Bay provided the opportunity to characterize the complex mixed-radiation field, and to intercompare various instrumentation using both a conventional suite of powered detectors and passive dosimetry. In the second phase, volunteer aircrew carried (passive) neutron bubble detectors during their routine flight duties. From these measurements, the total dose equivalent was derived for a given route with a knowledge of the neutron fraction as determined from the scientific flights and computer code (CART-LF) calculations. This study has yielded an extensive database of over 3100 measurements providing the total dose equivalent for 385 different routes. By folding in flight frequency information and the accumulated flight hours, the annual occupational exposures of 26 flight crew have been determined. This study has indicated that most Canadian-based domestic and international aircrew will exceed the proposed annual ICRP-60 public limit of 1 mSv y{sup -1} but will be well below the occupational limit of 20 mSv y{sup -1}. (author)

  19. Cosmic Radiation Exposure on Canadian-Based Commercial Airline Routes

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, B.J.; Tume, P.; Bennett, L.G.I.; Pierre, M.; Green, A.R.; Cousins, T.; Hoffarth, B.E.; Jones, T.A.; Brisson, J.R

    1999-07-01

    As a result of the recent recommendations of ICRP 60 and in anticipation of possible regulation on occupational exposure of commercial aircrew, a two-part investigation was carried out over a one-year period to determine the total dose equivalent on representative Canadian-based flight routes. As part of the study, a dedicated scientific measurement flight (using both a conventional suite of powered detectors and passive dosimetry) was used to characterise the complex mixed radiation field and to intercompare the various instrumentation. In the other part of the study, volunteer aircrew carried (passive) neutron bubble detectors during their routine flight duties. From these measurements, the total dose equivalent was derived for a given route with a knowledge of the neutron fraction as determined from the scientific flight and computer code (CARI-LF) calculations. This investigation has yielded an extensive database of over 3100 measurements providing the total dose equivalent for 385 different routes. By folding in flight frequency information and the accumulated flight hours, the annual occupational exposures of 26 flight crew have also been determined. This study has indicated that most Canadian-based domestic and international aircrew will exceed the proposed annual ICRP 60 public limit of 1 mSv.y{sup -1}, but will be below the occupational limit of 20 mSv.y{sup -1}. (author)

  20. Radiation hygienic annual report 2012. General environmental radioactivity and radiation surveillance in the vicinity of nuclear facilities in Bavaria

    International Nuclear Information System (INIS)

    Pfau, T.; Bernkopf, J.; Klement, R.; Bayerisches Landesamt fuer Umwelt, Augsburg

    2013-01-01

    The radiation hygienic annual report 2012 includes the following issues: (1) Introduction: Legal aspects of the surveillance, implementation of the radiation protection law, nuclear facility sites in Bavaria, interim storage facilities in Bavaria. (2) Natural radioactivity surveillance: measured data for the exposure paths air, water, food chain land, food chain water, residuals and waste. (3) Radiation surveillance in the vicinity of nuclear facilities in Bavaria: measures for air, precipitation, soils, plants, food chain land, milk and milk products, surface water, food chain water, drinking and ground water; measured data in the vicinity of NNP Isar 1 bd Isar 2 (KKI1/KKI2), NPP Gundremmingen (KGG), NPP Grafenrheinfeld (KKG), research neutron source Muenchen FRM II; emissions, meteorological conditions, spreading calculations.

  1. Global levels of radiation exposure: Latest international findings

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1993-01-01

    The radiation exposure of the world's population has recently been reviewed by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). UNSCEAR has reconfirmed that the normal operation of all peaceful nuclear installations contributes insignificantly to the global exposure to radiation. Even taking into account all the nuclear accidents to date (including Chernobyl), the additional exposure would be equivalent to only about 20 days of natural exposure. Military uses of nuclear energy have committed the world to most of the radiation exposure caused by human activities

  2. Breast cancer induced by protracted radiation exposures

    International Nuclear Information System (INIS)

    Elkind, M.M.

    1997-01-01

    The experience at Hiroshima/Nagasaki demonstrated that breast cancer can be induced by single doses of ionizing radiation following latencies of 10-40 years. Several epidemiological studies, usually involving ancillary low-LET radiation to the breast, have demonstrated that breast cancer can be induced by protracted exposures, with similar latencies, and with similar dependencies on dose. Radiobiologically these results suggest that the target cells involved were deficient in repair of low-LET damage even when the protraction was over months to years. Since three-quarters of breast tumors originate in the ducts where their proliferation is controlled by menstrual-cycle timed estrogen/progesterone secretions, these cells periodically were in cycle. Thus, the two main elements of a conceptual model for radon-induced lung cancer -- kinetics and deficient repair -- are satisfied. The model indicates that breast cancer could be the cumulative effect of protracted small exposures, the risk from any one of which ordinarily would be quite small. (author)

  3. 47 CFR 1.1310 - Radiofrequency radiation exposure limits.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Radiofrequency radiation exposure limits. 1... Procedures Implementing the National Environmental Policy Act of 1969 § 1.1310 Radiofrequency radiation... exposure to radiofrequency (RF) radiation as specified in § 1.1307(b), except in the case of portable...

  4. Predictors of radiation exposure to providers during percutaneous nephrolithotomy

    Directory of Open Access Journals (Sweden)

    David L Wenzler

    2017-01-01

    Conclusion: Increased stone burden, partial or staghorn calculi, surgery and fluoroscopy duration, and absence of preexisting access were associated with high provider radiation exposure. Radiation safety awareness is essential to minimize exposure and to protect the patient and all providers from potential radiation injury.

  5. An integrated framework for effective reduction of occupational radiation exposure in a nuclear power plant

    International Nuclear Information System (INIS)

    Joo, Hyun Moon; Hak, Soo Kim; Young, Ho Cho; Chang, Sun Kang

    1998-01-01

    For effective reduction of occupational radiation exposure in a nuclear power plant, it is necessary to identify repetitive high radiation jobs during maintenance and refueling operation and comprehensively assess them. An integrated framework for effective reduction of occupational radiation exposure is proposed in this study. The framework consists of three parts; data collection, statistical analysis, and ALARA findings. A PC-based database program, INSTORE, is used for data collection and reduction, and the Rank Sum Method is used in identifying high radiation jobs. As a case study, the data accumulated in Kori Units 3 and 4 have been analyzed. The results of this study show that the radiation job classifications of SG related work have much effect on annual ORE collective dose in Kori Units 3 and 4. As an example of ALARA findings, hence, the improvements for the radiation job classifications of SG related work are summarized

  6. Air crew exposure to cosmic radiation. New analysis, recommendations EURADOS

    International Nuclear Information System (INIS)

    Spurny, F.; Votockova, I.

    1995-01-01

    Cosmic radiation on the board of an aircraft consist of two components: directly ionizing radiation (electron, proton - low LET) and neutrons (high LET). Neither composition nor the energy spectrum of usual on-Earth calibration sources ( 60 Co, 252 Cf) do not correspond to the field on a board. Therefore high energy reference fields behind shielding high energy accelerator at CERN and Dubna have been created and intensively studied. Their typical characteristics following from the results of our measurements were obtained. In-flight measurements on the board of commercial aircraft have been realized since 1991 during about 20 flights, Flight routes extended from the 1.3 grad N up to about 65 grad N, flying altitudes varied from 8.2 km to 12.5 km. The exposure level due to galactic cosmic radiation is inversely proportional to the solar activity. Some radiation protection aspects were concluded: (a) The usual limits of annual air crew flight hours correspond at 11.3 km to about 4 mSv per year, with new ICRP conversion factors to about 5 mSv per year; (b) Monthly flight hours limit does not exclude that the exposure of a pregnant women can exceed 1 mSv during this period; (c) The air crew exposure should therefore be checked, controlled a nd administered as conscientiously as for any other group of occupationally exposed persons. A Working group 11 of EURADOS 'Exposure of air crew to cosmic radiation' has been formed (1992-1995) to prepare basic analysis and recommendations concerning the topics. The basic recommendations are the following: (a) air crew flying routinely at altitudes over 8 km are deemed to be category B workers, it is therefore important to estimate, record, control and, where necessary, to limit the doses; (b) the preferred procedure in order to estimate doses to air crew or frequent flyers is to determine route doses and fold these data with data on staff rostering; (c) where doses may exceed the limit for category B workers (6 mSv per year), on

  7. Occupational radiation exposure at PWRs: international comparison of some exposure indicators between 1975 and 1976

    International Nuclear Information System (INIS)

    Benedittini, M.; Lochard, J.

    1988-03-01

    This report presents occupational radiation exposures at PWRs for 1986. It updates the CEPN report no 103 which covered the 1975-1985 period. Data have been collected for Belgium, Federal Republic of Germany, Finland (this country was not included in the previous report), France, Japan, Sweden, Switzerland, United-States. Only reactors in commercial operation since July 1974 have been considered in the analysis. Figures related to 1986, do not change significantly previous results for average annual doses over all operating years in the various countries. Differences between average annual collective doses remain important: from 0.95 to 4.68 expressed in terms of man-Sv/reactor, and from 1.4 to 8.3 expressed in terms of man-Sv/GW-y. As far as average annual individual doses are concerned, values are ranging between 1.6 and 4.8 mSv. The data up to the end of 1986 show however a general increase of collective doses in the various countries apart for the United-States. The average collective dose per reactor for all PWRs out of the United-States raised from 2.07 man-Sv in 1985 to 2.37 man-Sv in 1986. This general increase is mainly due to special or unscheduled maintenance works which tend to raise with plant age. In the United-States the dose reduction is reflecting the 5 new reactors that came on stream in 1986 with relatively lower doses in the first operating year. Excluding these 5 new reactors from the analysis, figures show a stability in the average annual collective dose. Generally it can be concluded that collective exposures in the various countries are coming closer. This probably shows a tendency towards an uniformization of practices and mode of operations in the different countries [fr

  8. Radiation exposure in homes through radon and thoron daughter products

    International Nuclear Information System (INIS)

    Schmier, H.

    1984-01-01

    In a random selection of about 6000 homes in the Federal Republic of Germany, the radon concentration in room air has been measured using a simple dosemeter developed by Karlsruhe Nuclear Research Centre. The mean radon concentration has been determined to be approximately 40-50 Bqu/m 3 . If this experiment is taken as a representative survey for the FRG, the mean dose contributed by the natural radiation exposure through radon and its short-lived decay products to the effective annual dose to the lungs can be computed to be about 1 mSv (100 mrem), using the internationally accepted conversion factors. Apart from this survey, special radon measuring programmes have been carried out, including simultaneous recording of meteorological data, in order to obtain information on the parameters to be taken into account when describing the daily variations of radon concentrations. (orig./DG) [de

  9. GPU Nuclear Corporation's radiation exposure management system

    International Nuclear Information System (INIS)

    Slobodien, M.J.; Bovino, A.A.; Perry, O.R.; Hildebrand, J.E.

    1984-01-01

    GPU Nuclear Corporation has developed a central main frame (IBM 3081) based radiation exposure management system which provides real time and batch transactions for three separate reactor facilities. The structure and function of the data base are discussed. The system's main features include real time on-line radiation work permit generation and personnel exposure tracking; dose accountability as a function of system and component, job type, worker classification, and work location; and personnel dosemeter (TLD and self-reading pocket dosemeters) data processing. The system also carries the qualifications of all radiation workers including RWP training, respiratory protection training, results of respirator fit tests and medical exams. A warning system is used to prevent non-qualified persons from entering controlled areas. The main frame system is interfaced with a variety of mini and micro computer systems for dosemetry, statistical and graphics applications. These are discussed. Some unique dosemetry features which are discussed include assessment of dose for up to 140 parts of the body with dose evaluations at 7,300 and 1000 mg/cm 2 for each part, tracking of MPC hours on a 7 day rolling schedule; automatic pairing of TLD and self-reading pocket dosemeter values, creation and updating of NRC Forms 4 and 5, generation of NRC required 20.407 and Reg Guide 1.16 reports. As of July 1983, over 20 remote on-line stations were in use with plans to add 20-30 more by May 1984. The system provides response times for on-line activities of 2-7 seconds and 23 1/2 hours per day ''up time''. Examples of the various on-line and batch transactions are described

  10. External exposure due to natural radiation (KINKI)

    International Nuclear Information System (INIS)

    1978-01-01

    A field survey of exposure rates due to natural radiation has been conducted throughout the Kinki district of Japan during both September and October 1973. In each location, measurements of exposures at one to fifteen sites, one of where contained 5 stations at least, were made. A total of 143 sites were measured. Observations were made using a spherical ionization chamber and several scintillation surveymeters. The spherical plastic ionization chamber of which inner diameter and wall thickness are 200 mm and 3 mm (acrylate) respectively has adequate sensitivity for field survey. The chamber was used as a standard of apparatus, but it is difficult to use the apparatus in all locations only by the apparatus, so that a surveymeter with a NaI(Tl) 1''phi x 1'' scintillator was used for regular measurements. Two types of surveymeters, the one with a 2''phi x 2'' NaI(Tl) scintillator and the other with a 3''phi x 3'' NaI(Tl) scintillator, were used as auxiliary devices. Both the chamber and the surveymeter were used in 20 sites and their readings were compared for drawing a relationship between them. Practically the direct reading of the surveymeter were reduced into the corresponding value of the plastic chamber through the relationship of linear proportion. Systematic error at calibration ( 60 Co) and reading error (rodoh) of the plastic chamber were within +-6% (maximum over all error) and within +-3.5% (standard error for 6μ R/hr) respectively. Reading error of the surveymeter is about +-3% (standard error for 6μ R/hr). Measurements in open bare field were made at one meter above the ground and outdoor gamma-rays exposure rates (μ R/hr) were due to cosmic rays as well as terrestrial radiation, as it may be considered that the contribution of fallout due to artificial origin was very small. (J.P.N.)

  11. Troubles in vacuum system and radiation exposure

    International Nuclear Information System (INIS)

    Konno, Osamu

    1978-01-01

    It is about eleven years since the LINAC of 300 MeV in Tohoku University has first accelerated electrons. The maintenance and improvement of the accelerator used more than 10 years now give the related personnel an important problem of radiation exposure. 40 days were required for the maintenance and checking-up in 1977, and other 26 days were used for other construction works. The troubles in the vacuum system occurred 81 times in total. The vacuum system is divided into two subsystems, each being provided with a leak detector. Either of them enables to detect and locate the leak. Silver-alloy brazing of a duct with a cooling water tube has deteriorated in the strength because of repeated baking temperature and/or the copper tubes for cooling have been eroded due to the large local cell action by purified water. The similar phenomena have occurred in RF windows, outside of which is cooled with water. Carbonaceous matter has stuck to the element of the ion pump, but successfully been cleaned. Though the energy compression system was installed for the efficient use of electrons, the troubles due to overheating of the current monitor have increased because of its limited space, and the change of location was made. Considerable surface residual radiation dose was found at some parts of transport system, and a few personnel have been exposed to radiation over 1000 mrem/year as a result of the troubles in vacuum system. (Wakatsuki, Y.)

  12. The report of medical exposures in diagnostic radiology. Pt. 1. The questionnaire of medical exposure and standard radiation exposure

    International Nuclear Information System (INIS)

    Sasakawa, Yasuhiro; Matsumura, Yoshitaka; Iwasaki, Takanobu; Segawa, Hiroo; Yasuda, Sadatoshi; Kusuhara, Toshiaki

    1997-01-01

    We had made reports of patient radiation exposure for doctors to judge adaptation of medical radiation rightly. By these reports the doctors can be offered data of exposure dose and somatic effect. First, we sent out questionnaires so that we grasped the doctor's understanding about radiation exposure. Consequently we understood that the doctors had demanded data of exposure dose and somatic effect. Secondly, by the result of questionnaires we made the tables of exposure dose about radiological examination. As a result we have be able to presume exposure dose about high radiation sensitive organization as concrete figures. (author)

  13. Occupational exposure to natural radiation in Brazil

    International Nuclear Information System (INIS)

    Melo, D.R.

    2002-01-01

    The mining, milling and processing of uranium and thorium bearing minerals may result in radiation doses to workers. A preliminary survey pilot program, that included six mines in Brazil (two coal mines, one niobium mine, one nickel mine, one gold mine and one phosphate mine), was launched in order to determine the need to control the radioactive exposure of the mine-workers. Our survey consisted of the collection and analysis of urine samples, complemented by feces and air samples. The concentrations of uranium, thorium and polonium were measured in these samples and compared to background data from family members of the workers living in the same dwelling and from residents from the general population of Rio de Janeiro. The results from the coal mines indicated that the inhalation of radon progeny may be a source of occupational exposure. The workers from the nickel, gold and phosphate mines that were visited do not require a program to control internal radiological doses. The niobium mine results showed that in some areas of the industry exposure to thorium and uranium might occur. (author)

  14. Radiation risk from terrestrial exposure for population in cities of Serbia

    International Nuclear Information System (INIS)

    Jankovic-Mandic, Lj.; Dragovic, S.; Jankovic-Mandic, Lj.)

    2007-01-01

    In this work total gamma dose rate, annual effective dose and external hazard index are calculated based on specific activities of 226 Ra, 232 Th and 40 K determined by gamma-ray spectrometry. The average value of total gamma dose rate (61.8 n Gy/h) and annual effective dose (7.58·10 -5 Sv) from terrestrial exposure in 22 cities in Serbia are close to average world values. The average value of external hazard index of 0.35 showed that there is no significant radiation risk for population in cities of Serbia from terrestrial exposure. (author) [sr

  15. Criteria for radiological protection against exposure to natural radiation

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan

    2012-01-01

    Exposure of humans to natural sources of radiation has been a continuous and inevitable feature of life on earth. This exposure exceeds all due to artificial sources combined for most people. Many exposures to natural radiation sources are modified by human action. In particular, natural radionuclides are released into the environment in mineral processing and in activities such as the production of phosphate fertilizers and the use of fossil fuels. An increase of exposures to this natural radiation is caused. The relevance of exposure to natural radiation is confirmed by the fact that, for most people, the exposures to natural background radiation have been much more significant than exposures to artificial sources, with exceptions. Among these exceptions have been noted: medical exposures, accidents with release of radionuclides and some specific workplaces. In all cases, however, the natural background radiation has formed the basis on which all the others exposures are added and is a common level serving as compared to other exposures. Regulations and instructions have begun to establish in some countries to regulate natural radiation, countries like Spain, have already incorporated into its regulations on health protection against ionizing radiation the subject of natural radiation. (author) [es

  16. Radiation exposure from anthropogenic actinides in the northern Ukraine

    International Nuclear Information System (INIS)

    Hippler, Sven

    2006-01-01

    As a consequence of the Chernobyl accident, a large area of the northern Ukraine has been contaminated with many different radioactive substances to such an extent that the population hat to be evacuated. Officially, this exclusion still persists today. Meanwhile, people started returning to their dwellings without permission, and they continue living today within the contaminated area. This raises the question of how severe the radiation exposure to the illegal resettlers really is and of whether the restrictions are still justified. Currently, the radiation exposure is mainly being caused by 137 Cs and 90 Sr. But in the long-term, the influence of the long-living man-made actinoids will become important. In this study, their portion of the contamination of the evacuated area and the resulting contribution to the radiation exposure were examined in detail by considering the situation of the village Khristinovka as an example. For these purposes, many different environmental samples from Khristinovka (e.g. soil, food) have been analysed. The determination of the activity concentration of the actinoids was carried out by α-spectrometric measurements after radiochemical separations. Among the different man-made actinoids, only the nuclides 238 Pu, 239 Pu, 240 Pu and 241 Am are of immediate relevance. The most important actinoid is plutonium because of its slow migration in soil. Therefore, the long-living plutonium nuclides will contribute to the radiation exposure even when 90 Sr and 137 Cs will have decayed nearly completely. The observed deposition densities of (126 ± 7) Bq m -2 239, 240 Pu and (38.7 ± 3.4) Bq m -2 238 Pu are comparable to the official statements for this area. Thereby it is possible to distinguish between the contributions which originate from Chernobyl and the nuclear weapons fallout by means of the activity ratios between various radionuclides present. The additional annual dose to the general public of Khristinovka caused by man

  17. Occupational hazard: radiation exposure for the urologist: developing a reference standard

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, Seth A.; Rangarajan, Sriram S.; Chen, Tony; Palazzi, Kerrin L.; Langford, J. Scott; Sur, Roger L., E-mail: rlsur@ucsd.edu [Department of Surgery and Division of Urology, U C San Diego Health Science System, San Diego, CA (United States)

    2013-03-15

    Introduction: to date, there is a paucity of literature offering practicing urologists a reference for the amount of radiation exposure received while surgically managing urolithiasis. This study examines the cumulative radiation exposure of an urologist over 9 months. Materials and methods: We present a case series of fluoroscopic exposures of an experienced stone surgeon operating at an academic comprehensive stone center between April and December 2011. Radiation exposure measurements were determined by a thermoluminescent dosimeter worn on the outside of the surgeon's thyroid shield. Estimations of radiation exposure (mrem) per month were charted with fluoroscopy times, using scatter plots to estimate Spearman's rank correlation coefficients. Results: the total 9-month radiation exposure was 87 mrems for deep dose equivalent (DDE), 293 mrem for lens dose equivalent (LDE), and 282 mrem for shallow dose equivalent (SDE). Total fluoroscopy time was 252.44 minutes for 64 ureteroscopies (URSs), 29 percutaneous nephrolithtomies (PNLs), 20 cystoscopies with ureteral stent placements, 9 shock wave ithotripsies (SWLs), 9 retrograde pyelograms (RPGs), 2 endoureterotomies, and 1 ureteral balloon dilation. Spearman's rank correlation coefficients examining the association between fluoroscopy time and radiation exposure were not significant for DDE (p = 0.6, Spearman's rho = 0.2), LDE (p = 0.6, Spearman's rho = 0.2), or SDE (p = 0.6, Spearman's rho = 0.2). Conclusions: Over a 9-month period, total radiation exposures were well below annual accepted limits (DDE 5000 mrem, LDE 15,000 mrem and SDE 50,000 mrem). Although fluoroscopy time did not correlate with radiation exposure, future prospective studies can account for co-variates such as patient obesity and urologist distance from radiation source. (author)

  18. Intervention in emergency situations involving radiation exposure (1990)

    International Nuclear Information System (INIS)

    1992-01-01

    This document covers radiation protection aspects arising in emergency situations. It does not cover the measures necessary to reduce the health consequences of radiation exposure, i.e. the medical care of exposed individuals, nor does it cover psychological problems arising from the exposure of individuals or of a population. These problems may arise from anxiety about possible late effects of radiation exposure and from any actions implemented to reduce exposure. Even though radiation exposure levels may be low and insignificant, these problems must be taken into account in determining any action to be implemented to reduce radiation exposure. The primary concern of this document is with exposure in areas which are close to the source and in the period immediately after a source is out of control. It outlines the principles which can be used for planning and implementing countermeasures for protection of the public. 24 refs., 13 tabs

  19. Detriment calculations resulting from occupational radiation exposures in Egypt

    International Nuclear Information System (INIS)

    Abdel-Ghani, A.H.

    2000-01-01

    The application of the nominal probability coefficient to evaluate the detriment after the annual occupational exposures of workers from radiation sources and radioactive material have been calculated for workers in medical practices, industrial applications, atomic energy activities and those involved in exploration and mining of radioactive ores and phosphates. The aim of detriment calculations is to provide a foresight for the future occurrence of stochastic effects among the exposed workers. The calculated detriment can be classified into three classes. The first includes workers in diagnostic radiology and atomic energy activities who received the higher doses and consequently represent the higher detriment. The second class comprises workers in radiotherapy and nuclear medicine whose detriment is for times lesser than that of the first class. The third one concerns workers in industrial applications and in exploration and mining of radioactive ores and phosphates, their detriments ten times lesser than that of the second class. The occupational radiation doses are endorsed by the united nation scientific committee on efects of atomic radiation (UNSCEAR) for the period january 1995 to december 1998

  20. Ultraviolet radiation exposure from UV-transilluminators.

    Science.gov (United States)

    Akbar-Khanzadeh, Farhang; Jahangir-Blourchian, Mahdi

    2005-10-01

    UV-transilluminators use ultraviolet radiation (UVR) to visualize proteins, DNA, RNA, and their precursors in a gel electrophoresis procedure. This study was initiated to evaluate workers' exposure to UVR during their use of UV-transilluminators. The levels of irradiance of UV-A, UV-B, and UV-C were determined for 29 UV-transilluminators at arbitrary measuring locations of 6, 25, 62, and 125 cm from the center of the UV-transilluminator's filter surface in the direction of the operator's head. The operators (faculty, research staff, and graduate students) worked within 62 cm of the transilluminators, with most subjects commonly working at time ranged from 1 to 60 min. Actinic hazard (effective irradiance level of UVR) was also determined for three representative UV-transilluminators at arbitrary measuring locations of 2.5, 5, 10, 15, 20, 30, 40, and 50 cm from these sets' filter surface in the direction of the operator's head. The allowable exposure time for these instruments was less than 20 sec within 15 cm, less than 35 sec within 25 cm, and less than 2 min within 50 cm from the UV-transilluminators' filter surface. The results of this study suggest that the use of UV-transilluminators exposes operators to levels of UVR in excess of exposure guidelines. It is recommended that special safety training be provided for the affected employees and that exposure should be controlled by one or the combination of automation, substitution, isolation, posted warning signs, shielding, and/or personal protective equipment.

  1. Patient radiation exposure during different kyphoplasty techniques

    International Nuclear Information System (INIS)

    Panizza, D.; Barbieri, M.; Parisoli, F.; Moro, L.

    2014-01-01

    The scope of this study was to quantify patient radiation exposure during two different techniques of kyphoplasty (KP), which differ by a cement delivery method, in order to assess whether or not one of the two used methods can reduce the patient dose. Twenty patients were examined for this investigation. One X-ray fluoroscopy unit was used for localization, navigation and monitoring of cement delivery. The patient bio-metric data, the setting of the fluoroscope, the exposure time and the kerma-area product (KAP) were monitored in all the procedures for anteroposterior (AP) and lateral (LL) fluoroscopic projections in order to assess the range of radiation doses imparted to the patient. Theoretical entrance skin dose (ESD) and effective dose (E) were calculated from intraoperatively measured KAP. An average ET per procedure was 1.5±0.5 min for the manual injection technique (study A) and 1.4±0.4 min for the distance delivery technique (study B) in the AP plane, while 3.2±0.7 and 5.1±0.6 min in the lateral plane, respectively. ESD was estimated as an average of 0.10±0.06 Gy for study A and 0.13±0.13 Gy for study B in the AP or/and 0.59±0.46 and 1.05±0.36 Gy in the lateral view, respectively. The cumulative mean E was 1.9±1.0 mSv procedure -1 for study A and 3.6±0.9 mSv procedure -1 for study B. Patient radiation exposure and associated effective dose from KP may be considerable. The technique of distance cement delivery appears to be slower than the manual injection technique and it requires a more protracted fluoroscopic control in the lateral projection, so that this system entails a higher amount of dose to the patient. (authors)

  2. Patient radiation exposure during different kyphoplasty techniques.

    Science.gov (United States)

    Panizza, Denis; Barbieri, Massimo; Parisoli, Francesco; Moro, Luca

    2014-01-01

    The scope of this study was to quantify patient radiation exposure during two different techniques of kyphoplasty (KP), which differ by a cement delivery method, in order to assess whether or not one of the two used methods can reduce the patient dose. Twenty patients were examined for this investigation. One X-ray fluoroscopy unit was used for localization, navigation and monitoring of cement delivery. The patient biometric data, the setting of the fluoroscope, the exposure time and the kerma-area product (KAP) were monitored in all the procedures for anteroposterior (AP) and lateral (LL) fluoroscopic projections in order to assess the range of radiation doses imparted to the patient. Theoretical entrance skin dose (ESD) and effective dose (E) were calculated from intraoperatively measured KAP. An average ET per procedure was 1.5±0.5 min for the manual injection technique (study A) and 1.4±0.4 min for the distance delivery technique (study B) in the AP plane, while 3.2±0.7 and 5.1±0.6 min in the lateral plane, respectively. ESD was estimated as an average of 0.10±0.06 Gy for study A and 0.13±0.13 Gy for study B in the AP or/and 0.59±0.46 and 1.05±0.36 Gy in the lateral view, respectively. The cumulative mean E was 1.9±1.0 mSv procedure(-1) for study A and 3.6±0.9 mSv procedure(-1) for study B. Patient radiation exposure and associated effective dose from KP may be considerable. The technique of distance cement delivery appears to be slower than the manual injection technique and it requires a more protracted fluoroscopic control in the lateral projection, so that this system entails a higher amount of dose to the patient.

  3. Radiation exposure of cardiologists eye lenses during interventional procedures

    International Nuclear Information System (INIS)

    Treckova, V.; Nikodemova, D.; Salat, D.

    2014-01-01

    Recently published studies have indicated a lower threshold of eye lens doses for developing cataracts than previously used. These studies have shown that the latency period responsible for cataract development depends on the absorbed eye lens dose. The recommendations of the ICRP, the new BSS of IAEA and the 2013/59/EURATOM Directive revise the old occupational limit of equivalent dose (150 mSv) to the new lower value of 20 mSv per year. Probably this value will be exceeded mainly during specific interventional procedures. The main aim of the present study was to investigate the received eye lens doses by monitoring and assessment of radiation load of cardiologists in the particular Cardiologic Healthcare Facility in Slovakia. The measurements were realized by using TLD located on the both sides of the protective lead glasses of five cardiologists during CA/PTCA procedures, performed in the period of 1 month. Evaluation of the dosimeters was performed by HARSHAW TLD 3500. Collected parameters of each individual examination were expressed in the quantity personal dose equivalent Hp(0,07). The whole body doses during the CA/PTCA procedures were controlled by RaySafe i2 dosimetry system, allowing the collection of real time radiation exposure of medical staff. Values of personal dose equivalent Hp(0,07) on the left eye lens (where we observed higher dose values), were extrapolated to annual doses and compared with the new eye lens limit. The comparison of the results (calculating the average annual dose from the gathered annual workload of each cardiologist) indicates that the new proposed limit for eye lens doses (20 mSv/year) should be exceeded. Important information comes from the results of RaySafe measurements, which refer to the fact, that although the whole-body annual doses obtained by the followed cardiologists doses not exceed the annual limit of effective dose, the equivalent doses to the lens of the eye obtained from TLD, reached the overflow value

  4. Radiation exposure of cardiologists eye lenses during interventional procedures

    International Nuclear Information System (INIS)

    Treckova, V.; Nikodemova, D.; Salat, D.

    2014-01-01

    Recently published studies have indicated a lower threshold of eye lens doses for developing cataracts than previously used. These studies have shown that the latency period responsible for cataract development depends on the absorbed eye lens dose. The recommendations of the ICRP, the new BSS of IAEA and the 2013/59/EURATOM Directive revise the old occupational limit of equivalent dose (150 mSv) to the new lower value of 20 mSv per year. Probably this value will be exceeded mainly during specific interventional procedures. The main aim of the present study was to investigate the received eye lens doses by monitoring and assessment of radiation load of cardiologists in the particular Cardio logic Healthcare Facility in Slovakia. The measurements were realized by using TLD located on the both sides of the protective lead glasses of five cardiologists during CA/PTCA procedures, performed in the period of 1 month. Evaluation of the dosimeters was performed by HARSHAW TLD 3500. Collected parameters of each individual examination were expressed in the quantity personal dose equivalent Hp(0,07). The whole body doses during the CA/PTCA procedures were controlled by RaySafe i2 dosimetry system, allowing the collection of real time radiation exposure of medical staff. Values of personal dose equivalent Hp(0,07) on the left eye lens (where we observed higher dose values), were extrapolated to annual doses and compared with the new eye lens limit. The comparison of the results (calculating the average annual dose from the gathered annual workload of each cardiologist) indicates that the new proposed limit for eye lens doses (20 mSv/year) should be exceeded. Important information comes from the results of RaySafe measurements, which refer to the fact, that although the whole-body annual doses obtained by the followed cardiologists doses not exceed the annual limit of effective dose, the equivalent doses to the lens of the eye obtained from TLD, reached the overflow value

  5. Technologically modified exposures to natural radiation. Annex C

    International Nuclear Information System (INIS)

    1982-01-01

    This Annex deals with some examples of technologically modified exposures to natural radiation. Radiation exposures due to coal-fired power plants, geothermal energy production, exploitation of phosphate rock, aircraft travel, and consumer products are discussed. The present state of knowledge does not allow an accurate estimate of the collective effective dose equivalent from technologically modified exposures to natural radiation to be made. This annex has an extensive bibliography with at least 200 references.

  6. Predictors of radiation exposure to providers during percutaneous nephrolithotomy

    OpenAIRE

    David L Wenzler; Joel E Abbott; Jeannie J Su; William Shi; Richard Slater; Daniel Miller; Michelle J Siemens; Roger L Sur

    2017-01-01

    Background: Limited studies have reported on radiation risks of increased ionizing radiation exposure to medical personnel in the urologic community. Fluoroscopy is readily used in many urologic surgical procedures. The aim of this study was to determine radiation exposure to all operating room personnel during percutaneous nephrolithotomy (PNL), commonly performed for large renal or complex stones. Materials and Methods: We prospectively collected personnel exposure data for all PNL cases at...

  7. Physician and nurse knowledge about patient radiation exposure in ...

    African Journals Online (AJOL)

    2015-11-23

    Nov 23, 2015 ... Physician and nurse awareness of the radiation dose in the ED and the associated cancer risks to ... has activated mass media and Internet communications, and .... explained that radiation exposure has no relationship to.

  8. Radiation effects after low dose chronic long-term exposure

    International Nuclear Information System (INIS)

    Fliedner, T.M.; Friesecke, I.

    1997-01-01

    This document approaches the radiation effects after low dose chronic long-term exposure, presenting examples occurred, the pathophysiologic mechanisms for cell system tolerance in elevated radiation fields, and the diagnostic and therapeutic possibilities

  9. Radiation Exposure to Staff in Intensive Care Unit with Portable CT Scanner

    Directory of Open Access Journals (Sweden)

    Zhichao Xie

    2016-01-01

    Full Text Available Background. Bedside radiological procedures pose a risk of radiation exposure to ICU staff. The perception of risk may increase the degree of caution among the health care staff and raise new barriers preventing patients from obtaining prompt care. Objective. The aim of this study was to estimate the annual cumulative radiation dose to individual ICU staff. Methods. In this prospective study, forty subjects were required to wear thermoluminescent dosimeter badges during their working hours. The badges were analyzed to determine the exposure after 3 months. Results. A total of 802 radiological procedures were completed at bedside during the study period. The estimated annual dosage to doctors and nurses on average was 0.99 mSv and 0.88 mSv (p<0.001, respectively. Residents were subjected to the highest radiation exposure (1.04 mSv per year, p=0.002. The radiation dose was correlated with day shift working hours (r=0.426; p=0.006 and length of service (r=-0.403; p<0.01. Conclusions. With standard precautions, bedside radiological procedures—including portable CT scans—do not expose ICU staff to high dose of ionizing radiation. The level of radiation exposure is related to the daytime working hours and length of service.

  10. Studies on occupational exposure to external radiation at Fukuoka University Hospital

    International Nuclear Information System (INIS)

    Miyauchi, Teiichi; Oshima, Yoshio; Ono, Yo

    1982-01-01

    This is a report of the yearly changes of exposure received by workers in radiological occupations at Fukuoka University Hospital from August 1973 to December 1980. The total number of the workers during this period involving diagnostic radiology, radiotherapy and the other related fields included 153 physicians, 27 technicians, 29 nurses and 16 assistants. Out of 225 workers, only two angiographers and two involved in intracavitary radiation therapy received more than 500 mrem of the annual exposure dose. The highest dose was 610 mrem. The exposure doses have gradually decreased each year. The exposure of the workers has remarkably decreased to almost negligible since a remote afterloading system was installed for intracavitary radiation therapy. In no worker was any somatic effect of radiation detected in the periodical physical examinations, even in the number of lymphocytes in the peripheral blood. (author)

  11. Studies on occupational exposure to external radiation at Fukuoka University Hospital

    Energy Technology Data Exchange (ETDEWEB)

    Miyauchi, Teiichi; Oshima, Yoshio; Ono, Yo [Fukuoka Univ. (Japan)

    1982-09-01

    This is a report of the yearly changes of exposure received by workers in radiological occupations at Fukuoka University Hospital from August 1973 to December 1980. The total number of the workers during this period involving diagnostic radiology, radiotherapy and the other related fields included 153 physicians, 27 technicians, 29 nurses and 16 assistants. Out of 225 workers, only two angiographers and two involved in intracavitary radiation therapy received more than 500 mrem of the annual exposure dose. The highest dose was 610 mrem. The exposure doses have gradually decreased each year. The exposure of the workers has remarkably decreased to almost negligible since a remote afterloading system was installed for intracavitary radiation therapy. In no worker was any somatic effect of radiation detected in the periodical physical examinations, even in the number of lymphocytes in the peripheral blood.

  12. Proceedings of the 26th annual meeting of the National Council on Radiation Protection Measurements

    International Nuclear Information System (INIS)

    Richmond, C.R.

    1991-01-01

    This book reports on the 26th Annual Meeting of the National Council on Radiation Protection and Measurements which addressed the topic Health and Ecological Implications of Radioactively Contaminated Environments, a topic of great current interest and importance. The meeting was divided into five subtopics. The first dealt with the contaminated sites themselves, the second with human health implications, the third on remediation, the fourth (a panel) on lessons learned and issues of the future and finally a summation. The meeting also included progress reports on the work of three NCRP committees, Scientific Committee 1-2 on the Assessment of Risk for Radiation Protection Purposes, Scientific Committee 66 on Biological Effects and Exposure Criteria for Ultrasound and Scientific Committee 83 on Identification of Research Needs for Radiation Protection. Summaries of these reports prepared by their respective chairmen are included in this volume

  13. Annual report for FY 2011 on the activities of radiation safety in J-PARC

    International Nuclear Information System (INIS)

    2013-02-01

    This annual report describes the activities of radiation safety of Japan Proton Accelerator Research Complex (J-PARC) for FY 2011. The activities described are radiation protection in workplaces, environmental monitoring, individual monitoring, maintenance of monitoring instruments, and the technological developments of radiation protection. Occupational exposures have not exceeded the prescribed dose limit. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. J-PARC was suffered from the Great East Japan Earthquake and the accident at the Fukushima Daiichi Nuclear Power Plant. The report also covers the activities for the recovery of J-PARC and the environmental monitoring of radioactivity from the accident. (author)

  14. Annual report for FY 2011 on the activities of radiation safety in J-PARC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-02-15

    This annual report describes the activities of radiation safety of Japan Proton Accelerator Research Complex (J-PARC) for FY 2011. The activities described are radiation protection in workplaces, environmental monitoring, individual monitoring, maintenance of monitoring instruments, and the technological developments of radiation protection. Occupational exposures have not exceeded the prescribed dose limit. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. J-PARC was suffered from the Great East Japan Earthquake and the accident at the Fukushima Daiichi Nuclear Power Plant. The report also covers the activities for the recovery of J-PARC and the environmental monitoring of radioactivity from the accident. (author)

  15. French population's exposure to ionizing radiations

    International Nuclear Information System (INIS)

    2016-01-01

    This report deals with the exposure of the French population to ionizing radiation. The exposures taken into account are related to cosmic and telluric radiations, to radon, to ingestion of natural radionuclides, to medical imaging and to industrial and military sources. Additionally to the mean effective dose, considered as the macroscopic indicator of the population exposure, the variations of the effective dose for each source of exposure are also presented. Then, the variation of the total effective dose is presented. (authors)

  16. Radiation exposure in the wismut mines

    International Nuclear Information System (INIS)

    Seitz, G.; Ludwig, T.; Bauer, H.D.; Lehmann, F.

    1996-01-01

    Uranium mining grew fast in Saxonia after Second World War. No radiation protection was performed in the first 'wild' years (1946-1954). Winning with air hammer and drilling had been done without dust reduction and led to an enormous airborne dust concentration. These bad working conditions were unique world-wide. Measurements of dustborne activity concentrations had not been taken. To reconstruct the exposure conditions of miners in these years, four series of experiments under original working conditions were carried out. Stress must be laid on the fact that these measurements should result in the received doses according to uranium and it's long living daughters. Personal and stationary air samplers were used to collect the dust. Activity concentration measurements were done by gamma spectrometry. (author)

  17. Occupational radiation exposures in research laboratories

    International Nuclear Information System (INIS)

    Vaccari, S.; Papotti, E.; Pedrazzi, G.

    2006-01-01

    Radioactive sources are widely used in many research activities at University centers. In particular, the activities concerning use of sealed form ( 57 Co in Moessbauer application) and unsealed form ( 3 H, 14 C, 32 P in radioisotope laboratories) are analyzed. The radiological impact of these materials and potential effective doses to researchers and members of the public were evaluated to show compliance with regulatory limits. A review of the procedures performed by researchers and technicians in the research laboratories with the relative dose evaluations is presented in different situations, including normal operations and emergency situations, for example the fire. A study of the possible exposure to radiation by workers, restricted groups of people, and public in general, as well as environmental releases, is presented. (authors)

  18. Occupational radiation exposures in research laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Vaccari, S.; Papotti, E. [Parma Univ., Health Physics (Italy); Pedrazzi, G. [Parma Univ., Dept. of Public Health (Italy)

    2006-07-01

    Radioactive sources are widely used in many research activities at University centers. In particular, the activities concerning use of sealed form ({sup 57}Co in Moessbauer application) and unsealed form ({sup 3}H, {sup 14}C, {sup 32}P in radioisotope laboratories) are analyzed. The radiological impact of these materials and potential effective doses to researchers and members of the public were evaluated to show compliance with regulatory limits. A review of the procedures performed by researchers and technicians in the research laboratories with the relative dose evaluations is presented in different situations, including normal operations and emergency situations, for example the fire. A study of the possible exposure to radiation by workers, restricted groups of people, and public in general, as well as environmental releases, is presented. (authors)

  19. Controlling radiation exposure during interventional procedures in childhood cancer patients

    International Nuclear Information System (INIS)

    Racadio, John M.

    2009-01-01

    Many pediatric cancer patients undergo multiple diagnostic and therapeutic radiologic procedures over the course of their illnesses and are therefore at high risk for radiation exposure. There are a variety of measures that radiologists can employ to reduce this risk. These include limiting the use of radiation whenever possible, using specific strategies to reduce radiation exposure during interventional procedures, using quality assurance programs to ensure compliance, and maintaining continuing staff radiation safety educational programs. Some of the diagnostic and therapeutic interventional radiologic procedures that are performed in pediatric oncology patients are discussed here, along with specific tips for managing radiation exposure. (orig.)

  20. The latest occupational radiation exposure data from U.S. Nuclear Regulatory Commission Licensees

    International Nuclear Information System (INIS)

    Brock, T.

    2007-01-01

    This presentation summarizes the latest - 2005 occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission (NRC) Radiation Exposure Information and Reporting System. The bulk of the information contained in the paper was compiled from the 2005 annual reports submitted by NRC licensees subject to the reporting requirements of U.S. regulations (10 CFR 20.2206). Those licensees subject to reporting include commercial nuclear power plants, industrial radiographers, fuel processors, independent spent fuel storage installations, manufacturers and distributors of by-product material, facilities for low-level waste disposal, and geologic repositories for high-level waste. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in terms of collective dose and the distribution of doses by licensee category. (author)

  1. A model investigation of annual surface ultraviolet radiation in Iran

    International Nuclear Information System (INIS)

    Sabziparvar, A.-A.

    2003-01-01

    In recent years, there has been some concern regarding solar ultraviolet (UV) radiation received at the earth,s surface because of its biological hazards affecting living organisms. Although the geographical distribution of ground-based UV network is relatively good in some continents,but over Asia, the number of UV instruments are not sufficient for meteorological and biological purposes. Iran, as an Asian country, is also suffering from the lack of UV monitoring network with the exception of one ground-based UV spectrophotometer site (Brower III) at Esfahan. Using a complex radiative transfer model and various meteorological data (for 8 years) such as total column ozone, cloudiness, surface albedo, surface air pressure, relative humidity, visibility and daily total solar radiation (TSR), the geographical distribution of annual integrated biological surface UV irradiances such as UVB, erythema and cataracts are calculated. The comparison is made for cloud-free and all-sky conditions for eight selected cities distributed from the southern tip of the country (25 N-60 E) to the northern border (39 N-48 E). It is shown that the difference between the annual UV at south and north in all-sky condition is larger than the differences in cloud-free condition. The ratio of some biological UV irradiances at southern cities to the same component at northern cities shows a factor of two and more which is quite significant. The possible reasons which might cause such differences are discussed

  2. 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)

  3. Medical radiation exposure and genetic risks

    International Nuclear Information System (INIS)

    Baker, D.G.

    1980-01-01

    Everyone is exposed to background radiation throughout life (100 mrem/year to the gonads or 4 to 5 rem during the reproductive years). A lumbosacral series might deliver 2500 mrem to the male or 400 mrem to the female gonads. A radiologic procedure is a cost/benefit decision, and genetic risk is a part of the cost. Although cost is usually very low compared to benefit, if the procedure is unnecessary then the cost may be unacceptable. On the basis of current estimates, the doubling dose is assumed to be 40 rem (range 20 to 200) for an acute dose, and 100 rem for protracted exposure. Although there is no satisfactory way to predict the size of the risk for an individual exposed, any risk should be incentive to avoid unnecessary radiation to the gonads. Conception should be delayed for at least ten months for women and three or four months for men after irradiation of the gonads. The current incidence of genetically related diseases in the United States population is 60,000 per million live births. Based on the most conservative set of assumptions, an average gonadal dose of 1000 mrem to the whole population would increase the incidence of genetically related diseases by 0.2%

  4. Operation control device under radiation exposure

    International Nuclear Information System (INIS)

    Kimura, Kiichi; Murakami, Toichi.

    1994-01-01

    The device of the present invention performs smooth progress of operation by remote control for a plurality of operations in periodical inspections in controlled areas of a nuclear power plant, thereby reducing the operator's exposure dose. Namely, the device monitors the progressing state of the operation by displaying the progress of operation on a CRT of a centralized control device present in a low dose area remote from an operation field through an ITV camera disposed in the vicinity of the operation field. Further, operation sequence and operation instruction procedures previously inputted in the device are indicated to the operation field through an operation instruction outputting device (field CRT) in accordance with the progress of the operation steps. On the other hand, the operation progress can be aided by inputting information from the operation field such as start or completion of the operation steps. Further, the device of the present invention can monitor the change of operation circumstances and exposure dose of operators based on the information from a radiation dose measuring device disposed in the operation circumstance and to individual operators. (I.S.)

  5. External and internal exposure to natural radiations inside ancient Egyptian tombs in Saqqara

    Energy Technology Data Exchange (ETDEWEB)

    Abo-Elmagd, M [National Institute for Standard, Radiation Measurements Department, P.O. Box 136 Giza code no. 12211 (Egypt); Metwally, S M [Faculty of Science, Department of Physics, Ain Shams University, P.O. Box 11566, Cairo (Egypt); Elmongy, S A [Atomic Energy Authority, Nuclear Safety, Cairo (Egypt); Salama, E [Faculty of Science, Department of Physics, Ain Shams University, P.O. Box 11566, Cairo (Egypt); El-Fiki, S A [Faculty of Science, Department of Physics, Ain Shams University, P.O. Box 11566, Cairo (Egypt)

    2006-02-15

    Some ancient Egyptian tombs in Saqqara are closed for visit to undergo fixation processes. The workers inside these tombs exposed to natural radiations from natural Gamma emitters (external exposure) and inhale unknown radon doses (internal exposure) for long periods. The external exposure in all studied tombs is lower than the maximum recommended action level. The internal exposure in terms of annual effective dose in the south tomb is equal to 28.83mSv/year which highly exceed the recommended level (3-10mSv/year). In this tomb, the external exposure is equal to 21.43{mu}Sv/year. This reflects the hazards of radon over the other natural radiations in the closed area. Among the workers inside the studied tombs, the expected morality is equal to 0.0033%, 0.0199% and 0.0724% for the south entrance of Zoser pyramid, the Serapeum tomb, and the south tomb respectively. ctively.

  6. External and internal exposure to natural radiations inside ancient Egyptian tombs in Saqqara

    International Nuclear Information System (INIS)

    Abo-Elmagd, M.; Metwally, S.M.; Elmongy, S.A.; Salama, E.; El-Fiki, S.A.

    2006-01-01

    Some ancient Egyptian tombs in Saqqara are closed for visit to undergo fixation processes. The workers inside these tombs exposed to natural radiations from natural Gamma emitters (external exposure) and inhale unknown radon doses (internal exposure) for long periods. The external exposure in all studied tombs is lower than the maximum recommended action level. The internal exposure in terms of annual effective dose in the south tomb is equal to 28.83mSv/year which highly exceed the recommended level (3-10mSv/year). In this tomb, the external exposure is equal to 21.43μSv/year. This reflects the hazards of radon over the other natural radiations in the closed area. Among the workers inside the studied tombs, the expected morality is equal to 0.0033%, 0.0199% and 0.0724% for the south entrance of Zoser pyramid, the Serapeum tomb, and the south tomb respectively. ctively

  7. External radiation exposure after deposition of man-made radionuclides

    International Nuclear Information System (INIS)

    Jacob, P.

    1991-01-01

    The first step in assessing the external radiation exposure of the population is the determination of the gamma dose rate over meadows, which are used as reference points for various reasons. The second step is the description of external radiation exposures in urban and rural environments. The relation to the radiation exposure in a meadow is a function of the radionuclide distribution, i.e. the type of deposition. Finally, a simple method of calculating external radiation exposure is developed on the basis of recent findings. The method is compared with the method used in the UNSCEAR report for calculating radiation exposures after Chernobyl and with the method described in the AVV (General Administrative Regulation) of the Radiation Protection Ordinance. (orig./HP) [de

  8. Radiation protection and environmental monitoring in the area of the Asse mine. Annual report 1993

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1994-01-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  9. Radiation protection and environmental monitoring in the area of the Asse mine. Annual report 1994

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1995-01-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  10. Radiation protection and ambient radioactivity monitoring in the area of the Asse mine. Annual report 2005

    International Nuclear Information System (INIS)

    Meyer, H.; Wanka, T.

    2006-01-01

    Radiation protection measurements in the Asse mine and its environment were continued. Programmes for monitoring off-air and the environment more or less summarize monitoring measures and measurements so far. 358 measurements were made, i.e. as many as in the year before. All values recorded were in the range of natural background activity. In some cases, also long-term effects of early nuclear weapons tests and of the Chernobyl accident were identified. All staff members were monitored in accordance with the Radiation Protection Ordinance, and local doses, local dose rates and mine air activity were recorded in the framework of occupational radiation protection. None of the measurements exceeded the permissible personal doses and activities for occulpationally exposed persons. In the off-air of the salt mine, low concentrations of H-3, C-14, Pb-10 and Rn-222 including Rn-220 as well as short-lived radon decay products were measured. Concentrations in the environment of the shaft as calculated from the annual measurements were lower in some instances than the average natural concentrations of these nuclides. Radiation exposure from emissions in the most unfavourable site in the vicinity was far below the limiting values set by the Radiation Protection Ordinance. Storage of radioactive waste and research activities in the Asse salt mine resulted in no significantly higher population exposure in the surrounding villages. (orig.)

  11. Effects of high vs low-level radiation exposure

    International Nuclear Information System (INIS)

    Bond, V.P.

    1983-01-01

    In order to appreciate adequately the various possible effects of radiation, particularly from high-level vs low-level radiation exposure (HLRE, vs LLRE), it is necessary to understand the substantial differences between (a) exposure as used in exposure-incidence curves, which are always initially linear and without threshold, and (b) dose as used in dose-response curves, which always have a threshold, above which the function is curvilinear with increasing slope. The differences are discussed first in terms of generally familiar nonradiation situations involving dose vs exposure, and then specifically in terms of exposure to radiation, vs a dose of radiation. Examples are given of relevant biomedical findings illustrating that, while dose can be used with HLRE, it is inappropriate and misleading the LLRE where exposure is the conceptually correct measure of the amount of radiation involved

  12. An assessment of the potential radiation exposure from residual radioactivity in scrap metal for recycling

    International Nuclear Information System (INIS)

    Lee, Sang Yoon; Lee, Kun Jai

    1997-01-01

    With current waste monitoring technology it is reasonable to assume that much of the material designated as low level waste (LLW), generated within nuclear facilities, is in fact uncontaminated. This may include operational wastes, metal and rubble, office waste and discrete items from decommissioning or decontamination operations. Materials that contain only trivial quantities of radionuclides could realistically be exempted or released from regulatory control for recycle or reuse. A criterion for uncontrolled disposal of low-level radioactive contaminated waste is that the radiation exposure of the public and of each individual caused by this disposal is so low that radiation protection measures need not be taken. The International Atomic Energy Agency (IAEA) suggests an annual effective doses of 10 μ Sv as a limit for the individual radiation dose. In 1990, new recommendation on radiation protection standards was developed by International Commission on Radiological Protection (ICRP) to take into account new biological information related to the detriment associated with radiation exposure. Adoption of these recommendations necessitated a revision of the Commission's secondary limits contained in Publication 30, Parts 1 ∼ 4. This study summarized the potential radiation exposure from valuable scrap metal considered to uncontrolled recycle by new ICRP recommendations. Potential exposure pathways to people following were analyzed and relevant models developed. Finally, concentrations leading to an individual dose of 10 μ Sv/yr were calculated for 14 key radionuclides. These potential radiation exposures are compared with the results of an IAEA study. 12 refs., 6 tabs., figs

  13. Predictors of radiation exposure to providers during percutaneous nephrolithotomy

    Science.gov (United States)

    Wenzler, David L.; Abbott, Joel E.; Su, Jeannie J.; Shi, William; Slater, Richard; Miller, Daniel; Siemens, Michelle J.; Sur, Roger L.

    2017-01-01

    Background: Limited studies have reported on radiation risks of increased ionizing radiation exposure to medical personnel in the urologic community. Fluoroscopy is readily used in many urologic surgical procedures. The aim of this study was to determine radiation exposure to all operating room personnel during percutaneous nephrolithotomy (PNL), commonly performed for large renal or complex stones. Materials and Methods: We prospectively collected personnel exposure data for all PNL cases at two academic institutions. This was collected using the Instadose™ dosimeter and reported both continuously and categorically as high and low dose using a 10 mrem dose threshold, the approximate amount of radiation received from one single chest X-ray. Predictors of increased radiation exposure were determined using multivariate analysis. Results: A total of 91 PNL cases in 66 patients were reviewed. Median surgery duration and fluoroscopy time were 142 (38–368) min and 263 (19–1809) sec, respectively. Median attending urologist, urology resident, anesthesia, and nurse radiation exposure per case was 4 (0–111), 4 (0–21), 0 (0–5), and 0 (0–5) mrem, respectively. On univariate analysis, stone area, partial or staghorn calculi, surgery duration, and fluoroscopy time were associated with high attending urologist and resident radiation exposure. Preexisting access that was utilized was negatively associated with resident radiation exposure. However, on multivariate analysis, only fluoroscopy duration remained significant for attending urologist radiation exposure. Conclusion: Increased stone burden, partial or staghorn calculi, surgery and fluoroscopy duration, and absence of preexisting access were associated with high provider radiation exposure. Radiation safety awareness is essential to minimize exposure and to protect the patient and all providers from potential radiation injury. PMID:28216931

  14. Occupational radiation exposure in Germany in 2012. Report of the radiation protection register; Die berufliche Strahlenexposition in Deutschland 2012. Bericht des Strahlenschutzregisters

    Energy Technology Data Exchange (ETDEWEB)

    Frasch, Gerhard; Kammerer, Lothar; Karofsky, Ralf; Mordek, Else; Schlosser, Andrea; Spiesl, Josef

    2014-04-15

    In Germany, persons who are occupationally exposed to ionising radiation are monitored by several official dosimetry services that transmit the dose records about individual radiation monitoring to the Radiation Protection Register of the Federal Office for Radiation Protection (BfS). The purpose of the Radiation Protection Register is to supervise the keeping of the dose limits and to monitor the compliance with the radiation protection principle ''Optimisation'' by performing detailed annual statistical analyses of the monitored persons and their radiation exposure. The annual report of the Radiation Protection Register provides information about status and development of occupational radiation exposure in Germany. In 2012, about 350,000 workers were monitored with dosemeters for occupational radiation exposure. The number increased continuously by totally 10 % into the past five years. 19 % of the monitored persons received measurable personal doses. The average annual dose of these exposed workers was 0.52 mSv corresponding to 2.6 % of the annual dose limit of 20 mSv for radiation workers. In total, 2 persons exceeded the annual dose limit of 20 mSv, i.e. less than one case per 100,000 monitored persons. The collective dose of the monitored persons decreased to 27.9 Person-Sv, the lowest value since the last fifty years of occupational dose monitoring. 45 airlines calculated the route doses of 40,000 aircraft crew members by using certified computer programmes for dose calculation and sent the accumulated monthly doses via the Federal Office for Civil Aviation (''Luftfahrt-Bundesamt, LBA'') to the BfS. The collective dose of the aircraft crew personnel is 78.5 person- Sv, and thus significantly higher than the total collective dose of the workers monitored with personal dosemeters. The annual average dose of aircraft crew personnel was 1.96 mSv and decreased compared to 2011 (2.12 mSv) due to solar cycle. In 2012, about

  15. Exposing exposure: automated anatomy-specific CT radiation exposure extraction for quality assurance and radiation monitoring.

    Science.gov (United States)

    Sodickson, Aaron; Warden, Graham I; Farkas, Cameron E; Ikuta, Ichiro; Prevedello, Luciano M; Andriole, Katherine P; Khorasani, Ramin

    2012-08-01

    To develop and validate an informatics toolkit that extracts anatomy-specific computed tomography (CT) radiation exposure metrics (volume CT dose index and dose-length product) from existing digital image archives through optical character recognition of CT dose report screen captures (dose screens) combined with Digital Imaging and Communications in Medicine attributes. This institutional review board-approved HIPAA-compliant study was performed in a large urban health care delivery network. Data were drawn from a random sample of CT encounters that occurred between 2000 and 2010; images from these encounters were contained within the enterprise image archive, which encompassed images obtained at an adult academic tertiary referral hospital and its affiliated sites, including a cancer center, a community hospital, and outpatient imaging centers, as well as images imported from other facilities. Software was validated by using 150 randomly selected encounters for each major CT scanner manufacturer, with outcome measures of dose screen retrieval rate (proportion of correctly located dose screens) and anatomic assignment precision (proportion of extracted exposure data with correctly assigned anatomic region, such as head, chest, or abdomen and pelvis). The 95% binomial confidence intervals (CIs) were calculated for discrete proportions, and CIs were derived from the standard error of the mean for continuous variables. After validation, the informatics toolkit was used to populate an exposure repository from a cohort of 54 549 CT encounters; of which 29 948 had available dose screens. Validation yielded a dose screen retrieval rate of 99% (597 of 605 CT encounters; 95% CI: 98%, 100%) and an anatomic assignment precision of 94% (summed DLP fraction correct 563 in 600 CT encounters; 95% CI: 92%, 96%). Patient safety applications of the resulting data repository include benchmarking between institutions, CT protocol quality control and optimization, and cumulative

  16. Aquisition of age- and sex-dependent patient data for the calculation of annual radiation exposure in nuclear medicine: a German pilot study; Erfassung alters- und geschlechtsbezogener Daten nuklearmedizinischer Untersuchungen zur Berechnung der jaehrlichen Strahlenexposition in der BRD: Eine Pilotstudie

    Energy Technology Data Exchange (ETDEWEB)

    Schnell-Inderst, P.; Hacker, M.; Weiss, M.; Hahn, K. [Klinik und Poliklinik fuer Nuklearmedizin, Klinikum der Univ. Muenchen (Germany); Nosske, D.; Stamm-Meyer, A.; Brix, G. [Bundesamt fuer Strahlenschutz, Inst. fuer Strahlenhygiene, Neuherberg (Germany)

    2004-04-01

    Aim: a pilote study for estimation of radiation exposure due to diagnostic procedures in nuclear medicine using routine data of hospitals and practices in Germany. Methods: hospitals and practices willing to participate in the study supplied data of one year (1997), containing information on patients' identification number, age, sex, type of diagnostic procedure, radiopharmaceutical, administered activity, type of health insurance (private/public), inpatient/outpatient status, and so-called leistungsziffer, which describes the type of medical performances in Germany. The effective dose per examination was calculated according to ICRP 80. Mean, standard deviation, median, 5{sup th} and 95{sup th} percentiles of the effective dose were calculated, stratified by type of organ system and also by sex and age, including patients of {>=} 18 years. Results: 82 039 examinations from patients of 9 hospitals and practices were analyzed. The median (5-95{sup th} percentiles) of the effective dose per examination for all patients was 2.9 mSv (0.4-8.5 mSv); 1.2 examinations per patient and year were performed on average. The three most frequent examinations were bone scans (median 3.4 mSv; 2.9-5.1), thyroid (0.9 mSv; 0.4-2.2) and cardiovascular studies (7.3 mSv; 3.8-20.2). The median effective dose for 18 to 40 years old women was 1.0 mSv (0.4-5.8), for women between 41 and 65 years 2.2 mSv (0.4-7.3) and for women older than 65 years 2.4 mSv (0.5-7.6). The corresponding values for men were 2.6 mSv (0.3-7.6); 3.3 mSv (0.4-9.1), and 3.4 mSv (0.5-8.8). Conclusion: it was possible to gain an accurate determination of radiation exposure of diagnostic procedures in nuclear medicine by routine data. (orig.) [German] Ziel: Pilotstudie zur Ermittlung der Strahlenexposition in Deutschland bei Untersuchungen in der nuklearmedizinischen Diagnostik anhand von Routinedaten aus Kliniken und Praxen. Methoden: Kliniken und Praxen in Deutschland lieferten 1997 routinemaessig erhobene

  17. Surveillance of environmental radiation in Finland. Annual Report 2004

    International Nuclear Information System (INIS)

    Mustonen, R.

    2005-07-01

    The main goal of the surveillance of environmental radioactivity is to be always aware of levels of artificial radiation in the environment to which the public is exposed. Another goal is to detect all remarkable changes in levels of environmental radiation and radioactivity. Compliance with the basic safety standards laid down for protection of health of the general public against dangers arising from ionising radiation can be ensured with environmental radiation surveillance. Running of surveillance programmes on continuous basis also maintains and develops competence and readiness to respond to radiological emergencies. Surveillance of environmental radiation contains surveillance of artificial radiation and artificial radioactive elements in the environment. Natural radiation and natural radioactive elements are not associated with the surveillance programme, although the greater part of the public exposure to radiation is caused by natural radiation. Exposure to natural radiation is controlled separately if there is reason to suspect that natural radioactive elements cause unusual high exposure to the public (e.g. indoor radon and natural radionuclides in drinking water). Surveillance of environmental radioactivity in Finland is one of the official obligations of the Radiation and Nuclear Safety Authority (STUK). This obligation is based on the national and the European Communities' legislation. The Finnish radiation protection legislation appoints STUK as the national authority responsible for surveillance of environmental radioactivity, and the Euratom Treaty assumes continuous monitoring of levels of radioactivity in the air, water and soil in the Member States. In Finland, also the Finnish Meteorological Institute (FMI) and the Defence Forces are monitoring environmental radiation at their own stations. This report summarises the results of environmental radiation surveillance in 2004. The report also contains some comparisons with results from the

  18. Biological effects of low-dose ionizing radiation exposure

    International Nuclear Information System (INIS)

    Reinoehl-Kompa, Sabine; Baldauf, Daniela; Heller, Horst

    2009-01-01

    The report on the meeting of the Strahlenschutzkommission 2007 concerning biological effects of low-dose ionizing radiation exposure includes the following contributions: Adaptive response. The importance of DNA damage mechanisms for the biological efficiency of low-energy photons. Radiation effects in mammography: the relative biological radiation effects of low-energy photons. Radiation-induced cataracts. Carcinomas following prenatal radiation exposure. Intercellular apoptosis induction and low-dose irradiation: possible consequences for the oncogenesis control. Mechanistic models for the carcinogenesis with radiation-induced cell inactivation: application to all solid tumors in the Japanese atomic bomb survivors. Microarrays at low radiation doses. Mouse models for the analysis of biological effects of low-dose ionizing radiation. The bystander effect: observations, mechanisms and implications. Lung carcinoma risk of Majak workers - modeling of carcinogenesis and the bystander effect. Microbeam studies in radiation biology - an overview. Carcinogenesis models with radiation-induced genomic instability. Application to two epidemiological cohorts.

  19. Occupational radiation exposure history of Idaho Field Office Operations at the INEL

    International Nuclear Information System (INIS)

    Horan, J.R.; Braun, J.B.

    1993-10-01

    An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years

  20. Occupational radiation exposure history of Idaho Field Office Operations at the INEL

    Energy Technology Data Exchange (ETDEWEB)

    Horan, J.R.; Braun, J.B.

    1993-10-01

    An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

  1. Radiation exposure by man-modified materials containing natural radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Becker, D.E. [Technical Inspection Agency of Bavaria, Munich (Germany); Eder, E. [Government of Bavaria, Ministry for State Development and Environmental Affairs Development, Munich (Germany); Reichelt, A. [Technical Inspection Agency of Bavaria, Munich (Germany)

    1992-07-01

    More than one hundred materials, containing natural radioactive nuclides, are being investigated due to radiation exposure to people. This paper deals with thoriated gas mantles and shows that the radiation exposure by inhalation of radionuclides released while burning and exchange is not negligible. (author)

  2. 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.)

  3. Epistemological limitation for attributing health effects to natural radiation exposure

    International Nuclear Information System (INIS)

    González, Abel J.

    2010-01-01

    The attribution of health effects to prolonged radiation exposure situations, such as those experienced in nature, is a challenging problem. The paper describes the epistemological limitations for such attribution it demonstrate that in most natural exposure situations, the theory of radiation-related sciences is not capable to provide the scientific evidence that health effects actually occur (or do not occur) and, therefore, that radiation effects are attributable to natural exposure situations and imputable to nature. Radiation exposure at high levels is known to provoke health effects as tissue reactions. If individuals experience these effects they can be attributed to the specific exposure with a high degree of confidence under the following conditions: the dose incurred have been higher that the relevant dose-threshold for the specific effect; and an unequivocal pathological diagnosis is attainable ensuring that possible competing causes have been eliminated. Only under these conditions, the occurrence of the effect may be properly attested and attributed to the exposure. However, even high levels of natural radiation exposure are lower than relevant dose-thresholds for tissue reactions and, therefore, natural radiation exposure is generally unable to cause these type of effects. One exception to this general rule could be situations of high levels of natural radiation exposure that might be sufficient to induce opacities in the lens of the eyes (which could be considered a tissue-reaction type of effect)

  4. Impact of climate change on occupational exposure to solar radiation.

    Science.gov (United States)

    Grandi, Carlo; Borra, Massimo; Militello, Andrea; Polichetti, Alessandro

    2016-01-01

    Occupational exposure to solar radiation may induce both acute and long-term effects on skin and eyes. Personal exposure is very difficult to assess accurately, as it depends on environmental, organisational and individual factors. The ongoing climate change interacting with stratospheric ozone dynamics may affect occupational exposure to solar radiation. In addition, tropospheric levels of environmental pollutants interacting with solar radiation may be altered by climate dynamics, so introducing another variable affecting the overall exposure to solar radiation. Given the uncertainties regarding the direction of changes in exposure to solar radiation due to climate change, compliance of outdoor workers with protective measures and a proper health surveillance are crucial. At the same time, education and training, along with the promotion of healthier lifestyles, are of paramount importance.

  5. Background radiation levels and medical exposure levels in Australia

    International Nuclear Information System (INIS)

    Webb, D.V.; Solomon, S.B.; Thomson, J.E.M.

    1999-01-01

    The average effective background dose received by the Australian population has been reassessed to be ∼1.5 millisievert (mSv) per year. Over half of this exposure arises from exposure from terrestrial radiation and cosmic rays, the remainder from radionuclides within the body and from inhalation of radon progeny. This background is to be compared with medical radiation, primarily diagnostic, which could add half as much again to the population exposure. This paper reviews research programmes carried out by the Australian Radiation Laboratory to study radiation exposure from natural background and from medical use. While the latter exposure is accepted to have a social benefit, there is a need to ensure that doses are no more than necessary to provide effective diagnosis and optimal treatment. Copyright (1999) Australasian Radiation Protection Society Inc

  6. Optimizing radiation exposure for CT localizer radiographs

    Energy Technology Data Exchange (ETDEWEB)

    Bohrer, Evelyn; Maeder, Ulf; Fiebich, Martin [Univ. of Applied Sciences, Giessen (Germany). Inst. of Medical Physics and Radiation Protection-IMPS; Schaefer, Stefan; Krombach, Gabriele A. [Univ. Hospital Giessen (Germany). Dept. of Radiology; Noel, Peter B. [Technische Univ. Muenchen (Germany). Dept. of Diagnostic and Interventional Radiology

    2017-08-01

    The trend towards submillisievert CT scans leads to a higher dose fraction of localizer radiographs in CT examinations. The already existing technical capabilities make dose optimization of localizer radiographs worthwhile. Modern CT scanners apply automatic exposure control (AEC) based on attenuation data in such a localizer. Therefore not only this aspect but also the detectability of anatomical landmarks in the localizer for the desired CT scan range adjustment needs to be considered. The effective dose of a head, chest, and abdomen-pelvis localizer radiograph with standard factory settings and user-optimized settings was determined using Monte Carlo simulations. CT examinations of an anthropomorphic phantom were performed using multiple sets of acquisition parameters for the localizer radiograph and the AEC for the subsequent helical CT scan. Anatomical landmarks were defined to assess the image quality of the localizer. CTDI{sub vol} and effective mAs per slice of the helical CT scan were recorded to examine the impact of localizer settings on a helical CT scan. The dose of the localizer radiograph could be decreased by more than 90% while the image quality remained sufficient when selecting the lowest available settings (80 kVp, 20 mA, pa tube position). The tube position during localizer acquisition had a greater impact on the AEC than the reduction of tube voltage and tube current. Except for the use of a pa tube position, all changes of acquisition parameters for the localizer resulted in a decreased total radiation exposure. A dose reduction of CT localizer radiograph is necessary and possible. In the examined CT system there was no negative impact on the modulated helical CT scan when the lowest tube voltage and tube current were used for the localizer.

  7. DEGRO 2012. 18. annual congress of the German Radiation Oncology Society. Radiation oncology - medical physics - radiation biology. Abstracts

    International Nuclear Information System (INIS)

    Anon.

    2012-01-01

    The volume includes the abstracts of the contributions and posters of the 18th annual congress of the German Radiation Oncology Society DEGRO 2012. The lectures covered the following topics: Radiation physics, therapy planning; gastrointestinal tumors; radiation biology; stererotactic radiotherapy/breast carcinomas; quality management - life quality; head-neck-tumors/lymphomas; NSCL (non-small cell lung carcinomas); pelvic tumors; brain tumors/pediatric tumors. The poster sessions included the following topics: quality management, recurrent tumor therapy; brachytherapy; breast carcinomas and gynecological tumors; pelvis tumors; brain tumors; stereotactic radiotherapy; head-neck carcinomas; NSCL, proton therapy, supporting therapy; clinical radio-oncology, radiation biology, IGRT/IMRT.

  8. DOE occupational radiation exposure. Report 1992--1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The DOE Occupational Radiation Exposure Report, 1992-1994 reports occupational radiation exposures incurred by individuals at US Department of Energy (DOE) facilities from 1992 through 1994. This report includes occupational radiation exposure information for all DOE employees, contractors, subcontractors, and visitors. This information is analyzed and trended over time to provide a measure of the DOE`s performance in protecting its workers from radiation. Occupational radiation exposure at DOE has been decreasing over the past 5 years. In particular, doses in the higher dose ranges are decreasing, including the number of doses in excess of the DOE limits and doses in excess of the 2 rem Administrative Control Level (ACL). This is an indication of greater attention being given to protecting these individuals from radiation in the workplace.

  9. DOE occupational radiation exposure. Report 1992--1994

    International Nuclear Information System (INIS)

    1997-01-01

    The DOE Occupational Radiation Exposure Report, 1992-1994 reports occupational radiation exposures incurred by individuals at US Department of Energy (DOE) facilities from 1992 through 1994. This report includes occupational radiation exposure information for all DOE employees, contractors, subcontractors, and visitors. This information is analyzed and trended over time to provide a measure of the DOE's performance in protecting its workers from radiation. Occupational radiation exposure at DOE has been decreasing over the past 5 years. In particular, doses in the higher dose ranges are decreasing, including the number of doses in excess of the DOE limits and doses in excess of the 2 rem Administrative Control Level (ACL). This is an indication of greater attention being given to protecting these individuals from radiation in the workplace

  10. Radiation exposure of nurses in a coronary care unit

    International Nuclear Information System (INIS)

    Jankowski, C.B.

    1984-01-01

    In response to increasing awareness of radiation as a possible occupational hazard, nursing personnel staffing a hospital CCU were monitored over a 3-year period to determine occupational exposure. Portable x-ray machines, fluoroscopic units, and patients injected with radiopharmaceuticals were all potential radiation sources on such a unit. Whole-body TLD badges, exchanged monthly, indicated no cumulative exposures over 80 mR during the entire study period. The minimal exposures reported do not justify regular use of dosimeters. Adherence to standard protective measures precludes most exposure to machine-produced radiation. Close, prolonged contact with a patient after an RVG study that utilizes /sup 99m/Tc may account for some exposure. The data indicate that radiation is not a significant occupational hazard for CCU nurses at this hospital; similar minimal exposures would be expected of other nonoccupationally exposed nursing personnel in like environments

  11. Health risk assessment of exposure to ionizing radiation

    International Nuclear Information System (INIS)

    Ogata, Hiromitsu

    2011-01-01

    Risk assessment is an essential process for evaluating the human health effects of exposure to ionizing radiation and for determining acceptable levels of exposure. There are two major components of radiation risk assessment: a measure of exposure level and a measure of disease occurrence. For quantitative estimation of health risks, it is important to evaluate the association between exposure and disease occurrence using epidemiological or experimental data. In these approaches, statistical risk models are used particularly for estimating cancer risks related to exposure to low levels of radiation. This paper presents a summary of basic models and methods of risk assessment for studying exposure-risk relationships. Moreover, quantitative risk estimates are subject to several sources of uncertainty due to inherent limitations in risk assessment studies. This paper also discusses the limitations of radiation risk assessment. (author)

  12. Registration and monitoring of radiation exposure from radiological imaging

    International Nuclear Information System (INIS)

    Jungmann, F.; Pinto dos Santos, D.; Hempel, J.; Dueber, C.; Mildenberger, P.

    2013-01-01

    Strategies for reducing radiation exposure are an important part of optimizing medical imaging and therefore a relevant quality factor in radiology. Regarding the medical radiation exposure, computed tomography has a special relevance. The use of the integrating the healthcare enterprise (IHE) radiation exposure monitoring (REM) profile is the upcoming standard for organizing and collecting exposure data in radiology. Currently most installed base devices do not support this profile generating the required digital imaging and communication in medicine (DICOM) dose structured reporting (SR). For this reason different solutions had been developed to register dose exposure measurements without having the dose SR object. Registration and analysis of dose-related parameters is required for constantly optimizing examination protocols, especially computed tomography (CT) examinations based on the latest research results in order to minimize the individual radiation dose exposure from medical imaging according to the principle as low as reasonably achievable (ALARA). (orig.) [de

  13. Ocular exposure to ultraviolet and visible radiation from light sources

    International Nuclear Information System (INIS)

    Hietanen, M.

    1992-01-01

    Exposure of the eyes to UV radiation and blue light of artificial light sources and the sun was evaluated. A spectroradiometer was used to determine the spectral irradiance at 1 nm intervals from 250 to 800 nm. Various groups of workers are at risk of ocular over-exposure to optical radiation, outdoor workers maintenance personnel of bright light source as and wear eye-protectors with effective filtering of UV radiation and blue light. (author)

  14. Occupational radiation exposure in Germany in 2011. Report of the radiation protection register; Die berufliche Strahlenexposition in Deutschland 2011. Bericht des Strahlenschutzregisters

    Energy Technology Data Exchange (ETDEWEB)

    Frasch, Gerhard; Kammerer, Lothar; Karofsky, Ralf; Mordek, Else; Schlosser, Andrea; Spiesl, Josef

    2013-04-15

    In Germany, persons who are occupationally exposed to ionising radiation are monitored by several official dosimetry services that transmit the dose records about individual radiation monitoring to the Radiation Protection Register of the Federal Office for Radiation Protection (BfS). The purpose of the Radiation Protection Register is to supervise the keeping of the dose limits and to monitor the compliance with the radiation protection principle ''Optimisation'' by performing detailed annual statistical analyses of the monitored persons and their radiation exposure. The annual report of the Radiation Protection Register provides information about status and development of occupational radiation exposure in Germany. In 2011, about 350,000 workers were monitored with dosemeters for occupational radiation exposure. The number increased during the past five years continuously by 10 %. Only 19 % of the monitored persons received measurable personal doses. The average annual dose of these exposed workers was 0.58 mSv corresponding to 3 % of the annual dose limit of 20 mSv for radiation workers. In total, 7 persons exceeded the annual dose limit of 20 mSv, i.e. two cases per 100,000 monitored persons. The collective dose of the monitored persons decreased to 38.5 Person-Sv, the lowest value since the last fifty years of occupational dose monitoring. In 2010, 45 airlines calculated the route doses of 39,000 members of the aircraft crew personnel by using certified computer programmes for dose calculation and sent the accumulated monthly doses via the Federal Office for Civil Aviation (''Luftfahrt-Bundesamt, LBA'') to the BfS. The collective dose of the aircraft crew personnel is 83 person-Sv, and thus significantly higher than the total collective dose of the workers monitored with personal dosemeters (38.5 person-Sv). The annual average dose of aircraft crew personnel was 2.12 mSv and decreased compared to 2010 (2,30 mSv). In 2011

  15. Criteria for radiological protection against exposure to natural radiation

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan

    2012-01-01

    Ionizing radiation includes natural radiation which has been part cosmic radiation. Radon in homes, irradiation, gamma, among others, they have also been part of ionizing radiation. The activities that have lead to natural radiation materials are: mining and processing of uranium, radio application and thorium, phosphate industry, mining and smelting of metals, oil and gas extraction, coal mining and power generation, rare earth industry and titanium, zirconium and ceramics, building materials, waste water purification. Therefore, different criteria for radiation protection have had to create against exposure to natural radiation. Distinct rules and regulations to control were created in that sense [es

  16. Radiation exposure in gastroenterology: improving patient and staff protection.

    LENUS (Irish Health Repository)

    Ho, Immanuel K H

    2014-08-01

    Medical imaging involving the use of ionizing radiation has brought enormous benefits to society and patients. In the past several decades, exposure to medical radiation has increased markedly, driven primarily by the use of computed tomography. Ionizing radiation has been linked to carcinogenesis. Whether low-dose medical radiation exposure will result in the development of malignancy is uncertain. This paper reviews the current evidence for such risk, and aims to inform the gastroenterologist of dosages of radiation associated with commonly ordered procedures and diagnostic tests in clinical practice. The use of medical radiation must always be justified and must enable patients to be exposed at the lowest reasonable dose. Recommendations provided herein for minimizing radiation exposure are based on currently available evidence and Working Party expert consensus.

  17. Observations of nesting avifauna under gamma-radiation exposure

    International Nuclear Information System (INIS)

    Buech, R.R.

    1977-01-01

    An opportunity arose to observe the nesting success of birds (up to the time of fledging) when the Enterprise Forest Radiation Facility was established for a study of the effects of gamma radiation on the flora and fauna of northern forest communities. The results of these observations on the fate of the nest occupants in relation to radiation exposure are presented

  18. The treatment progress of radiation dermatitis from external exposure

    International Nuclear Information System (INIS)

    Pu Wangyang; Liu Yulong

    2009-01-01

    Radiation dermatitis is often seen and is often a complication of radiation therapy of tumors. It is characterized by poor healing, stubborn relapse, and carcinogenesis.. The treatment include drug, physical therapy and surgery. This article describes the treatment progress of radiation dermatitis from external exposure. (authors)

  19. On the radiation exposure in temporomandibular joint examinations

    International Nuclear Information System (INIS)

    Rother, U.; Hildebrandt, K.H.

    1979-01-01

    The radiation exposure caused by standardized examinations of the temporomandibular joint has been determined with the aid of 660 exposures of an Alderson phantom. Comparative examinations were performed with the classic contact technique according to Parma to elucidate the results obtained. The lowest surface exposure was observed in contact examinations of the temporomandibular joint. Application of a flat cone led to a 13-fold reduction in surface exposure compared to contact examinations according to Parma. Furthermore, radiation exposure strongly decreased from the irradiation field to the adjacent area if a cone (flat cone and ear cone) was used. (author)

  20. Radiation exposure in I-131 iodine therapy

    International Nuclear Information System (INIS)

    Friedrich, W.

    1985-01-01

    In the past five years, the applied I-131 radioactivity quantity has doubled with a constant number of beds. In 1984, it was 925 GBq (25 Ci). Despite this development, no changes in the professional radiation exposure were made out. The evaluation shows a dose smaller than 0.04 man Sv/TBq (0.16 man rem/Ci) of I-131 applied. This value is below the traceability limit of the film badges. The incorporation load of the personnel (27 members) was determined by monthly body counter measurements. Only in one measurement thyroid gland activity of 5 kBq (140 nCi) was detected. Most measurements did not show any incorporation; and the few positive results were below 0.74 kBq (20 nCi). The environmental load due to unfiltered release from patients' rooms was determined at the fence of the nuclear research plant. The maximum was 0.24 mSv/a thyroid gland dose of a small child in 1982 taking into account the measured 90% partion of organic compound iodine. The waste water is decayed following chemical treatment in storage tanks. (orig./HP) [de

  1. Radiation exposures for DOE [Department of Energy] and DOE contractor employees, 1988

    International Nuclear Information System (INIS)

    Merwin, S.E.; Traub, R.J.; Millet, W.H.

    1990-12-01

    This is the 21st in a series of annual radiation exposure reports published by the Department of Energy (DOE) or its predecessors. This report summarizes the radiation exposures received at DOE and DOE contractor facilities in 1988. Radiation exposures to both employees and visitors are included. Trends in radiation exposures are evaluated by comparing the doses received in 1988 to those received in previous years. The significance of the doses is addressed by comparing them to the DOE limits and by correlating the doses to health risks based on risk estimates from expert groups. This report represents a significant advancement from previous reports because it is the first for which detailed exposure data are available for each individual monitored at a DOE facility. This reports contains information on different types of radiation doses, such as penetrating, shallow, and neutron doses. It also contains analysis of exposures by age, sex, and occupation of the exposed individuals. This report is the first of any federal organization that presents such detailed exposure data. The purpose of this report is to disseminate information regarding radiation exposures received at US Department of Energy (DOE) and DOE contractor facilities. The primary purpose of this practice is to ensure that the DOE occupational dose limits are not exceeded and that as low as reasonably achievable (ALARA) goals are met. A secondary purpose, however, is to provide information that can be used by other organizations and individuals who wish to collect and analyze such information. This information may be useful for estimating the effect of changing dose limits on operations at DOE facilities, determining the progress of DOE with respect to the ALARA principle, or, in combination with epidemiological information, assisting researchers in determining whether or not low doses of ionizing radiation are harmful. 23 refs., 20 figs., 23 tabs

  2. Mapping the exposure of the Brazilian population to natural background radiation - cosmic radiation

    International Nuclear Information System (INIS)

    Rochedo, Elaine R.R.; Salles, Krause C.S.; Prado, Nadya M.C.

    2013-01-01

    The main objective of this work is to statically and graphically describe the exposure of the Brazilian population to natural background radiation. in this stage, doses due to cosmic rays is being assessed based on sea level dose rates, corrected by latitude and altitude, according to the model recommended by UNSCEAR. In this work, the doses were estimated for ali Brazilian municipalities with more than 100.000 inhabitants. The 253 municipalities selected for this study include about 52% of the Brazilian population. Average dose rate was estimated to be about 50 n Sv/h with a variation coefficient of 31%. The estimated doses have shown a strong influence of altitude on dose rates, with a correlation coefficient of 0,998 for ao exponential fit. This result confirms previous studies that show a large effect of the altitude 00 exposure from cosmic radiation. Considering the same occupation and shielding conditions used by UNSCEAR as global averages, average annual dose was estimated to be 0,37 (0,24 - 0,76) mSv/y, very close to UNSCEAR worldwide average of 0,38 (0,3 - 1,0) mSv/y. (author)

  3. Mapping the exposure of the Brazilian population to natural background radiation - cosmic radiation

    Energy Technology Data Exchange (ETDEWEB)

    Rochedo, Elaine R.R., E-mail: elaine@ird.gov.br [Instituto de Radioprotecao e Dosimetria (lRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Salles, Krause C.S.; Prado, Nadya M.C., E-mail: krausesalles@yahoo.com.br, E-mail: nadya@ime.ib.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The main objective of this work is to statically and graphically describe the exposure of the Brazilian population to natural background radiation. in this stage, doses due to cosmic rays is being assessed based on sea level dose rates, corrected by latitude and altitude, according to the model recommended by UNSCEAR. In this work, the doses were estimated for ali Brazilian municipalities with more than 100.000 inhabitants. The 253 municipalities selected for this study include about 52% of the Brazilian population. Average dose rate was estimated to be about 50 n Sv/h with a variation coefficient of 31%. The estimated doses have shown a strong influence of altitude on dose rates, with a correlation coefficient of 0,998 for ao exponential fit. This result confirms previous studies that show a large effect of the altitude 00 exposure from cosmic radiation. Considering the same occupation and shielding conditions used by UNSCEAR as global averages, average annual dose was estimated to be 0,37 (0,24 - 0,76) mSv/y, very close to UNSCEAR worldwide average of 0,38 (0,3 - 1,0) mSv/y. (author)

  4. Occupational exposure of medical radiation workers in Lithuania, 1950-2003

    International Nuclear Information System (INIS)

    Samerdokiene, V.; Atkocius, V.; Kurtinaitis, J.; Valuckas, K.P.

    2008-01-01

    This study presents the summary of historical exposures, measurement practice and evolution of the recording of the individual doses of medical radiation workers during 1950-2003 in Lithuania. The aim of this study is to present occupational exposure of medical radiation workers in Lithuania since the earliest appearance period. Data from publications have been used for the earliest two periods prior to 1969; data from the archives of the largest hospitals, for the period 1970-1990 and data from Lithuanian Subdivision of Individual Dosimetry of Radiation Protection Center, for the period 1991-2003. The analysis of the data obtained from personal records allows to conclude that the average annual effective dose of Lithuanian medical radiation workers was greatly reduced in radiology, radiotherapy and nuclear medicine in all occupational categories from 1950 to 2003. During the last period 1991-2003 extremity doses clearly decreased and after 1994 were no longer present in Lithuania. (authors)

  5. Investigation of radiation exposure dosage in dental and panoramic radiography

    International Nuclear Information System (INIS)

    Ishii, Kenichi

    2005-01-01

    Dental radiography and a 10-sheet procedure were conducted at 10 sites in the maxillomandibular anterior teeth and at both sides of the premolar and molar teeth sections with and without a protective apron (total 22 patterns). Experiments, which included a total of five patterns, involving standard ortho-radiography were performed with and without a protective apron, positioning of an apron exclusively on the anterior or the posterior portion of the body and utility of an apron that covered the entire body. Results are as follows: In dental radiography, internal organs included in a bundle demonstrated high radiation exposure, whereas organs excluded from the bundle exhibited low radiation exposure. In organs situated below the thyroid gland, utilization of aprons resulted in lower radiation exposure. In ortho-radiography, radiation exposure was greatest in the parotid gland, followed by the mandibular, sublingual and thyroid glands, respectively. The protective apron resulted in lower radiation exposure at sites situated below the mammary glands; moreover, a protector covering the entire body led to lower radiation exposure in comparison to an apron worn exclusively on the anterior or the posterior aspect of the body. No significant difference was observed in terms of exposure between protective aprons worn on the anterior or the posterior aspect of the body. Furthermore, a protective collar resulted in nearly zero radiation exposure in the thyroid gland. However, a protective collar largely interferes with interpretation of the radiograph; thus, in order to produce interpretable radiographs, protection of the thyroid gland is not possible. In conclusion, radiation exposure dosage can be reduced via utilization of a protective apron positioned below the thyroid gland during dental radiography and below the mammary glands during ortho-radiography. We confirmed evidence indicating that application of a protective apron can reduce patient radiation exposure dosage

  6. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1991

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-07-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1991. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1991 annual reports submitted by about 436 licensees indicated that approximately 206,732 individuals were monitored, 182,334 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.15 rem (cSv) and an average measurable dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 96,231 individuals completed their employment with one or more of the 436 covered licensees during 1991. Some 68,115 of these individuals terminated from power reactor facilities, and about 7,763 of them were considered to be transient workers who received an average dose of 0.52 rem (cSv)

  7. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1989

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1992-04-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC 1 licensees during the years 1969 through 1989. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC 1 licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1989 annual reports submitted by about 448 licensees indicated that approximately 216,294 individuals were monitored 111,000 of whom were monitored by nuclear power facilities. They incurred an average individual does of 0.18 rem (cSv) and an average measurable dose of 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,535 individuals completed their employment with one or more of the 448 covered licensees during 1989. Some 76,561 of these individuals terminated from power reactor facilities, and about 10, 344 of them were considered to be transient workers who received an average dose of 0.64 rem (cSv)

  8. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1988

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1991-07-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1988. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1988 annual reports submitted by about 429 licensees indicated that approximately 220,048 individuals were monitored, 113,00 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.20 rem (cSv) and an average measurable dose of 0.41 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,072 individuals completed their employment with one or more of the 429 covered licensees during 1988. Some 80,211 of these individuals terminated from power reactor facilities, and about 8,760 of them were considered to be transient workers who received an average dose of 0.27 rem (cSv). 17 refs., 11 figs., 29 tabs

  9. Exposure of Finnish population to solar UV radiation and consequent carcinogenic effects

    Energy Technology Data Exchange (ETDEWEB)

    Huurto, L.; Jansen, C. [Turku Univ. Hospital, Turku (Finland); Jokela, K. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland)

    1996-12-31

    Depletion of stratospheric ozone increases irradiance of terrestrial ultraviolet (UV) radiation at short wavelengths, which may be harmful to the human health. To understand quantitatively the risks caused by increasing UV radiation to the Finnish population, the actual UV exposure of the population has to be assessed. It was shown that the snow reflection increases the UV exposure to the face and eyes particularly in the northern Finland. In 1993 exceptionally low ozone levels persisted up to the end of May, which resulted in a theoretical increase in the annual UV dose ranging from 8 % to 13 % in Finland. The maximal increase in the measured erythemally effective dose rate was 34 % on 23 April, when compared with the theoretical normal value. During this study exposure models have been developed. The models have been combined them with Green`s radiation transfer model to estimate annual facial UV doses received by different groups of Finnish population. Also, an updated estimate for increase in skin cancer incidence due to the ozone depletion is presented. It is estimated that the maximal increase in UV doses caused by the depletion of the stratospheric ozone will be 12 % in the first years of the next century in Finland. This may result in increase in skin carcinomas by 20-30 % if the people do not improve their protection against solar UV radiation. At the moment the annual facial UV dose of the Finnish indoor worker varies from 3 % to 6 % of the annual ambient dose. In the worst case an outdoor worker may receive even 16% of the annual ambient dose. However, the doses received by indoor workers during vacation to an untanned skin may be more harmful due to the increased risk of malignant melanoma.

  10. Exposure of Finnish population to solar UV radiation and consequent carcinogenic effects

    Energy Technology Data Exchange (ETDEWEB)

    Huurto, L; Jansen, C [Turku Univ. Hospital, Turku (Finland); Jokela, K [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland)

    1997-12-31

    Depletion of stratospheric ozone increases irradiance of terrestrial ultraviolet (UV) radiation at short wavelengths, which may be harmful to the human health. To understand quantitatively the risks caused by increasing UV radiation to the Finnish population, the actual UV exposure of the population has to be assessed. It was shown that the snow reflection increases the UV exposure to the face and eyes particularly in the northern Finland. In 1993 exceptionally low ozone levels persisted up to the end of May, which resulted in a theoretical increase in the annual UV dose ranging from 8 % to 13 % in Finland. The maximal increase in the measured erythemally effective dose rate was 34 % on 23 April, when compared with the theoretical normal value. During this study exposure models have been developed. The models have been combined them with Green`s radiation transfer model to estimate annual facial UV doses received by different groups of Finnish population. Also, an updated estimate for increase in skin cancer incidence due to the ozone depletion is presented. It is estimated that the maximal increase in UV doses caused by the depletion of the stratospheric ozone will be 12 % in the first years of the next century in Finland. This may result in increase in skin carcinomas by 20-30 % if the people do not improve their protection against solar UV radiation. At the moment the annual facial UV dose of the Finnish indoor worker varies from 3 % to 6 % of the annual ambient dose. In the worst case an outdoor worker may receive even 16% of the annual ambient dose. However, the doses received by indoor workers during vacation to an untanned skin may be more harmful due to the increased risk of malignant melanoma.

  11. Prenatal radiation exposure. Conclusions in the light of radiology

    International Nuclear Information System (INIS)

    Leppin, W.

    1987-01-01

    Within 6 years of the appearance of the guideline for action to be taken by doctors in the event of prenatal exposure to radiation, intended as a proposal for discussion, the following has turned out: in no case has termination of pregnancy become necessary following prenatal radiation exposure, prenatal radiation exposure was always low (about 20 mSv), there is no risk below respective threshold doses, teratogenesis is a non-stochastic process, which is why risk assessment was modified, the sensitivity of the human fetus to radiation is highest during the period of neuroblast development (9th to 16th week p.c.), and knowledge about an existing pregnancy can be taken for granted by that time, so radiation exposure is calculable and can be restricted to negligible quantities. (TRV) [de

  12. Historical overview of radiation exposure guidance on radioactive consumer products

    International Nuclear Information System (INIS)

    Tapert, A.C.

    1978-01-01

    This paper is an historical overview of radiation exposure recommendations suggested by several commissions, committees, and agencies. Guidelines issued by the International Commission of Radiological Protection, International Atomic Energy Agency, Federal Radiation Council, Nuclear Energy Agency (formerly the European Nuclear Energy Agency), National Council on Radiation Protection and Measurements, Food and Drug Administration, Conference of Radiation Control Program Directors, and the US Nuclear Regulatory Commission are discussed

  13. DOE 2010 Occupational Radiation Exposure November 2011

    Energy Technology Data Exchange (ETDEWEB)

    U.S. Department of Energy, Office of Health, Safety and Security, Office of Analysis

    2011-11-11

    This report discusses radiation protection and dose reporting requirements, presents the 2010 occupational radiation dose data trended over the past 5 years, and includes instructions to submit successful ALARA projects.

  14. Radiation exposure due to nuclear power

    International Nuclear Information System (INIS)

    This information brochure contains 12 earlier papers of leading experts on the radiation hazard the population incurs during normal operation of nuclear facilities and the radiation-biological fundamentals of the effects of ionizing radio humans. (HP) [de

  15. High beta radiation exposure of medical staff measures for optimisation of radiation protection

    International Nuclear Information System (INIS)

    Barth, I.; Rimpler, A.

    2006-01-01

    Full text of publication follows: New therapies applying beta radionuclides have been introduced in medicine in recent years, especially in nuclear medicine, e. g. radio-synoviorthesis, radioimmunotherapy and palliative pain therapy. The preparation of radiopharmaceuticals, their dispensary as well as injection require the handling of vials and syringes with high activities of beta emitters at small distances to the skin. Thus the medical staff may be exposed to a high level of beta radiation. Hence the local skin dose, Hp(0,07), was measured at these workplaces with thin-layer thermoluminescent dosemeters TLD (LiF:Mg,P,Cu) fixed to the tip of the fingers at both hands of the personnel. In addition, official beta/photon ring dosemeters were worn at the first knuckle of the index finger. Very high local skin doses were measured at the tip of index finger and thumb. The findings indicate that the exposure of the staff can exceed the annual dose limit for skin of 500 mSv when working at a low protection standard. By the use of appropriate shieldings and tools (e.g. tweezers or forceps) the exposure was reduced of more than one order of magnitude. The German dosimetry services provide official beta/photon ring dosemeters for routine monitoring of the extremity exposure of occupationally exposed persons. But even monitoring with these official dosemeters does not provide suitable results to control compliance with the dose limit in the majority of cases because they can mostly not be worn at the spot of highest beta exposure (finger tip). Therefore, a study was performed to identify the difference of readings of official ring dosemeters and the maximum local skin dose at the finger tips. At workplaces of radio-synoviorthesis a correction factor of 3 was determined provided that the staff worked at high radiation protection standard and the ring dosemeters were worn at the first knuckle of the index finger. The correction factor increases significantly when the radiation

  16. Exposure to the atmospheric ionizing radiation environment: a study on Italian civilian aviation flight personnel

    International Nuclear Information System (INIS)

    De Angelis, G.; Caldora, M.; Santaquilani, M.; Scipione, R.; Verdecchia, A.

    2003-01-01

    A study of the effects of high-LET, low-dose and low-dose-rate ionizing radiation and associated risk analysis is underway. This study involves analyzing the atmospheric ionizing radiation exposure (including high-energy neutrons) and associated effects for members of civilian aviation flight personnel, in an attempt to better understand low-dose long-term radiation effects on human subjects. The study population includes all Italian civilian airline flight personnel, both cockpit and cabin crew members, whose work history records and actual flights (route, aircraft type, and date for each individual flight for each person where possible) are available. The dose calculations are performed along specific flight legs, taking into account the actual flight profiles for all different routes and the variations with time of solar and geomagnetic parameters. Dose values for each flight are applied to the flight history of study participants in order to estimate the individual annual and lifetime occupational radiation dose. An update of the study of the physical atmospheric ionizing radiation exposure is given here, in terms of environmental modeling, flight routes, radiation dose evaluation along different flight paths, and exposure matrix construction. The exposure analysis is still in progress, and the first results are expected soon

  17. Exposure to ultraviolet radiation: recommendations for cosmetic use

    International Nuclear Information System (INIS)

    Dias, C.; Carvalho, F.R.S.

    2000-01-01

    The beginning of the so-called tanning industry made possible the acquisition of a tanned skin independently of the available solar radiation. The tan is produced by ultraviolet radiation and, as well as in solar exposure, there are additional risks on the use of the so-called sun-beds. The damaging effects of ultraviolet exposure are well documented and reasonably quantified. The objective of this paper is to inform the potential effects of ultraviolet radiation exposure in sun-beds and to provide recommendations in order to reduce the associated risks. These recommendations are adapted for cosmetics use only (author)

  18. The Relationship between Ultraviolet Radiation Exposure and Vitamin D Status

    Directory of Open Access Journals (Sweden)

    Ola Engelsen

    2010-05-01

    Full Text Available This paper reviews the main factors influencing the synthesis of vitamin D, with particular focus on ultraviolet radiation exposure. On the global level, the main source of vitamin D is the sun. The effect of solar radiation on vitamin D synthesis depends to some extent on the initial vitamin D levels. At moderate to high latitudes, diet becomes an increasingly important source of vitamin D due to decreased solar intensity and cold temperatures, which discourage skin exposure. During the mid-winter season, these factors result in decreased solar radiation exposure, hindering extensively the synthesis of vitamin D in these populations.

  19. Non-Ionizing Radiation - sources, exposure and health effects

    International Nuclear Information System (INIS)

    Hietanen, M.

    2003-01-01

    Non-ionizing radiation contains the electromagnetic wavelengths from ultraviolet (UV) radiation to static electric and magnetic fields. Optical radiation consists of UV, visible and infrared (IR) radiation while EM fields include static, extremely low (ELF), low frequency (LF) and radiofrequency (RF) fields. The principal scientific organization on non-ionizing radiation is the International Commission on Non-Ionizing Radiation Protection (ICNIRP). The main activity of ICNIRP is to provide guidance on safe exposure and protection of workers and members of the public by issuing statements and recommendations. (orig.)

  20. Regulation of nuclear radiation exposures in India

    Energy Technology Data Exchange (ETDEWEB)

    Mishra, U.C. E-mail: ucmishra@yahoo.com

    2004-07-01

    India has a long-term program of wide spread applications of nuclear radiations and radioactive sources for peaceful applications in medicine, industry, agriculture and research and is already having several thousand places in the country where such sources are being routinely used. These places are mostly outside the Department of Atomic Energy (DAE) installations. DAE supplies such sources. The most important application of nuclear energy in DAE is in electricity generation through nuclear power plants. Fourteen such plants are operating and many new plants are at various stages of construction. In view of the above mentioned wide spread applications, Indian parliament through an Act, called Atomic Energy Act, 1964 created an autonomous body called Atomic Energy Regulatory Board (AERB) with comprehensive authority and powers. This Board issues codes, guides, manuals, etc., to regulate such installations so as to ensure safe use of such sources and personnel engaged in such installations and environment receives radiation exposures within the upper bounds prescribed by them. Periodic reports are submitted to AERB to demonstrate compliance of its directives. Health, Safety and Environment Group of Bhabha Atomic Research Centres, Mumbai carries out necessary surveillance and monitoring of all installations of the DAE on a routine basis and also periodic inspections of other installations using radiation sources. Some of the nuclear fuel cycle plants like nuclear power plants and fuel reprocessing involve large radioactive source inventories and have potential of accidental release of radio activity into the environment, an Environmental Surveillance Laboratory (ESL) is set up at each such site much before the facility goes into operation. These ESL's collect baseline data and monitor the environment throughout the life of the facilities including the de- commissioning stage. The data is provided to AERB and is available to members of the public. In addition, a

  1. Regulation of nuclear radiation exposures in India

    International Nuclear Information System (INIS)

    Mishra, U.C.

    2004-01-01

    India has a long-term program of wide spread applications of nuclear radiations and radioactive sources for peaceful applications in medicine, industry, agriculture and research and is already having several thousand places in the country where such sources are being routinely used. These places are mostly outside the Department of Atomic Energy (DAE) installations. DAE supplies such sources. The most important application of nuclear energy in DAE is in electricity generation through nuclear power plants. Fourteen such plants are operating and many new plants are at various stages of construction. In view of the above mentioned wide spread applications, Indian parliament through an Act, called Atomic Energy Act, 1964 created an autonomous body called Atomic Energy Regulatory Board (AERB) with comprehensive authority and powers. This Board issues codes, guides, manuals, etc., to regulate such installations so as to ensure safe use of such sources and personnel engaged in such installations and environment receives radiation exposures within the upper bounds prescribed by them. Periodic reports are submitted to AERB to demonstrate compliance of its directives. Health, Safety and Environment Group of Bhabha Atomic Research Centres, Mumbai carries out necessary surveillance and monitoring of all installations of the DAE on a routine basis and also periodic inspections of other installations using radiation sources. Some of the nuclear fuel cycle plants like nuclear power plants and fuel reprocessing involve large radioactive source inventories and have potential of accidental release of radio activity into the environment, an Environmental Surveillance Laboratory (ESL) is set up at each such site much before the facility goes into operation. These ESL's collect baseline data and monitor the environment throughout the life of the facilities including the de- commissioning stage. The data is provided to AERB and is available to members of the public. In addition, a multi

  2. Evaluation of the radiation exposure. Recommendation of the radiation protection commission

    International Nuclear Information System (INIS)

    Baldauf, Daniela

    2014-01-01

    The recommendation of the Strahlenschutzkommission (radiation protection commission) deals with the realistic requirements for the radiation exposure assessment based on radio-ecological modeling. The recommendation is applicable for all exposure situations that can be derived from FEP (features, events processes) exposure scenarios. In this case the exposure scenario consists of natural and technical features and a set of processes and events that can influence the radiation exposure of the population. The report includes the scientific justification, the previous procedure in Germany and abroad (EURATOM, France, UK, Ukraine, USA).

  3. Occupational exposures in industrial application of radiation during 1999-2008

    International Nuclear Information System (INIS)

    Sanaye, Suresh Shantaram; Baburajan, Sujatha; Pawar, Suresh Ganpat; Nalawade, Shailesh Krishna; Sapra, Balvinder Kaur

    2012-01-01

    Radiation sources are used in various industrial applications like industrial radiograph, industrial irradiation, industrial fluoroscopy, nucleonic gauges, well logging etc., Gamma, beta X-ray as well as neutron sources are used for various applications. Number of radiation workers in this field has increased over the years. Due to operating conditions prevailing during the exposure as well as the strength of the sources used in some of the applications, radiation protection plays an important role in this field. Analysis of doses received by radiation workers in industry provides information on trends of doses as well as adequateness of radiation protection practices followed in this sector. In India, National Occupational Dose Registry System (NODRS) of Radiological Physics and Advisory Division (RPAD), Bhabha Atomic Research Centre (BARC) maintains personnel dose information of monitored radiation workers in the country. Analysis of occupational dose data of industrial radiation workers for last 10 years, i.e., 1999-2008 has been presented in this paper. It is observed that even though there is an increase in monitored radiation workers, percentage of persons receiving radiation exposure has come down during this period. There is also a decrease in the average annual dose as well as the collective dose. Further analysis of sub-categories shows that industrial radiography operations are the main contributor for collective dose (about 77%) followed by well logging and industrial X-ray operations (about 8% each). Thus, in addition to industrial radiography attention is also to be given to operations in these areas. (author)

  4. Occupational exposure to ionizing radiation in Jordanian medical institutions

    International Nuclear Information System (INIS)

    Al-Shakhrah, A. I; Hilow, M. H.

    1999-01-01

    This research survey analyses occupational radiation data 214 Jordanian medical workers during the five-year time period 1990-1994 with the objective of identifying any time dose trend and to determine if annual dose variations exist with regard to sex and job or work status. Comparison of radiation status in Joedanian medical field with that of other countries is a second objective of this study. Biological effects of radiation will, however, not be studied in this research. The statistical analysis of the collected data has shown existence of a decreasing annual dose time trend during the five-year period. This year-to-year variation amy indicate that Jordanian radiation workers are becoming more aware of radiation hazards and they have benefited reasonably from the radiation protection training programmes that were held during that period. These workers are then becoming well abiders by the regulations of the Jordanian radiation authorities. analysis of variance has shown as well that the three factors, which are working status, qualifications and sex, contribute significantly to explaining the variability in annual radiation dose. (authors). 10 refs 4 figs., 7 tabs

  5. Environmental radiation exposure in case of power plant accidents

    International Nuclear Information System (INIS)

    Eder, K.

    1977-01-01

    The paper tries to overcome prejudices concerning radiation effects due to power plant accidents as well as to show the radiation exposure that may be expected near the the patient and to indicate ways and means to avoid or reduce this radiation exposure and to avoid contamination. It is a contribution to better information on radiation accidents and radiolesions in nuclear power plants with the aim of close cooperation between power plants, physicians, and hospitals and of helping to overcome erroneous popular assumptions. (orig./HP) [de

  6. Radiation exposure to patients during extracorporeal shock wave lithotripsy

    International Nuclear Information System (INIS)

    Marti, J.M.; Robles, J.E.; Arbizu, J.; Castro, F. de; Berian, J.M.; Richter, J.A.

    1992-01-01

    We analyzed the radiological exposure to patients during Extracorporeal Shock Wave Lithotripsy (ESWL) using a second generator lithotriptor. Stone location is accomplished by fluoroscopy and 'quick pics' or snapshots. A prospective study over 55 patients showed a mean exposure of 32.2 R. The introduction of the ALARA criterion reduced it to 16.1 R in the following 145 patients. Mean radiation exposure to patient varies according to treatment difficulty. A mean increase of radiation exposure of 1.6 between low and high difficulty treatment groups was observed. This variation was about 96% when the physician who performed the treatment was considered. (author)

  7. Doses from Medical Radiation Sources

    Science.gov (United States)

    ... Medical Radiation Sources Michael G. Stabin, PhD, CHP Introduction Radiation exposures from diagnostic medical examinations are generally ... of exposure annually to natural background radiation. Plain Film X Rays Single Radiographs Effective Dose, mSv Skull ( ...

  8. Population exposure to ultraviolet radiation in Finland 1920-1995: Exposure trends and a time-series analysis of exposure and cutaneous melanoma incidence

    International Nuclear Information System (INIS)

    Kojo, Katja; Jansen, Christer T.; Nybom, Pia; Huurto, Laura; Laihia, Jarmo; Ilus, Taina; Auvinen, Anssi

    2006-01-01

    Ultraviolet radiation (UVR) is the principal cause of cutaneous malignant melanoma (CMM). However, the relation between CMM and UVR exposure is not clear. We present the trends of population exposure to UVR and conduct a time-series analysis of the relation between UVR exposure and incidence of CMM. Data on CMM incidence were obtained from the Finnish Cancer Registry. Clothing coverage of the body was scored from archival photographs and the proportion of uncovered skin was used as a measure of solar exposure. Information on the number of sunny resort holidays, duration of annual holidays, and sunscreen sales were obtained from various sources. Exposed skin area doubled from 1920 to 1985. The average duration of annual holidays increased 30-fold. The number of sunny resort holidays and the sales of sunscreens increased rapidly from 1980. CMM was most strongly associated with solar exposure of 5-19 years earlier. There is a considerable decrease in clothing coverage during the 20th century. UVR exposure preceding CMM occurrence 4 years or less does not appear relevant, whereas the period 5-19 years prior to CMM occurrence might be the most relevant period. However, findings of ecological studies may not be applicable at the individual level

  9. Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2007

    Energy Technology Data Exchange (ETDEWEB)

    LR Roeder

    2007-12-01

    This annual report describes the purpose and structure of the program, and presents key accomplishments in 2007. Notable achievements include: • Successful review of the ACRF as a user facility by the DOE Biological and Environmental Research Advisory Committee. The subcommittee reinforced the importance of the scientific impacts of this facility, and its value for the international research community. • Leadership of the Cloud Land Surface Interaction Campaign. This multi-agency, interdisciplinary field campaign involved enhanced surface instrumentation at the ACRF Southern Great Plains site and, in concert with the Cumulus Humilis Aerosol Processing Study sponsored by the DOE Atmospheric Science Program, coordination of nine aircraft through the ARM Aerial Vehicles Program. • Successful deployment of the ARM Mobile Facility in Germany, including hosting nearly a dozen guest instruments and drawing almost 5000 visitors to the site. • Key advancements in the representation of radiative transfer in weather forecast models from the European Centre for Medium-Range Weather Forecasts. • Development of several new enhanced data sets, ranging from best estimate surface radiation measurements from multiple sensors at all ACRF sites to the extension of time-height cloud occurrence profiles to Niamey, Niger, Africa. • Publication of three research papers in a single issue (February 2007) of the Bulletin of the American Meteorological Society.

  10. 12th Quadrennial Congress of the International Association for Radiation Research incorporating the 50th Annual Meeting of Radiation Research Society, RANZCR Radiation Oncology Annual Scientific Meeting and AINSE Radiation Science Conference

    International Nuclear Information System (INIS)

    2003-01-01

    The 12th International Congress of Radiation Research (ICRR2003), for the first time held in the Southern Hemisphere under the auspices of the International Association of Radiation Research (IARR). The Australian affiliate of IARR is the Australian Institute of Nuclear Science and Engineering (AINSE). As with recent Congresses, the annual scientific meeting of the Radiation Research Society will be incorporated into the program. The Congress will be further enhanced by the integration of the annual scientific meeting of the Faculty of Radiation Oncology of the Royal Australian and New Zealand College of Radiologists, and the AINSE Radiation Science Conference. An exciting programme was presented with the main threads being radiation oncology, radiation biology, radiation chemistry/physics, radiation protection and the environment. Items in INIS scope have been separately indexed

  11. Radiation exposure in nuclear medicine: real-time measurement

    Directory of Open Access Journals (Sweden)

    Iara Sylvain

    2002-09-01

    Full Text Available French regulations have introduced the use of electronic dosimeters for personal monitoring of workers. In order to evaluate the exposure from diagnostic procedures to nuclear medicine staff, individual whole-body doses were measured daily with electronic (digital personal dosimeters during 20 consecutive weeks and correlated with the work load of each day. Personal doses remained always below 20 µSv/d under normal working conditions. Radiation exposure levels were highest to tech staff, nurses and stretcher-bearers. The extrapolated annual cumulative doses for all staff remained less than 10 % of the maximum legal limit for exposed workers (2 mSv/yr. Electronic dosimeters are not technically justified for routine survey of staff. The high sensitivity and immediate reading of electronic semiconductor dosimeters may become very useful for exposure control under risky working conditions. It may become an important help for optimising radiation protection.A legislação francesa introduziu o uso de dosímetros eletrônicos para monitoração da exposição do trabalhador. Afim de avaliar a exposição do trabalhador proveniente de exames diagnósticos em medicina nuclear, doses individuais do corpo inteiro foram medidas diariamente com dosímetros eletrônicos (digitais durante 20 semanas consecutivas e correlatas com as atividades de trabalho de cada dia. As doses foram sempre inferiores à 20 µSv por dia em condições normais de trabalho. Os níveis de exposição de radiação mais elevados foram para os enfermeiros, manipuladores e maqueiros. A extrapolação da dose anual para todos os trabalhadores foi menos que 10 % do limite máximo legal para os trabalhadores expostos (2 mSv/ano. Dosímetros eletrônicos não são tecnicamente justificados para a o controle de rotina da exposição dos trabalhadores, mas a alta sensibilidade e a leitura imediata desses dosímetros podem vir a serem muito úteis para o controle da exposição em condi

  12. Fluoroscopic radiation exposure: are we protecting ourselves adequately?

    Science.gov (United States)

    Hoffler, C Edward; Ilyas, Asif M

    2015-05-06

    While traditional intraoperative fluoroscopy protection relies on thyroid shields and aprons, recent data suggest that the surgeon's eyes and hands receive more exposure than previously appreciated. Using a distal radial fracture surgery model, we examined (1) radiation exposure to the eyes, thyroid, chest, groin, and hands of a surgeon mannequin; (2) the degree to which shielding equipment can decrease exposure; and (3) how exposure varies with fluoroscopy unit size. An anthropomorphic model was fit with radiation-attenuating glasses, a thyroid shield, an apron, and gloves. "Exposed" thermoluminescent dosimeters overlaid the protective equipment at the eyes, thyroid, chest, groin, and index finger while "shielded" dosimeters were placed beneath the protective equipment. Fluoroscopy position and settings were standardized. The mini-c-arm milliampere-seconds were fixed based on the selection of the kilovolt peak (kVp). Three mini and three standard c-arms scanned a model of the patient's wrist continuously for fifteen minutes each. Ten dosimeter exposures were recorded for each c-arm. Hand exposure averaged 31 μSv/min (range, 22 to 48 μSv/min), which was 13.0 times higher than the other recorded exposures. Eye exposure averaged 4 μSv/min, 2.2 times higher than the mean thyroid, chest, and groin exposure. Gloves reduced hand exposure by 69.4%. Glasses decreased eye exposure by 65.6%. There was no significant difference in exposure between mini and standard fluoroscopy. Surgeons' hands receive the most radiation exposure during distal radial plate fixation under fluoroscopy. There was a small but insignificant difference in mean exposure between standard fluoroscopy and mini-fluoroscopy, but some standard units resulted in lower exposure than some mini-units. On the basis of these findings, we recommend routine protective equipment to mitigate exposure to surgeons' hands and eyes, in addition to the thyroid, chest, and groin, during fluoroscopy procedures

  13. The causes and consequences of human exposure to ionising radiation

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1991-01-01

    Few phenomena cause as much concern in developed countries as human exposure to artificial sources of radiation, and yet there are more potent threats to health: natural radiation is more pervasive and exposures more substantial; common practices such as smoking and drinking are more detrimental. Developing countries may be more anxious to establish radiological procedures than radiological protection. This paper gives the ranges of exposure to which people are subjected from natural and artificial sources which should help to put all doses in perspective. The relationship between dose and risk is established and used to show that exposures to radiation leak to low levels of risk. Finally, the new recommendations of ICRP for the control of radiation risk are presented. (Author)

  14. Mouse fecal microbiome after exposure to high LET radiation

    Data.gov (United States)

    National Aeronautics and Space Administration — Space travel is associated with continuous low-dose-rate exposure to high Linear Energy Transfer (LET) radiation. Pathophysiological manifestations after low-dose...

  15. Factors influencing radiation exposure during the extracorporeal shock wave lithotripsy

    Energy Technology Data Exchange (ETDEWEB)

    Wei Chuan Chen; Ying Huei Lee; Ming Tsun Chen; Jong Khing Huang; Luke S Chang (Division of Urology, Dept. of Surgery, National Yang-Ming Medical College and Veterans General Hospital-Taipei, Taiwan (China))

    1991-01-01

    A prospective evaluation of 89 consecutive sessions of extracorporeal shock wave lithotripsy (ESWL) was undertaken to try and find the best way of minimising the amount of exposure to radiation. Forty-two patients were randomly allocated to undergo ESWL treatment by experienced surgeons (group A), and 47 to undergo the treatment by inexperienced surgeons (group B). The mean calculated entrance radiation exposure was 3.01 rads (group A: 2.64 (0.97) rads, range 1.00-4.48, group B: 3.38 (0.86) rads, range 1.11-5.75). Among factors that influenced radiation exposure, the tissue: air ratio should be borne in mind and the level of skill in controlling movement of gantry was the most important in reducing the exposure to radiation. (au).

  16. Factors influencing radiation exposure during the extracorporeal shock wave lithotripsy

    International Nuclear Information System (INIS)

    Wei Chuan Chen; Ying Huei Lee; Ming Tsun Chen; Jong Khing Huang; Luke S Chang

    1991-01-01

    A prospective evaluation of 89 consecutive sessions of extracorporeal shock wave lithotripsy (ESWL) was undertaken to try and find the best way of minimising the amount of exposure to radiation. Forty-two patients were randomly allocated to undergo ESWL treatment by experienced surgeons (group A), and 47 to undergo the treatment by inexperienced surgeons (group B). The mean calculated entrance radiation exposure was 3.01 rads (group A: 2.64 (0.97) rads, range 1.00-4.48, group B: 3.38 (0.86) rads, range 1.11-5.75). Among factors that influenced radiation exposure, the tissue: air ratio should be borne in mind and the level of skill in controlling movement of gantry was the most important in reducing the exposure to radiation. (au)

  17. UDAD, Radiation Exposure to Man at Uranium Processing Plant

    International Nuclear Information System (INIS)

    Momeni, M.H.; Yuan, Y.; Zielen, A.J.

    1983-01-01

    1 - Description of problem or function: The Uranium Dispersion and Dosimetry (UDAD) program provides estimates of potential radiation exposure to individuals and to the general population in the vicinity of a uranium processing facility such as a uranium mine or mill. Only transport through the air is considered. Exposure results from inhalation, external irradiation from airborne and ground- deposited activity, and ingestion of foodstuffs. Individual dose commitments, population dose commitments, and environmental dose commitments are computed. The program was developed for application to uranium mining and milling; however, it may be applied to dispersion of any other pollutant. 2 - Method of solution: The removal of radioactive particles from a contaminated area such as uranium tailings by wind action is estimated from theoretical and empirical wind-erosion equations according to the wind speed, particle size distribution, surface roughness, and other parameters. Atmospheric concentrations of radioactivity from specific sources are calculated by means of a dispersion-deposition-resuspension model. Source depletion as a result of deposition, fallout of the heavier particulates, and radioactive decay and ingrowth of radon daughters are included in a sector-averaged, Gaussian plume dispersion model. The average air concentration at any given receptor location is assumed to be constant during each annual release period, but to increase from year to year because of resuspension. Surface contamination is estimated by including buildup from deposition, ingrowth of radio- active daughters, and removal by radioactive decay, weathering, and other environmental processes. Deposition velocity is estimated on the basis of particle size, density, and physical and chemical environmental conditions which influence the behavior of the smaller particles. Calculation of the inhalation dose to an individual is based on the ICRP Task Group Lung Model (TGLM). Estimates of the dose to

  18. Variations with time and age in the relative risks of solid cancer incidence after radiation exposure

    International Nuclear Information System (INIS)

    Little, M.P.; Muirhead, C.R.; de Vathaire, F.; Charles, M.W.

    1997-01-01

    The Japanese atomic bomb survivor cancer incidence dataset and data on five groups exposed to radiation for medical reasons in childhood are analysed and evidence found for a reduction in the radiation-induced relative risk of cancers other than leukaemia with increasing time since exposure and age at exposure. The rate of the reductions in relative risk with time since exposure are not significantly different for those exposed in childhood and for those exposed in adulthood, if adjustment is made for the effects on the relative risk of age at exposure. For those irradiated in childhood, there is a statistically significant annual reduction of 5.8% (95% Cl 2.8, 8.9) in excess relative risk, and there are no strong indications of inter-cohort heterogeniety in the speed of reduction of relative risk. After adjustment for the effects of age at exposure, there is a significant annual reduction of 3.6% (95% Cl 1.6, 5.6) in excess relative risk in all age-at-exposure groups. There are significant reductions of 5.2% (95% Cl 3.7, 6.8) in excess relative risk per year of age at exposure. There are statistically significant (P = 0.04) interactions between the exponential adjustments to the excess relative risk for age at exposure and time since exposure in the Japanese data, but no indications (P = 0.38) of such interactions when powers of time since exposure and attained age are used to adjust the excess relative risk, so that the fit of the model with power adjustments is to be preferred to that of the model with exponential adjustments. (author)

  19. Medical radiation exposure and usage for diagnostic radiology in Malaysia

    International Nuclear Information System (INIS)

    Ng, Kwan-Hoong; Rassiah, Premavathy; Abdullah, B.J.J.; Wang, Hwee-Beng; Shariff Hambali, Ahmad; Muthuvelu, Pirunthavany; Sivalingam, S.

    2001-01-01

    A national dose survey of routine X-ray examinations in Malaysia (a Level II country) from 1993 to 1995 had established baseline data for seven common types of x-ray examinations. A total of 12 randomly selected public hospitals and 867 patients were included in this survey. Survey results are generally comparable with those reported in the UK, USA and IAEA. The findings support the importance of the ongoing national quality assurance programme to ensure doses are kept to a level consistent with optimum image quality. The data was useful in the formulation of national guidance levels as recommended by the IAEA. The medical radiation exposure and usage for diagnostic radiology (1990-1994) enabled a comparison to be made for the first time with the UNSCEAR 2000 Report. In 1994, the number of physicians, radiologists, x-ray units and x-ray examinations per 1000 population was 0.45, 0.005, 0.065 and 183, respectively; 3.6 million x-ray examinations were performed; the annual effective dose per capita was 0.05 mSv and collective dose was 1000 person-Sv. Chest examinations contributed 63% of the total. Almost all examinations experienced increasing frequency except for barium studies, cholecystography, and intravenous urography (-23%, -36%, -51%). Notable increases were observed in computed tomography (161%), cardiac procedures (190%), and mammography (240%). (author)

  20. Miners' radiation exposure in a subsurface bauxite-mine

    International Nuclear Information System (INIS)

    Somlai, J.; Kovacs, T.; Jobbagy, V.; Varhegyi, A.

    2004-01-01

    To examine the natural origin radioactivity of the bauxite samples we can establish that the 226 Ra activity concentration exceeded (155-489 Bq/kg) the average values measured in the rocks (25-40 Bq/kg). 222 Rn produced from the 226 Ra could be concentrated in the mines. In the course of our work we carried out an extensive radiological-dosimetric survey for 1 month. On the grounds of the different kind of working processes we put 11 track detectors in different places and continuous radon detector equipment were placed into 2 sites. Besides these measurements we determined the gamma dose rate, the equilibrium factor, the amount of the flying-dust and the long-lived alpha emitter isotopes 2 times in 7 different places. We gave personal radon dosimeter to 14 miners. It was worn only during the working time and after hours was stored in a well-controlled Rn concentration place. The average radon activity concentration measured in different places in the mine changed between 204-3910 Bq/m 3 . We found very high radon levels some places especially in the drawings. The miners during this 1 month have taken part several mining processes, so lower values were detected. To take into account the results, the miners' estimated annual dose exposure is between the range of 2.5-10.2 mSv/y which is not negligible compared to the natural radiation background (2.5 mSv/y). (author)