WorldWideScience

Sample records for calculating radiation exposures

  1. 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

  2. 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.

  3. The calculation of maximum permissible exposure levels for laser radiation

    International Nuclear Information System (INIS)

    Tozer, B.A.

    1979-01-01

    The maximum permissible exposure data of the revised standard BS 4803 are presented as a set of decision charts which ensure that the user automatically takes into account such details as pulse length and pulse pattern, limiting angular subtense, combinations of multiple wavelength and/or multiple pulse lengths, etc. The two decision charts given are for the calculation of radiation hazards to skin and eye respectively. (author)

  4. 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

  5. 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

  6. Calculation of radiation exposure in diagnostic radiology. Method and surveys

    International Nuclear Information System (INIS)

    Duvauferrier, R.; Ramee, A.; Ezzeldin, K.; Guibert, J.L.

    1984-01-01

    A computerized method for evaluating the radiation exposure of the main target organs during various diagnostic radiologic procedures is described. This technique was used for educational purposes: study of exposure variations according to the technical modalities of a given procedure, and study of exposure variations according to various technical protocols (IVU, EGD barium study, etc.). This method was also used for studying exposure of patients during hospitalization in the Rennes Regional Hospital Center (France) in 1982, according to departments (urology, neurology, etc.). This method and results of these three studies are discussed [fr

  7. 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

  8. 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.

  9. New physical model calculates airline crews' radiation exposure

    Science.gov (United States)

    Schultz, Colin

    2013-12-01

    Airline pilots and crews, who spend hundreds of hours each year flying at high altitude, are exposed to increased doses of radiation from galactic cosmic rays and solar energy particles, enough that airline crew members are actually considered radiation workers by the International Commission on Radiological Protection.

  10. Calculation of radiation exposures from patients to whom radioactive materials have been administered

    Science.gov (United States)

    Cormack, John; Shearer, Jane

    1998-03-01

    Spreadsheet templates which calculate cumulative exposures to other persons from patients to whom radioactive materials have been administered have been developed by the authors. Calculations can be based on any specified single-, bi- or tri-exponential whole-body clearance rate and a diurnal (or any other periodic) contact pattern. The time (post-administration) during which close contact should be avoided in order to constrain the radiation exposure and exposure rates to selected limits is also calculated using an iterative technique (Newton's method), and the residual activity at the time when contact can resume is also calculated. These templates find particular application in the calculation of exposures to persons who are in contact with patients who have received for therapeutic purposes. The effect of changing dose limits, contact patterns and using individually derived clearance rates may be readily modelled.

  11. Calculation of radiation exposures from patients to whom radioactive materials have been administered

    International Nuclear Information System (INIS)

    McCormack, J.; Shearer, J.

    1998-01-01

    Spreadsheet templates have been developed by the authors to calculate radiation exposures to others from patients to whom radioactive materials have been administered (or, indeed, from any source of radiation exposure) to be readily calculated. The time during which contact should be avoided, along with the residual activity at resumption of contact is also calculated using an iterative technique. These spreadsheets allow a great deal of flexibility in the specification of clearance rates and close contact patterns for individual patients. Estimates of doses, restriction times and residual activities for 131 l thyrotoxic therapy, for various contact patterns and group of patients, were calculated. The spreadsheets are implemented using Microsoft EXCEL for both PC and Macintosh computers, and are readily available from the authors

  12. Dose factors to calculate the radiation exposure due to radioactive waste air from nuclear facilities

    International Nuclear Information System (INIS)

    Brenk, H.D.; Vogt, K.J.

    1977-01-01

    An evaluation of the environmental impact of nuclear plants according to paragraph 45 of the Radiation Protection Directive of the Federal Republic of Germany requires the calculation of dose conversion factors indicating the correlation between the contaminated medium and individual radiation exposure. The present study is to be conceived as a contribution to discussion on this subject. For the determination of radiation exposure caused by the waste air of nuclear plants, models are being specified for computing the dose conversion factors for the external exposure pathways of β-submersion, γ-submersion and γ-radiation from contaminated ground as well as the internal exposure pathways of inhalation and ingestion, which further elaborate and improve the models previously applied, especially as far as the ingestion pathway is concerned, which distinguishes between 6 major food categories. The computer models are applied to those radionuclides which are significan for nuclear emitters, in particular nuclear light-water power stations. The results obtained for the individual exposure pathways and affected organs are specified in the form of tables. For this purpose, calculations were first of all carried out for the so-called 'reference man'. The results can be transferred to population groups with different consumption habits (e.g. vegetarians) by the application of correction factors. The models are capable of being extended with a view to covering other age groups. (orig.) [de

  13. Calculation of conversion coefficients for radiological protection against external radiation exposures

    International Nuclear Information System (INIS)

    Zankl, M.

    2001-01-01

    Calculations are essential for radiation protection practice because organ doses and effective doses cannot be measured directly. Conversion coefficients describe the numerical relationships of protection quantities and operational quantities. The latter can be measured in practical situations using suitable dosimeters. The conversion coefficients are calculated using radiation transport codes - usually based on Monte Carlo methods - that simulate the interactions of radiation with matter in computational models of the human body. A new generation of human body models, the so-called voxel models, are constructed from image data of real persons using suitable image processing systems, consequently, they represent the human anatomy more realistically than the so-called mathematical models. The numerical effects of realistic body anatomy on the calculated conversion coefficients can amount to 70% and more for external exposures. (orig.) [de

  14. Utilization of MAX and FAX human phantoms for space radiation exposure calculations using HZETRN

    Science.gov (United States)

    Qualls, Garry; Slaba, Tony; Clowdsley, Martha; Blattnig, Steve; Walker, Steven; Simonsen, Lisa

    To estimate astronaut health risk due to space radiation, one must have the ability to calculate, for known radiation environments external to the body, particle spectra, LET spectra, dose, dose equivalent, or gray equivalent that are averaged over specific organs or tissue types. This may be accomplished using radiation transport software and computational human body tissue models. Historically, NASA scientists have used the HZETRN software to calculate radiation transport through both vehicle shielding materials and body tissue. The Computerized Anatomical Man (CAM) and the Computerized Anatomical Female (CAF) body models, combined with the CAMERA software, have been used for body tissue self-shielding calculations. The CAM and CAF, which were developed in 1973 and 1992, respectively, model the 50th percentile U.S. Air Force male and female and are constructed using individual quadric surfaces that combine to form thousands of solid regions that represent specific tissues and structures within the body. In order to transport an external radiation environment to a point within one of the body models using HZETRN, a directional distribution of the tissues surrounding that point is needed. The CAMERA software is used to "ray trace" the CAM and CAF models, providing the thickness of each tissue type traversed along each of a large number of rays originating at a dose point. More recently, R. Kramer of the Departmento de Energia Nuclear, Universidade Federal de Pernambuco in Brazil and his co-workers developed the Male Adult voXel (MAX) model and the Female Adult voXel (FAX). These voxel-based body models were developed using segmented Computed Tomography (CT) scans of adult cadavers, and the quantities and distributions of various body tissues have been adjusted to match those specified in the International Commission on Radiological Protection (ICRP) reference adult male and female. A new set of tools has been developed to facilitate space radiation exposure

  15. Comparison of two spreadsheets for calculation of radiation exposure following hyperthyroidism treatment with iodine-131

    Energy Technology Data Exchange (ETDEWEB)

    Vrigneaud, J.M. [CHU Bichat, nuclear medicine department, 75 - Paris (France); Carlier, T. [CHU Hotel Dieu, nuclear medicine department, 44 - Nantes (France)

    2006-07-01

    Comparison of the two spreadsheets did not show any significant differences provided that proper biological models were used to follow 131 iodine clearance. This means that even simple assumptions can be used to give reasonable radiation safety recommendations. Nevertheless, a complete understanding of the formalism is required to use correctly these spreadsheets. Initial parameters must be chosen carefully and validation of the computed results must be done. Published guidelines are found to be in accordance with those issued from these spreadsheets. Furthermore, both programs make it possible to collect biological data from each patient and use it as input to calculate individual tailored radiation safety advices. Also, measured exposure rate may be entered into the spreadsheets to calculate patient-specific close contact delays required to reduce the dose to specified limits. These spreadsheets may be used to compute restriction times for any given radiopharmaceutical, provided that input parameters are chosen correctly. They can be of great help to physicians to provide patients with guidance on how to maintain doses to other individuals as low as reasonably achievable. (authors)

  16. Comparison of two spreadsheets for calculation of radiation exposure following hyperthyroidism treatment with iodine-131

    International Nuclear Information System (INIS)

    Vrigneaud, J.M.; Carlier, T.

    2006-01-01

    Comparison of the two spreadsheets did not show any significant differences provided that proper biological models were used to follow 131 iodine clearance. This means that even simple assumptions can be used to give reasonable radiation safety recommendations. Nevertheless, a complete understanding of the formalism is required to use correctly these spreadsheets. Initial parameters must be chosen carefully and validation of the computed results must be done. Published guidelines are found to be in accordance with those issued from these spreadsheets. Furthermore, both programs make it possible to collect biological data from each patient and use it as input to calculate individual tailored radiation safety advices. Also, measured exposure rate may be entered into the spreadsheets to calculate patient-specific close contact delays required to reduce the dose to specified limits. These spreadsheets may be used to compute restriction times for any given radiopharmaceutical, provided that input parameters are chosen correctly. They can be of great help to physicians to provide patients with guidance on how to maintain doses to other individuals as low as reasonably achievable. (authors)

  17. Basis for calculating body equivalent doses after external radiation exposure. 3. rev. and enl. ed.; Berechnungsgrundlage fuer die Ermittlung von Koerper-Aequivalentdosen bei aeusserer Strahlenexposition

    Energy Technology Data Exchange (ETDEWEB)

    Sarenio, O. (comp.) [Geschaeftsstelle der Strahlenschutzkommission beim Bundesamt fuer Strahlenschutz, Bonn (Germany)

    2017-07-01

    The book on the basis for calculating body equivalent doses after external radiation exposure includes the following issues: introduction covering the scope of coverage and body equivalent doses for radiation protection, terminology, photon radiation, neutron radiation, electron radiation, mixed radiation fields and the estimation of body equivalent doses for skin surface contamination.

  18. Cosmic radiation exposure of aircraft crew: compilation of measured and calculated data

    Czech Academy of Sciences Publication Activity Database

    Lindborg, L.; Bartlett, D.; Beck, P.; McAulay, I.; Schnuer, K.; Schraube, H.; Spurný, František

    2004-01-01

    Roč. 110, 1-4 (2004), s. 417-422 ISSN 0144-8420 Grant - others:EC project(XE) FIGM-CT2000-00068 Institutional research plan: CEZ:AV0Z1048901 Keywords : cosmic radiation exposure * aircraft crew * measurement Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.617, year: 2003

  19. The calculation of collective radiation exposure arising from discharges of activity into an estuary or sea in the British Isles

    International Nuclear Information System (INIS)

    Maul, P.R.

    1982-04-01

    A model is described for the calculation of collective radiation exposure for releases of activity to an estuary or sea. The model is based on methods described by the CEC with the main exposure pathways being via the ingestion of seafood and external exposure on beaches. For tritium the most important pathway arises from the transfer of activity from the marine to the atmospheric environment. The model is best suited for calculations for fairly long-lived nuclides which do not become dispersed globally and for which the seafood ingestion pathway is dominant. Dose calculations for short-lived nuclides or nuclides where the external exposure pathway can be important will have greater uncertainty associated with them. A computer code CODAR is being developed which incorporates this model. (author)

  20. Concepts for the calculation of radiation exposure in the environment of nuclear plants for planning and surveillance purposes

    International Nuclear Information System (INIS)

    Brenk, H.D.; Vogt, K.J.; Bruessermann, K.; Schwarz, G.

    1977-01-01

    In connection with the release of radioactive substances from nuclear plants, the following requirements are to be met in respect of the assessment of radiation exposure of persons in the environment of the plant: for the purpose of planning and licencing nuclear plants, the release rates of radioactive substances are to be limited to such a degree that the dose limit values specified in the Radiation Protection Ordinance are not exceeded at any time or on any site. This applies possibly under consideration of the pre-exposure rate. For long-lived radionuclides this requirement involves the calculation of annual doses at the end of a period determined by the time of operation of the plant and by the exposure time of the persons. During the operation of nuclear plants it is necessary to calculate the radiation exposure rates resulting from the emission measured for the year of reference. This application requires the calculation of the dose commitment resulting in the future on the basis of annual emissions for persons living in the environment of the plant. In connection with the long-term prediction of the environmental impact caused by the entire nuclear industry, problems will also be arising in conjunction with the case history of the environmental exposure being subject to respective alterations as a result of additional plants

  1. Modeling of radionuclide transport through rock formations and the resulting radiation exposure of reference persons. Calculations using Asse II parameters

    International Nuclear Information System (INIS)

    Kueppers, Christian; Ustohalova, Veronika; Steinhoff, Mathias

    2012-01-01

    The long-term release of radioactivity into the ground water path cannot be excluded for the radioactive waste repository Asse II. The possible radiological consequences were analyzed using a radio-ecological scenario developed by GRS. A second scenario was developed considering the solubility of radionuclides in salt saturated solutions and retarding/retention effects during the radionuclide transport through the cap rock layers. The modeling of possible radiation exposure was based on the lifestyle habits of reference persons. In Germany the calculation procedure for the prediction of radionuclide release from final repositories is not defined by national standards, the used procedures are based on analogue methods from other radiation protection calculations.

  2. Results of calculations of external gamma radiation exposure rates from fallout and the related radionuclide compositions. Operation Tumbler-Snapper, 1952

    International Nuclear Information System (INIS)

    Hicks, H.G.

    1981-07-01

    This report presents data on calculated gamma radiation exposure rates and ground deposition of related radionuclides resulting from Events that deposited detectable radioactivity outside the Nevada Test Site complex

  3. 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

  4. 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.

  5. SESAM: a model for the calculation of radiation exposure by emission of pollutants with the exhaust air in the case of a multi-source situation

    International Nuclear Information System (INIS)

    Ehrlich, H.G.; Vogt, K.J.; Brunen, E.

    The report deals with the calculation of the individual radiation exposure in the catchment area of several nuclear emitters. A model and computer program, SESAM - Calculation of the Radiation Exposure by Emission of Pollutants with the Exhaust air in the Case of a Multi-Source Situation -, was developed which makes possible all the evaluations of long-time exposure which are relevant for the licensing process - such as the determination of the maximum individual radiation exposure to the various organs at the worst receiving point - together with the exposure of the environment by several nuclear emission sources - such as, for example, several units of a power plant facility, the various emitters of a waste management center, or even consideration of the previous exposure of a site by nuclear emission sources

  6. 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.)

  7. Solar UV radiation exposure of seamen - Measurements, calibration and model calculations of erythemal irradiance along ship routes

    Energy Technology Data Exchange (ETDEWEB)

    Feister, Uwe [German Meteorological Service, Meteorological Observatory Lindenberg - Richard-Assmann-Observatory, Am Observatorium 12, 15848 Lindenberg (Germany); Meyer, Gabriele; Kirst, Ulrich [German Social Accident Insurance Institution for Transport and Traffic, Ottenser Hauptstrasse 54, 22765 Hamburg (Germany)

    2013-05-10

    Seamen working on vessels that go along tropical and subtropical routes are at risk to receive high doses of solar erythemal radiation. Due to small solar zenith angles and low ozone values, UV index and erythemal dose are much higher than at mid-and high latitudes. UV index values at tropical and subtropical Oceans can exceed UVI = 20, which is more than double of typical mid-latitude UV index values. Daily erythemal dose can exceed the 30-fold of typical midlatitude winter values. Measurements of erythemal exposure of different body parts on seamen have been performed along 4 routes of merchant vessels. The data base has been extended by two years of continuous solar irradiance measurements taken on the mast top of RV METEOR. Radiative transfer model calculations for clear sky along the ship routes have been performed that use satellite-based input for ozone and aerosols to provide maximum erythemal irradiance and dose. The whole data base is intended to be used to derive individual erythemal exposure of seamen during work-time.

  8. Results of calculations of external gamma radiation exposure rates from local fallout and the related radionuclide compositions of two hypothetical 1-MT nuclear bursts. Final report

    International Nuclear Information System (INIS)

    Hicks, H.

    1984-12-01

    This report presents data on calculated gamma radiation exposure rates and local surface deposition of related radionuclides resulting from two hypothetical 1-Mt nuclear bursts. Calculations are made of the debris from two types of bombs: one containing 235 U as a fissionable material (designated oralloy), the other containing 238 U (designated tuballoy). 4 references

  9. 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...

  10. Measurement and calculation of cosmic radiation exposure during a pole-to-pole flight sequence

    International Nuclear Information System (INIS)

    Taylor, Graeme C.; Ojjeh, Captain Aziz

    2010-01-01

    Cosmic ray dosimetry measurements were carried out on board a Global Express business jet operated by TAG Aviation (UK) during a pole-to-pole flight sequence that took place in November 2008. One Hawk TEPC and two EPDN2s were flown, and the TEPC measurements compared to calculated values from the route dose codes AVIDOS, CARI 6M, EPCARD versions 3.2 and 3.34, QARM and SIEVERT (online version). The largest difference between measured and calculated doses for the total flight sequence was found to be 13%. Agreement between the readings of the TEPC and the EPDN2s (once a calibration factor from the CERN High Energy Reference Field had been applied) was reasonably good given the relatively large uncertainties associated with the EPDN2 measurements.

  11. Influence of the most important data on the calculation of the maximum radiation exposure in the vicinity of nuclear facilities

    International Nuclear Information System (INIS)

    Schmidtlein, P.; Bonka, H.; Hesel, D.; Horn, H.G.

    1980-01-01

    Analysis of radiation exposure due to radionuclides released from nuclear facilities is discussed in relation to the demands of the Radiation Protection Oridinance in the Federal Republic of Germany. The results of the following estimations are presented as examples:- 1) The contribution of relevant radionuclides to the radiation exposure of an adult via the air pathway. 2) Contribution of relevant radionuclides to the radiation exposure of an adult via the water pathway. 3) Doses to lung and bone due to inhalation of 90 Sr aerosols with various particle diameters. 4) The influence of the plant-, milk- and meat transfer factors on the ingestion dose. 5) Accumulation factors in fish, in relation to consumption. 6) Variation of ground concentration due to loss of radionuclides via washing out into lower soil layers and harvest. (U.K.)

  12. 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 ...

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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)

  19. 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.)

  20. 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

  1. Calculating disability-adjusted life years (DALY) as a measure of excess cancer risk following radiation exposure

    International Nuclear Information System (INIS)

    Shimada, K; Kai, M

    2015-01-01

    This paper has proposed that disability-adjusted life year (DALY) can be used as a measure of radiation health risk. DALY is calculated as the sum of years of life lost (YLL) and years lived with disability (YLD). This multidimensional concept can be expressed as a risk index without a probability measure to avoid the misuse of the current radiation detriment at low doses. In this study, we calculated YLL and YLD using Japanese population data by gender. DALY for all cancers in Japan per 1 Gy per person was 0.84 year in men and 1.34 year in women. The DALY for all cancers in the Japanese baseline was 4.8 in men and 3.5 in women. When we calculated the ICRP detriment from the same data, DALYs for the cancer sites were similar to the radiation detriment in the cancer sites, excluding leukemia, breast and thyroid cancer. These results suggested that the ICRP detriment overestimate the weighting fraction of leukemia risk and underestimate the weighting fraction of breast and thyroid cancer. A big advantage over the ICRP detriment is that DALY can calculate the risk components for non-fatal diseases without the data of lethality. This study showed that DALY is a practical tool that can compare many types of diseases encountered in public health. (paper)

  2. 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.)

  3. 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

  4. 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

  5. Animal mortality resulting from uniform exposures to photon radiations: Calculated LD50s and a compilation of experimental data

    International Nuclear Information System (INIS)

    Jones, T.D.; Morris, M.D.; Wells, S.M.; Young, R.W.

    1986-12-01

    Studies conducted during the 1950s and 1960s of radiation-induced mortality to diverse animal species under various exposure protocols were compiled into a mortality data base. Some 24 variables were extracted and recomputed from each of the published studies, which were collected from a variety of available sources, primarily journal articles. Two features of this compilation effort are (1) an attempt to give an estimate of the uniform dose received by the bone marrow in each treatment so that interspecies differences due to body size were minimized and (2) a recomputation of the LD 50 where sufficient experimental data are available. Exposure rates varied in magnitude from about 10 -2 to 10 3 R/min. This report describes the data base, the sources of data, and the data-handling techniques; presents a bibliography of studies compiled; and tabulates data from each study. 103 refs., 44 tabs

  6. Calculating radiation exposures during use of (14)C-labeled nutrients, food components, and biopharmaceuticals to quantify metabolic behavior in humans.

    Science.gov (United States)

    Kim, Seung-Hyun; Kelly, Peter B; Clifford, Andrew J

    2010-04-28

    (14)C has long been used as a tracer for quantifying the in vivo human metabolism of food components, biopharmaceuticals, and nutrients. Minute amounts (food components, biopharmaceuticals, or nutrients to be organized into models suitable for quantitative hypothesis testing and determination of metabolic parameters. In vivo models are important for specification of intake levels for food components, biopharmaceuticals, and nutrients. Accurate estimation of the radiation exposure from ingested (14)C is an essential component of the experimental design. Therefore, this paper illustrates the calculation involved in determining the radiation exposure from a minute dose of orally administered (14)C-beta-carotene, (14)C-alpha-tocopherol, (14)C-lutein, and (14)C-folic acid from four prior experiments. The administered doses ranged from 36 to 100 nCi, and radiation exposure ranged from 0.12 to 5.2 microSv to whole body and from 0.2 to 3.4 microSv to liver with consideration of tissue weighting factor and fractional nutrient. In comparison, radiation exposure experienced during a 4 h airline flight across the United States at 37000 ft was 20 microSv.

  7. 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

  8. 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

  9. 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

  10. 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.)

  11. 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

  12. The calculation of individual radiation exposure rates arising from routine discharges of activity into an estuary or sea

    International Nuclear Information System (INIS)

    Maul, P.R.

    1982-03-01

    Simple methods are described which enable assessments to be made of exposure rates to individuals arising from the release of activity into an estuary or sea. These methods are based in the main on those employed by the Ministry of Agriculture Fisheries and Food together with models developed by the author. The exposure routes considered are the ingestion of seafood and external exposure from β and γ emitters arising from occupancy over contaminated sediments or beaches and the handling of fishing gear. These routes are generally the most important, but for any chosen site it will also be necessary to determine whether any other exposure routes are significant. (author)

  13. The calculation of individual radiation exposure rates arising from routine discharges of activity into an estuary or sea

    International Nuclear Information System (INIS)

    Maul, P.R.

    1982-11-01

    Simple methods are described which enable assessments to be made of exposure rates to individuals arising from the release of activity into an estuary or sea. These methods are based in the main on those employed by the Ministry of Agriculture Fisheries and Food together with models developed by the author. The exposure routes considered are the ingestion of seafood and external exposure from ν and ν emitters arising from occupancy over contaminated sediments or beaches and the handling of fishing gear. These routes are generally the most important, but for any chosen site it will also be necessary to determine whether any other exposure routes are significant. (author)

  14. INDAR: a computer code for the calculation of critical group radiation exposure from routine discharges of radioactivity to seas and estuaries - description and users' guide

    International Nuclear Information System (INIS)

    Maul, P.R.; Wilmott, S.

    1988-12-01

    The computer program INDAR enables detailed estimates to be made of critical group radiation exposure arising from routine discharges of radioactivity for coastal sites where the discharge is close to the shore and the shoreline is reasonably straight, and for estuarine sites where radioactivity is rapidly mixed across the width of the estuary. Important processes which can be taken into account include the turbulence generated by the discharge, the effects of a sloping sea bed and the variation with time of the lateral dispersion coefficient. The significance of the timing of discharges can also be assessed. INDAR uses physically meaningful hydrographic parameters directly. For most sites the most important exposure pathways are seafood consumption, external exposure over estuarine sediments and beaches, and the handling of fishing gear. As well as for these primary pathways, INDAR enables direct calculations to be made for some additional exposure pathways. The secondary pathways considered are seaweed consumption, swimming, the handling of materials other than fishing gear and the inhalation of activity. (author)

  15. 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

  16. Calculation of radiation exposure of the environment of interim storage facilities for the dry storage of spent fuel in dual-purpose casks

    Energy Technology Data Exchange (ETDEWEB)

    Wortmann, B.; Stratmann, W. [STEAG Encotec GmbH, Essen (Germany)

    2004-07-01

    Acceptance problems in the public concerning the transport of spent nuclear fuel elements and a new political objective of the Federal Government have forced the German utilities to embark on on-site interim storage projects for the temporary storage of spent nuclear fuel elements. STEAG encotec GmbH, Essen, Germany, was awarded contracts for the conceptual planning including necessary shielding calculations for the majority of the 13 nuclear sites which opted for the dry storage concept. The capacity of the storage facilities ranges from 80 to 100 casks, according to the storage needs of the plants. The average dose rate at the surface of each cask was limited to 0.5 mSv/h, independent of the type of radiation. These new buildings should not significantly increase the exposure of the public to radiation already originating from the existing nuclear power plant. The layout of the storage building therefore has to ensure that additional target values of 10-20 iSv/y are not exceeded. These very low target values as well as the requirement to avoid high mechanical impacts to the casks in case of external events led to a thickness of walls and ceilings of between 1.2 m and 1.3 m. To remove the decay heat from the casks by natural convection sufficient cross sections of the air inlet and outlet ducts are required.

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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

  4. Calculation of the dose caused by internal radiation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    For the purposes of monitoring radiation exposure it is necessary to determine or to estimate the dose caused by both external and internal radiation. When comparing the value of exposure to the dose limits, account must be taken of the total dose incurred from different sources. This guide explains how to calculate the committed effective dose caused by internal radiation and gives the conversion factors required for the calculation. Application of the maximum values for radiation exposure is dealt with in ST guide 7.2, which also sets out the definitions of the quantities and concepts most commonly used in the monitoring of radiation exposure. The monitoring of exposure and recording of doses are dealt with in ST Guides 7.1 and 7.4.

  5. 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.

  6. 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.

  7. 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)

  8. Engineering calculations in radiative heat transfer

    CERN Document Server

    Gray, W A; Hopkins, D W

    1974-01-01

    Engineering Calculations in Radiative Heat Transfer is a six-chapter book that first explains the basic principles of thermal radiation and direct radiative transfer. Total exchange of radiation within an enclosure containing an absorbing or non-absorbing medium is then described. Subsequent chapters detail the radiative heat transfer applications and measurement of radiation and temperature.

  9. 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)

  10. 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

  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. 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

  13. Radiation damage calculations for the LANSCE degrader

    International Nuclear Information System (INIS)

    Ferguson, P.D.; Sommer, W.F.; Dudziak, D.J.; Wechsler, M.S.; Barnett, M.H.; Corzine, R.K.

    1998-01-01

    The A-6 water degrader at the Los Alamos Neutron Science Center (LANSCE) linear proton accelerator has an outer shell of Inconel 718. The degrader was irradiated by 800-MeV protons during 1988--1993 to an exposure of 5.3 ampere-hours (A h). As described in Ref. 1, material from the Inconel is currently being cut into specimens for microhardness, three-point bending, ball punch, microscopy, and corrosion tests. This paper is devoted to calculations of radiation damage, particularly displacement and He production, sustained by the degrader Inconel

  14. 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)

  15. Modeling of radionuclide transport through rock formations and the resulting radiation exposure of reference persons. Calculations using Asse II parameters; Modellierung des Transports von Radionukliden durch Gesteinsschichten und der resultierenden Strahlenexposition von Referenzpersonen. Berechnungen mit Parametern der Asse II

    Energy Technology Data Exchange (ETDEWEB)

    Kueppers, Christian; Ustohalova, Veronika; Steinhoff, Mathias

    2012-05-21

    The long-term release of radioactivity into the ground water path cannot be excluded for the radioactive waste repository Asse II. The possible radiological consequences were analyzed using a radio-ecological scenario developed by GRS. A second scenario was developed considering the solubility of radionuclides in salt saturated solutions and retarding/retention effects during the radionuclide transport through the cap rock layers. The modeling of possible radiation exposure was based on the lifestyle habits of reference persons. In Germany the calculation procedure for the prediction of radionuclide release from final repositories is not defined by national standards, the used procedures are based on analogue methods from other radiation protection calculations.

  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. A method for determining weights for excess relative risk and excess absolute risk when applied in the calculation of lifetime risk of cancer from radiation exposure

    Energy Technology Data Exchange (ETDEWEB)

    Walsh, Linda [Federal Office for Radiation Protection, Department of Radiation Protection and Health, Oberschleissheim (Germany); University of Manchester, The Faculty of Medical and Human Sciences, Manchester (United Kingdom); Schneider, Uwe [University of Zurich, Vetsuisse Faculty, Zurich (Switzerland); Radiotherapy Hirslanden AG, Aarau (Switzerland)

    2013-03-15

    Radiation-related risks of cancer can be transported from one population to another population at risk, for the purpose of calculating lifetime risks from radiation exposure. Transfer via excess relative risks (ERR) or excess absolute risks (EAR) or a mixture of both (i.e., from the life span study (LSS) of Japanese atomic bomb survivors) has been done in the past based on qualitative weighting. Consequently, the values of the weights applied and the method of application of the weights (i.e., as additive or geometric weighted means) have varied both between reports produced at different times by the same regulatory body and also between reports produced at similar times by different regulatory bodies. Since the gender and age patterns are often markedly different between EAR and ERR models, it is useful to have an evidence-based method for determining the relative goodness of fit of such models to the data. This paper identifies a method, using Akaike model weights, which could aid expert judgment and be applied to help to achieve consistency of approach and quantitative evidence-based results in future health risk assessments. The results of applying this method to recent LSS cancer incidence models are that the relative EAR weighting by cancer solid cancer site, on a scale of 0-1, is zero for breast and colon, 0.02 for all solid, 0.03 for lung, 0.08 for liver, 0.15 for thyroid, 0.18 for bladder and 0.93 for stomach. The EAR weighting for female breast cancer increases from 0 to 0.3, if a generally observed change in the trend between female age-specific breast cancer incidence rates and attained age, associated with menopause, is accounted for in the EAR model. Application of this method to preferred models from a study of multi-model inference from many models fitted to the LSS leukemia mortality data, results in an EAR weighting of 0. From these results it can be seen that lifetime risk transfer is most highly weighted by EAR only for stomach cancer. However

  18. 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

  19. 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

  20. 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.

  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. Evaluation of the external radiation exposure dosimetry and calculation of maximum permissible concentration values for airborne materials containing 18F, 15O, 13N, 11C and 133Xe

    International Nuclear Information System (INIS)

    Piltingsrud, H.V.; Gels, G.L.

    1985-01-01

    To better understand the dose equivalent (D.E.) rates produced by airborne releases of gaseous positron-emitting radionuclides under various conditions of cloud size, a study of the external radiation exposure dosimetry of these radionuclides, as well as negatron, gamma and x-ray emitting 133Xe, was undertaken. This included a calculation of the contributions to D.E. as a function of cloud radii, at tissue depths of 0.07 mm (skin), 3 mm (lens of eye) and 10 mm (whole body) from both the particulate and photon radiations emitted by these radionuclides. Estimates of maximum permissible concentration (MPC) values were also calculated based on the calculated D.E. rates and current regulations for personnel radiation protection (CFR84). Three continuous air monitors, designed for use with 133Xe, were evaluated for applications in monitoring air concentrations of the selected positron emitters. The results indicate that for a given radionuclide and for a cloud greater than a certain radius, personnel radiation dosimeters must respond acceptably to only the photon radiations emitted by the radionuclide to provide acceptable personnel dosimetry. For clouds under that radius, personnel radiation dosimeters must also respond acceptably to the positron or negatron radiations to provide acceptable personnel dosimetry. It was found that two out of the three air concentration monitors may be useful for monitoring air concentrations of the selected positron emitters

  3. 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 ...

  4. 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 ...

  5. 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

  6. 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 (

  7. 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.

  8. Animal mortality resulting from uniform exposures to photon radiations: Calculated LD/sub 50/s and a compilation of experimental data

    Energy Technology Data Exchange (ETDEWEB)

    Jones, T.D.; Morris, M.D.; Wells, S.M.; Young, R.W.

    1986-12-01

    Studies conducted during the 1950s and 1960s of radiation-induced mortality to diverse animal species under various exposure protocols were compiled into a mortality data base. Some 24 variables were extracted and recomputed from each of the published studies, which were collected from a variety of available sources, primarily journal articles. Two features of this compilation effort are (1) an attempt to give an estimate of the uniform dose received by the bone marrow in each treatment so that interspecies differences due to body size were minimized and (2) a recomputation of the LD/sub 50/ where sufficient experimental data are available. Exposure rates varied in magnitude from about 10/sup -2/ to 10/sup 3/ R/min. This report describes the data base, the sources of data, and the data-handling techniques; presents a bibliography of studies compiled; and tabulates data from each study. 103 refs., 44 tabs.

  9. 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

  10. 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

  11. Ionizing radiation calculations and comparisons with LDEF data

    Science.gov (United States)

    Armstrong, T. W.; Colborn, B. L.; Watts, J. W., Jr.

    1992-01-01

    In conjunction with the analysis of LDEF ionizing radiation dosimetry data, a calculational program is in progress to aid in data interpretation and to assess the accuracy of current radiation models for future mission applications. To estimate the ionizing radiation environment at the LDEF dosimeter locations, scoping calculations for a simplified (one dimensional) LDEF mass model were made of the primary and secondary radiations produced as a function of shielding thickness due to trapped proton, galactic proton, and atmospheric (neutron and proton cosmic ray albedo) exposures. Preliminary comparisons of predictions with LDEF induced radioactivity and dose measurements were made to test a recently developed model of trapped proton anisotropy.

  12. 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.)

  13. 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.)

  14. 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.)

  15. Calculating Risk: Radiation and Chernobyl.

    Science.gov (United States)

    Gale, Robert Peter

    1987-01-01

    Considers who is at risk in a disaster such as Chernobyl. Assesses the difficulty in translating information regarding radiation to the public and in determining the acceptability of technological risks. (NKA)

  16. Radiation protection calculations for diagnostic medical equipment

    International Nuclear Information System (INIS)

    Klueter, R.

    1992-01-01

    The standards DIN 6812 and DIN 6844 define the radiation protection requirements to be met by biomedical radiography equipment or systems for nuclear medicine. The paper explains the use of a specific computer program for radiation protection calculations. The program offers menu-controlled calculation, with free choice of the relevant nuclides. (DG) [de

  17. 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.

  18. Calculation codes in radiation protection, radiation physics and dosimetry

    International Nuclear Information System (INIS)

    2003-01-01

    These scientific days had for objective to draw up the situation of calculation codes of radiation transport, of sources estimation, of radiation doses managements and to draw the future perspectives. (N.C.)

  19. 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.

  20. The treatment of exposure for VNEM calculations

    International Nuclear Information System (INIS)

    Beere, William

    2004-01-01

    The VNEM approach to solving multi assembly neutron calculations has been shown to accurately reproduce pin power distributions [1]. However, this high accuracy is only possible when the contents of a node are accurately known. This is generally the case for fresh fuel, but once fuel has been exposed its composition changes. Often these changes are described by only a few parameters per node, such as exposure and spectral history. This ignores any tilt or boundary effects for the node. This can have significant effect on the accuracy of any neutron calculation. So if accurate neutron flux and power distributions are required it is also necessary to accurately describe the effects of exposure in a reactor situation. Thus, it is desired to study possible methods to generate VNEM coefficients for a node in a reactor situation. In this report we will suggest a possible method for modelling exposure and spectral history effects. Other effects as void fraction or boron concentration will not be considered here. Special attention has been placed on the ability to accommodate differences in power and spectral spatial distributions. The spatial distributions of exposure and spectral history are modelled as a set of expansion functions based on a set of given functions and the results of infinite lattice calculations. This method is shown to be adequate in reproducing multi assembly cross section distributions. Thus, further testing is required to check its ability to generate VNEM coefficients and ultimately flux distributions for multi assembly calculations. (Author)

  1. 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.

  2. 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

  3. 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)

  4. 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

  5. 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

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. Radiation shielding calculation using MCNP

    International Nuclear Information System (INIS)

    Masukawa, Fumihiro

    2001-01-01

    To verify the Monte Carlo code MCNP4A as a tool to generate the reference data in the shielding designs and the safety evaluations, various shielding benchmark experiments were analyzed using this code. These experiments were categorized in three types of the shielding subjects; bulk shielding, streaming, and skyshine. For the variance reduction technique, which is indispensable to get meaningful results with the Monte Carlo shielding calculation, we mainly used the weight window, the energy dependent Russian roulette and spitting. As a whole, our analyses performed enough small statistical errors and showed good agreements with these experiments. (author)

  11. 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

  12. 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.

  13. 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

  14. 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.)

  15. 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

  16. 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

  17. Variation in calculated human exposure. Comparison of calculations with seven European human exposure models

    NARCIS (Netherlands)

    Swartjes F; ECO

    2003-01-01

    Twenty scenarios, differing with respect to land use, soil type and contaminant, formed the basis for calculating human exposure from soil contaminants with the use of models contributed by seven European countries (one model per country). Here, the human exposures to children and children

  18. 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

  19. 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

  20. 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.

  1. 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.

  2. 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

  3. 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

  4. 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.

  5. Assessment of chemical exposures: calculation methods for environmental professionals

    National Research Council Canada - National Science Library

    Daugherty, Jack E

    1997-01-01

    ... on by scientists, businessmen, and policymakers. Assessment of Chemical Exposures: Calculation Methods for Environmental Professionals addresses the expanding scope of exposure assessments in both the workplace and environment...

  6. 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

  7. A Methodology for Calculating Radiation Signatures

    Energy Technology Data Exchange (ETDEWEB)

    Klasky, Marc Louis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wilcox, Trevor [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bathke, Charles G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); James, Michael R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-05-01

    A rigorous formalism is presented for calculating radiation signatures from both Special Nuclear Material (SNM) as well as radiological sources. The use of MCNP6 in conjunction with CINDER/ORIGEN is described to allow for the determination of both neutron and photon leakages from objects of interest. In addition, a description of the use of MCNP6 to properly model the background neutron and photon sources is also presented. Examinations of the physics issues encountered in the modeling are investigated so as to allow for guidance in the user discerning the relevant physics to incorporate into general radiation signature calculations. Furthermore, examples are provided to assist in delineating the pertinent physics that must be accounted for. Finally, examples of detector modeling utilizing MCNP are provided along with a discussion on the generation of Receiver Operating Curves, which are the suggested means by which to determine detectability radiation signatures emanating from objects.

  8. Radiation-damage calculations with NJOY

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Muir, D.W.; Mann, F.W.

    1983-01-01

    Atomic displacement, gas production, transmutation, and nuclear heating can all be calculated with the NJOY nuclear data processing system using evaluated data in ENDF/B format. Using NJOY helps assure consistency between damage cross sections and those used for transport, and NJOY provides convenient interface formats for linking data to application codes. Unique features of the damage calculation include a simple momentum balance treatment for radiative capture and a new model for (n, particle) reactions based on statistical model calculations. Sample results for iron and nickel are given and compared with the results of other methods

  9. 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)

  10. 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)

  11. 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.

  12. Spontaneous Radiation Background Calculation for LCLS

    CERN Document Server

    Reiche, Sven

    2004-01-01

    The intensity of undulator radiation, not amplified by the FEL interaction, can be larger than the maximum FEL signal in the case of an X-ray FEL. In the commissioning of a SASE FEL it is essential to extract an amplified signal early to diagnose eventual misalignment of undulator modules or errors in the undulator field strength. We developed a numerical code to calculate the radiation pattern at any position behind a multi-segmented undulator with arbitrary spacing and field profiles. The output can be run through numerical spatial and frequency filters to model the radiation beam transport and diagnostic. In this presentation we estimate the expected background signal for the FEL diagnostic and at what point along the undulator the FEL signal can be separated from the background. We also discusses how much information on the undulator field and alignment can be obtained from the incoherent radiation signal itself.

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. PABLM: a computer program to calculate accumulated radiation doses from radionuclides in the environment

    International Nuclear Information System (INIS)

    Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1980-03-01

    A computer program, PABLM, was written to facilitate the calculation of internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. This report contains details of mathematical models used and calculational procedures required to run the computer program. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides in the environment after the releases have ended. Radioactive decay is considered during the release of radionuclides, after they are deposited on the plants or ground, and during holdup of food after harvest. The radiation dose models consider several exposure pathways. Doses may be calculated for either a maximum-exposed individual or for a population group. The doses calculated are accumulated doses from continuous chronic exposure. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and MPC's of each radionuclide. The radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption that the contaminated medium is large enough to be considered an infinite volume or plane relative to the range of the emitted radiations. The equations for calculations of the radiation dose from external exposure to shoreline sediments include a correction for the finite width of the contaminated beach

  1. 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)

  2. 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)

  3. Calculating gamma dose factors for hot particle exposures

    International Nuclear Information System (INIS)

    Murphy, P.

    1990-01-01

    For hot particle exposures to the skin, the beta component of radiation delivers the majority of the dose. However, in order to fully demonstrate regulatory compliance, licenses must ordinarily provide reasonable bases for assuming that both the gamma component of the skin dose and the whole body doses are negligible. While beta dose factors are commonly available in the literature, gamma dose factors are not. This paper describes in detail a method by which gamma skin dose factors may be calculated using the Specific Gamma-ray Constant, even if the particle is not located directly on the skin. Two common hot particle exposure geometries are considered: first, a single square centimeter of skin lying at density thickness of 7 mg/cm 2 and then at 1000 mg/cm 2 . A table provides example gamma dose factors for a number of isotopes encountered at power reactors

  4. 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)

  5. An improved algorithm for calculating cloud radiation

    International Nuclear Information System (INIS)

    Yuan Guibin; Sun Xiaogang; Dai Jingmin

    2005-01-01

    Clouds radiation characteristic is very important in cloud scene simulation, weather forecasting, pattern recognition, and other fields. In order to detect missiles against cloud backgrounds, to enhance the fidelity of simulation, it is critical to understand a cloud's thermal radiation model. Firstly, the definition of cloud layer infrared emittance is given. Secondly, the discrimination conditions of judging a pixel of focal plane on a satellite in daytime or night time are shown and equations are given. Radiance such as reflected solar radiance, solar scattering, diffuse solar radiance, solar and thermal sky shine, solar and thermal path radiance, cloud blackbody and background radiance are taken into account. Thirdly, the computing methods of background radiance for daytime and night time are given. Through simulations and comparison, this algorithm is proved to be an effective calculating algorithm for cloud radiation

  6. 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.

  7. 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.

  8. 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.

  9. 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

  10. Radiation transport calculation methods in BNCT

    International Nuclear Information System (INIS)

    Koivunoro, H.; Seppaelae, T.; Savolainen, S.

    2000-01-01

    Boron neutron capture therapy (BNCT) is used as a radiotherapy for malignant brain tumours. Radiation dose distribution is necessary to determine individually for each patient. Radiation transport and dose distribution calculations in BNCT are more complicated than in conventional radiotherapy. Total dose in BNCT consists of several different dose components. The most important dose component for tumour control is therapeutic boron dose D B . The other dose components are gamma dose D g , incident fast neutron dose D f ast n and nitrogen dose D N . Total dose is a weighted sum of the dose components. Calculation of neutron and photon flux is a complex problem and requires numerical methods, i.e. deterministic or stochastic simulation methods. Deterministic methods are based on the numerical solution of Boltzmann transport equation. Such are discrete ordinates (SN) and spherical harmonics (PN) methods. The stochastic simulation method for calculation of radiation transport is known as Monte Carlo method. In the deterministic methods the spatial geometry is partitioned into mesh elements. In SN method angular integrals of the transport equation are replaced with weighted sums over a set of discrete angular directions. Flux is calculated iteratively for all these mesh elements and for each discrete direction. Discrete ordinates transport codes used in the dosimetric calculations are ANISN, DORT and TORT. In PN method a Legendre expansion for angular flux is used instead of discrete direction fluxes, land the angular dependency comes a property of vector function space itself. Thus, only spatial iterations are required for resulting equations. A novel radiation transport code based on PN method and tree-multigrid technique (TMG) has been developed at VTT (Technical Research Centre of Finland). Monte Carlo method solves the radiation transport by randomly selecting neutrons and photons from a prespecified boundary source and following the histories of selected particles

  11. 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.)

  12. 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).

  13. 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)

  14. 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

  15. Calculation of radiation dose received in computed tomography examinations

    International Nuclear Information System (INIS)

    Abed Elseed, Eslam Mustafa

    2014-07-01

    Diagnostic computed tomography (CT) examinations play an important role in the health care of the population. These examination may involve significant irradiation of the patient and probably represent the largest man-made source of radiation exposure for the population. This study was performed to assess the effective dose (ED) received in brain CT examination ( base of skull and cerebrum) and to analyze effective dose distributions among radiological departments under study. The study was performed at Elnileen Medical Center, coverage one CT unit and a sample of 51 patients (25 cerebrum sample and 26 base of skull sample). The following parameters were recorded age, weight, height body mass index (BMI) derived from weight (kg) and height ( m) and exposure factor and CTDI voi , DLP value. The effective dose was measured for brain CT examination. The ED values were calculated from the obtained DLP values using AAPM report No 96 calculation methods. The results of ED values calculated showed that patient exposure were within the normal range of exposure. The mean ED values calculated were 0.35±0.15 for base of skull of brain CT examinations and 0.70±0.32 for cerebrum of brain CT examination, respectively. Further studies are recommended with more number of pa.(Author)

  16. 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.

  17. Radiative forcing calculations for CH3Cl

    International Nuclear Information System (INIS)

    Grossman, A.S.; Grant, K.E.; Wuebbles, D.J.

    1994-06-01

    Methyl chloride, CH 3 Cl, is the major natural source of chlorine to the stratosphere. The production of CH 3 Cl is dominated by biological sources from the oceans and biomass burning. Production has a seasonal cycle which couples with the short lifetime of tropospheric CH 3 Cl to produce nonuniform global mixing. As an absorber of infrared radiation, CH 3 Cl is of interest for its potential affect on the tropospheric energy balance as well as for its chemical interactions. In this study, we estimate the radiative forcing and global warming potential (GWP) of CH 3 Cl. Our calculations use an infrared radiative transfer model based on the correlated k-distribution algorithm for band absorption. Global and annual average vertical profiles of temperature and trace gas concentration were assumed. The effects of clouds are modeled using three layers of global and annual average cloud optical properties. A radiative forcing value of 0.0053 W/m 2 ppbv was obtained for CH 3 Cl and is approximately linear in the background abundance. This value is about 2 percent of the forcing of CFC-11 and about 300 times the forcing of CO 2 , on a per molecule basis. The radiative forcing calculation for CH 3 Cl is used to estimate the global warming potential (GWP) of CH 3 Cl. The results give GWPs for CH 3 Cl of the order of 25 at a time of 20 years(CO 2 = 1). This result indicates that CH 3 Cl has the potential to be a major greenhouse gas if significant human related emissions were introduced into the atmosphere

  18. 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)

  19. Agriculture-related radiation dose calculations

    International Nuclear Information System (INIS)

    Furr, J.M.; Mayberry, J.J.; Waite, D.A.

    1987-10-01

    Estimates of radiation dose to the public must be made at each stage in the identification and qualification process leading to siting a high-level nuclear waste repository. Specifically considering the ingestion pathway, this paper examines questions of reliability and adequacy of dose calculations in relation to five stages of data availability (geologic province, region, area, location, and mass balance) and three methods of calculation (population, population/food production, and food production driven). Calculations were done using the model PABLM with data for the Permian and Palo Duro Basins and the Deaf Smith County area. Extra effort expended in gathering agricultural data at succeeding environmental characterization levels does not appear justified, since dose estimates do not differ greatly; that effort would be better spent determining usage of food types that contribute most to the total dose; and that consumption rate and the air dispersion factor are critical to assessment of radiation dose via the ingestion pathway. 17 refs., 9 figs., 32 tabs

  20. Monte Carlo calculations of channeling radiation

    International Nuclear Information System (INIS)

    Bloom, S.D.; Berman, B.L.; Hamilton, D.C.; Alguard, M.J.; Barrett, J.H.; Datz, S.; Pantell, R.H.; Swent, R.H.

    1981-01-01

    Results of classical Monte Carlo calculations are presented for the radiation produced by ultra-relativistic positrons incident in a direction parallel to the (110) plane of Si in the energy range 30 to 100 MeV. The results all show the characteristic CR(channeling radiation) peak in the energy range 20 keV to 100 keV. Plots of the centroid energies, widths, and total yields of the CR peaks as a function of energy show the power law dependences of γ 1 5 , γ 1 7 , and γ 2 5 respectively. Except for the centroid energies and power-law dependence is only approximate. Agreement with experimental data is good for the centroid energies and only rough for the widths. Adequate experimental data for verifying the yield dependence on γ does not yet exist

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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

  6. 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.

  7. 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

  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. 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

  10. 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

  11. Astronaut exposure to space radiation - Space Shuttle experience

    International Nuclear Information System (INIS)

    Atwell, W.

    1990-01-01

    Space Shuttle astronauts are exposed to both the trapped radiation and the galactic cosmic radiation environments. In addition, the sun periodically emits high-energy particles which could pose a serious threat to flight crews. NASA adheres to federal regulations and recommended exposure limits for radiation protection and has established a radiological health and risk assessment program. Using models of the space radiation environment, a Shuttle shielding model, and an anatomical human model, crew exposure estimates are made for each Shuttle flight. The various models are reviewed. Dosimeters are worn by each astronaut and are flown at several fixed locations to obtain inflight measurements. The dosimetry complement is discussed in detail. A comparison between the premission calculations and measurements is presented. Extrapolation of Shuttle experience to long-duration exposure is explored. 14 refs

  12. 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 ...

  13. 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

  14. 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)

  15. Correlation between natural radiation exposure and cancer mortality, (4)

    International Nuclear Information System (INIS)

    Noguchi, Kunikazu; Shimizu, Masami; Sairenji, Eiko; Anzai, Ikuro.

    1987-01-01

    In the previous studies, using Pearson's product moment correlation coefficient, we found that in most cases of cancers, statistically significant positive correlations were observed between natural background radiation exposure rate and crude cancer mortality rate over the period 1950 - 1978. Furthermore, we found that the statistical significance of correlation between natural background radiation exposure rate and the age-adjusted cancer mortality rate in the same period mostly disappeared. We studied the cause of this apparent correlation and found that the prefecture with a higher natural background radiation exposure rate had a greater component ratio of older people. In Japan, a number of prefectures with a higher natural background exposure rate are located in relatively thinly populated districts which have been experiencing an outflow of the younger generation to more highly industrialized and urbanized areas. Therefore, statistically significant positive correlations were observed for almost all cancers between natural background radiation exposure rate and crude cancer mortality rate. In the present investigation, we statistically tested the frequency distributions of natural background radiation exposure rate and age-adjusted cancer mortality rate, and calculated Spearman's rank correlation coefficient between natural background radiation exposure rate and the age-adjusted cancer mortality rate. The frequency distribution of the natural background radiation exposure rate and that of the age-adjusted mortality rate appeared normal in most cases of cancer, and the statistical significance of correlation between natural background exposure rate and the age-adjusted cancer mortality rate did not differ much on the whole, even though we used Spearman's rank correlation coefficient between them. (author)

  16. Correlation between natural radiation exposure and cancer mortality, (4)

    Energy Technology Data Exchange (ETDEWEB)

    Noguchi, Kunikazu; Shimizu, Masami; Sairenji, Eiko; Anzai, Ikuro

    1987-03-01

    In the previous studies, using Pearson's product moment correlation coefficient, we found that in most cases of cancers, statistically significant positive correlations were observed between natural background radiation exposure rate and crude cancer mortality rate over the period 1950 - 1978. Furthermore, we found that the statistical significance of correlation between natural background radiation exposure rate and the age-adjusted cancer mortality rate in the same period mostly disappeared. We studied the cause of this apparent correlation and found that the prefecture with a higher natural background radiation exposure rate had a greater component ratio of older people. In Japan, a number of prefectures with a higher natural background exposure rate are located in relatively thinly populated districts which have been experiencing an outflow of the younger generation to more highly industrialized and urbanized areas. Therefore, statistically significant positive correlations were observed for almost all cancers between natural background radiation exposure rate and crude cancer mortality rate. In the present investigation, we statistically tested the frequency distributions of natural background radiation exposure rate and age-adjusted cancer mortality rate, and calculated Spearman's rank correlation coefficient between natural background radiation exposure rate and the age-adjusted cancer mortality rate. The frequency distribution of the natural background radiation exposure rate and that of the age-adjusted mortality rate appeared normal in most cases of cancer, and the statistical significance of correlation between natural background exposure rate and the age-adjusted cancer mortality rate did not differ much on the whole, even though we used Spearman's rank correlation coefficient between them.

  17. Radiation shielding calculations for the vista spacecraft

    International Nuclear Information System (INIS)

    Sahin, Suemer; Sahin, Haci Mehmet; Acir, Adem

    2005-01-01

    The VISTA spacecraft design concept has been proposed for manned or heavy cargo deep space missions beyond earth orbit with inertial fusion energy propulsion. Rocket propulsion is provided by fusion power deposited in the inertial confined fuel pellet debris and with the help of a magnetic nozzle. The calculations for the radiation shielding have been revised under the fact that the highest jet efficiency of the vehicle could be attained only if the propelling plasma would have a narrow temperature distribution. The shield mass could be reduced from 600 tons in the original design to 62 tons. Natural and enriched lithium were the principle shielding materials. The allowable nuclear heating in the superconducting magnet coils (up to 5 mW/cm 3 ) is taken as the crucial criterion for dimensioning the radiation shielding structure of the spacecraft. The space craft mass is 6000 tons. Total peak nuclear power density in the coils is calculated as ∼5.0 mW/cm 3 for a fusion power output of 17 500 MW. The peak neutron heating density is ∼2.0 mW/cm 3 , and the peak γ-ray heating density is ∼3.0 mW/cm 3 (on different points) using natural lithium in the shielding. However, the volume averaged heat generation in the coils is much lower, namely 0.21, 0.71 and 0.92 mW/cm 3 for the neutron, γ-ray and total nuclear heating, respectively. The coil heating will be slightly lower if highly enriched 6 Li (90%) is used instead of natural lithium. Peak values are then calculated as 2.05, 2.15 and 4.2 mW/cm 3 for the neutron, γ-ray and total nuclear heating, respectively. The corresponding volume averaged heat generation in the coils became 0.19, 0.58 and 0.77 mW/cm 3

  18. 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.)

  19. 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.

  20. CONDOS methodology for evaluation of radiation exposure from consumer products

    International Nuclear Information System (INIS)

    O'Donnell, F.R.

    1979-01-01

    The CONDOS methodology is a tool for estimating radiation doses to man from exposures to radionuclides incorporated in consumer products. It consists of two parts: (1) an outline, checklist, and selected data for modeling the life span of a product or the material from which it is made; and (2) a computer code that uses the life-span model to calculate radiation doses to exposed individuals and population groups

  1. Critical evaluation of German regulatory specifications for calculating radiological exposure

    Energy Technology Data Exchange (ETDEWEB)

    Koenig, Claudia; Walther, Clemens [Hannover Univ. (Germany). Inst. of Radioecology; Smeddinck, Ulrich [Technische Univ. Braunschweig (Germany). Inst. of Law

    2015-07-01

    The assessment of radiological exposure of the public is an issue at the interface between scientific findings, juridical standard setting and political decision. The present work revisits the German regulatory specifications for calculating radiological exposure, like the already existing calculation model General Administrative Provision (AVV) for planning and monitoring nuclear facilities. We address the calculation models for the recent risk assessment regarding the final disposal of radioactive waste in Germany. To do so, a two-pronged approach is pursued. One part deals with radiological examinations of the groundwater-soil-transfer path of radionuclides into the biosphere. Processes at the so-called geosphere-biosphere-interface are examined, especially migration of I-129 in the unsaturated zone. This is necessary, since the German General Administrative Provision does not consider radionuclide transport via groundwater from an underground disposal facility yet. Especially data with regard to processes in the vadose zone are scarce. Therefore, using I-125 as a tracer, immobilization and mobilization of iodine is investigated in two reference soils from the German Federal Environment Agency. The second part of this study examines how scientific findings but also measures and activities of stakeholders and concerned parties influence juridical standard setting, which is necessary for risk management. Risk assessment, which is a scientific task, includes identification and investigation of relevant sources of radiation, possible pathways to humans, and maximum extent and duration of exposure based on dose-response functions. Risk characterization identifies probability and severity of health effects. These findings have to be communicated to authorities, who have to deal with the risk management. Risk management includes, for instance, taking into account acceptability of the risk, actions to reduce, mitigate, substitute or monitor the hazard, the setting of

  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. 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

  6. 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)

  7. 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)

  8. 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

  9. 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.

  10. 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)

  11. 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)

  12. 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)

  13. General fundamentals of calculation for determining the radiation exposure due to radioactive discharge into surface waters. I. Flowing waters. Allgemeine Berechnungsgrundlagen fuer die Bestimmung der Strahlenexposition durch radioaktive Einleitungen in Oberflaechengewaesser. T. 1. Fliessgewaesser

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The paper describes a mathematical model for estimating the internal radiation exposure via different exposure pathways through radioactive discharges from nuclear facilities (paragraph 45, rad. prot. law) into rivers. The connections between the compartments of an ecological system are shown in their main types. Not all exposure pathways described are relevant for all cases; the experts have to carry out the evaluation using their knowledge of the local circumstances. The model is only valid for running waters above the tidal limit with the plant operating according to the rules.

  14. 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)

  15. 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.

  16. Radiative forcing calculations for CH3Br

    International Nuclear Information System (INIS)

    Grossman, A.S.; Blass, W.E.; Wuebbles, D.J.

    1995-06-01

    Methyl Bromide, CH 3 Br, is the major organobromine species in the lower atmosphere and is a primary source of bromine in the stratosphere. It has a lifetime of 1.3 years. The IR methyl bromide spectra in the atmospheric window region, 7--13μ, was determined using a well tested Coriolis resonance and ell-doubling (and ell-resonance) computational system. A radiative forcing value of 0.00493 W/m 2 /ppbv was obtained for CH 3 Br and is approximately linear in the background abundance. This value is about 2 percent of the forcing of CFC-11 and about 278 times the forcing of C0 2 , on a per molecule basis. The radiative forcing calculation is used to estimate the global warming potential (GWP) of CH 3 Br. The results give GWPs for CH 3 Br of the order of 13 for an integration period of 20 years and 4 for an integration period of 100 years (assuming C0 2 = 1, following IPCC [1994]). While CH 3 Br has a GWP which is approximately 25 percent of the GWP of CH 4 , the current emission rates are too low to cause serious atmospheric greenhouse heating effects at this time

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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.)

  4. 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.

  5. 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

  6. 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

  7. PABLM: a computer program to calculate accumulated radiation doses from radionuclides in the environment

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.; Kennedy, W.E. Jr.; Soldat, J.K.

    1980-03-01

    A computer program, PABLM, was written to facilitate the calculation of internal radiation doses to man from radionuclides in food products and external radiation doses from radionuclides in the environment. This report contains details of mathematical models used and calculational procedures required to run the computer program. Radiation doses from radionuclides in the environment may be calculated from deposition on the soil or plants during an atmospheric or liquid release, or from exposure to residual radionuclides in the environment after the releases have ended. Radioactive decay is considered during the release of radionuclides, after they are deposited on the plants or ground, and during holdup of food after harvest. The radiation dose models consider several exposure pathways. Doses may be calculated for either a maximum-exposed individual or for a population group. The doses calculated are accumulated doses from continuous chronic exposure. A first-year committed dose is calculated as well as an integrated dose for a selected number of years. The equations for calculating internal radiation doses are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and MPC's of each radionuclide. The radiation doses from external exposure to contaminated water and soil are calculated using the basic assumption that the contaminated medium is large enough to be considered an infinite volume or plane relative to the range of the emitted radiations. The equations for calculations of the radiation dose from external exposure to shoreline sediments include a correction for the finite width of the contaminated beach.

  8. Cumulative radiation exposure in children with cystic fibrosis.

    LENUS (Irish Health Repository)

    O'Reilly, R

    2010-02-01

    This retrospective study calculated the cumulative radiation dose for children with cystic fibrosis (CF) attending a tertiary CF centre. Information on 77 children with a mean age of 9.5 years, a follow up time of 658 person years and 1757 studies including 1485 chest radiographs, 215 abdominal radiographs and 57 computed tomography (CT) scans, of which 51 were thoracic CT scans, were analysed. The average cumulative radiation dose was 6.2 (0.04-25) mSv per CF patient. Cumulative radiation dose increased with increasing age and number of CT scans and was greater in children who presented with meconium ileus. No correlation was identified between cumulative radiation dose and either lung function or patient microbiology cultures. Radiation carries a risk of malignancy and children are particularly susceptible. Every effort must be made to avoid unnecessary radiation exposure in these patients whose life expectancy is increasing.

  9. 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

  10. 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)

  11. 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

  12. Influence of materials choice on occupational radiation exposure in ITER

    International Nuclear Information System (INIS)

    Forty, C.B.A.; Firth, J.D.; Butterworth, G.J.

    1998-01-01

    In fission reactor plant, the radiation doses associated with inspection and maintenance of the primary cooling circuit account for a substantial fraction of the collective occupational radiation exposure (ORE). Similarly, it is anticipated that much of the ORE occurring during normal operation of ITER will arise from active deposits in the cooling loop. Using a number of calculation steps ranging from neutron activation analysis, mobilisation and transport modelling and Monte Carlo simulation, estimates for the gamma photon flux and radiation dose fields around a typical 'hot-leg' cooling pipe have been made taking SS316, OPTSTAB, MANET-II and F-82H steels as alternative candidate loop materials. (orig.)

  13. 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

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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)

  3. 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)

  4. 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

  5. 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).

  6. 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)

  7. Measuring and modeling exposure from environmental radiation on tidal flats

    International Nuclear Information System (INIS)

    Gould, T.J.; Hess, C.T.

    2005-01-01

    To examine the shielding effects of the tide cycle, a high pressure ion chamber was used to measure the exposure rate from environmental radiation on tidal flats. A theoretical model is derived to predict the behavior of exposure rate as a function of time for a detector placed one meter above ground on a tidal flat. The numerical integration involved in this derivation results in an empirical formula which implies exposure rate ∝tan-1(sint). We propose that calculating the total exposure incurred on a tidal flat requires measurements of only the slope of the tidal flat and the exposure rate when no shielding occurs. Experimental results are consistent with the model

  8. 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.

  9. 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.

  10. 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.

  11. [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

  12. 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)

  13. 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)

  14. 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

  15. 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

  16. 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)

  17. 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

  18. 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.

  19. 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.

  20. 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)

  1. Calculation codes in radiation protection, radiation physics and dosimetry; Codes de calcul en radioprotection, radiophysique et dosimetrie

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    These scientific days had for objective to draw up the situation of calculation codes of radiation transport, of sources estimation, of radiation doses managements and to draw the future perspectives. (N.C.)

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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)

  10. 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)

  11. 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

  12. 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.

  13. 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

  14. Assessment of natural radiation exposure inside a newly constructed building

    International Nuclear Information System (INIS)

    Shukla, V.K.; Sadasivan, S.; Nambi, K.S.V.; Sundaram, V.K.

    1994-01-01

    Naturally occurring radionuclides in building materials are one of the sources of radiation exposure to the population. Several building materials used for a newly constructed building complex were analysed for 40 K, 238 U radioactivity by gamma ray spectrometry. The external gamma dose inside the complex was evaluated by using the computer code QAD-CGGP. External dose rate was also measured by using scintillation gamma monitor. Calculated and the measured dose rate values are discussed. (author). 11 refs., 2 figs., 2 tabs

  15. Radiation exposures to technologists from nuclear medicine imaging procedures

    International Nuclear Information System (INIS)

    Sloboda, R.S.; Schmid, M.G.; Willis, C.P.

    1986-05-01

    Radiation exposures incurred by nuclear medicine technologists during diagnostic imaging and gamma camera quality control (QC) were measured on a procedural basis over a three-month period using a portable, low-range, self-reading ion chamber. A total of more than 400 measurements were made for 15 selected procedures. From these, mean procedural exposures and standard deviations were calculated. The results show that daily flood phantom QC, at 0.58 mR, and gated cardiac studies, at 0.45 mR, were the two greatest sources of exposure. Other procedures resulted in exposures varying roughly from 0.10 to 0.20 mR. Difficult patients were responsible for a doubling of technologist exposure for many procedures. Standard deviations were large for all procedures, averaging 65% of the mean values. Comparison of technologist exposure inferred from the procedural measurements with the time coincident collective dose equivalent recorded by the TLD service of the Radiation Protection Bureau indicates that approximately half of the collective technologist exposure arose from patient handling and flood QC

  16. 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...

  17. 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

  18. Some technologically enhanced exposures to natural radiation environment in India

    International Nuclear Information System (INIS)

    Lalit, B.Y.; Shukla, V.K.; Ramachandran, T.V.; Mishra, U.C.

    1982-01-01

    A summary of results of gamma spectrometric measurements of natural radioactivity in a number of coal and flyash samples from thermal power plants and phosphatic fertilizer samples collected from various fertilizer plants in India are presented. These constitute the sources of technologically enhanced exposures to natural radiation. A brief description of sampling and measurement procedures is given. The radiation doses to the population from coal burning for electricity generation have been calculated using the method outlined in UNSCEAR report of 1979 with corrections for local population density. The external radiation dose to the farmers has been calculated on the basis of usage of phosphatic fertilizers for rice, wheat, millets and sugarcane crops for the normal agricultural practices

  19. Radiation exposure from nuclear medicine studies in children

    International Nuclear Information System (INIS)

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

    1994-01-01

    Nuclear medical examinations of children have to be performed with special regard to the problems of radiation protection because of the high radiation sensitivity esp. of infants and young children. The present contribution describes how any unnecessary radiation exposure can be avoided by the correct choice and planning of a nuclear medical study, by using the appropriate radiopharmaceutical as well as by the exact calculation of the amount of activity applied, depending on body surface resp. body weight of the child. A technically optimized method which employs the best technical equipment and personnel, being specially trained for working with children, are important conditions to achieve optimal results of nuclear medical tests. Due to the difficulties of direct dose measurements, large variations in the biokinetic behaviour of radiopharmaceuticals and the restriction to standard phantoms, individual dose calculations or dose estimations in pediatrics cause great problems. This is reflected by often large variations of dosimetrical data given in the literature. (orig.) [de

  20. Radiation damage calculations for compound materials

    International Nuclear Information System (INIS)

    Greenwood, L.R.

    1990-01-01

    This paper reports on the SPECOMP computer code, developed to calculate neutron-induced displacement damage cross sections for compound materials such as alloys, insulators, and ceramic tritium breeders for fusion reactors. These new calculations rely on recoil atom energy distributions previously computed with the DISCS computer code, the results of which are stored in SPECTER computer code master libraries. All reaction channels were considered in the DISCS calculations and the neutron cross sections were taken from ENDF/B-V. Compound damage calculations with SPECOMP thus do not need to perform any recoil atom calculations and consequently need no access to ENDF or other neutron data bases. The calculations proceed by determining secondary displacements for each combination of recoil atom and matrix atom using the Lindhard partition of the recoil energy to establish the damage energy

  1. 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)

  2. 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.)

  3. 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)

  4. 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

  5. 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

  6. 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

  7. 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.)

  8. Kinetic neoclassical calculations of impurity radiation profiles

    Directory of Open Access Journals (Sweden)

    D.P. Stotler

    2017-08-01

    Full Text Available Modifications of the drift-kinetic transport code XGC0 to include the transport, ionization, and recombination of individual charge states, as well as the associated radiation, are described. The code is first applied to a simulation of an NSTX H-mode discharge with carbon impurity to demonstrate the approach to coronal equilibrium. The effects of neoclassical phenomena on the radiated power profile are examined sequentially through the activation of individual physics modules in the code. Orbit squeezing and the neoclassical inward pinch result in increased radiation for temperatures above a few hundred eV and changes to the ratios of charge state emissions at a given electron temperature. Analogous simulations with a neon impurity yield qualitatively similar results.

  9. Radiation exposure on flights; Strahlenexposition beim Fliegen. Ein Fall fuer den Strahlenschutz

    Energy Technology Data Exchange (ETDEWEB)

    Blettner, Maria [Mainz Univ. (Germany). Inst. fuer Medizinische Biometrie, Epidemiologie und Informatik (IMBEI); Boehm, Theresia; Eberbach, Frieder [Vereinigung Cockpit e.V. Main Airport Center (MAC), Frankfurt (Germany). AG Strahlenschutz; Bottollier-Depois, Jean-Francois [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France); Clairand, Isabelle; Huet, Christelle [Institut de Radioprotection et de Surete Nucleaire (IRSN), Fontenay-aux-Roses (France). Ionizing Radiation Dosimetry Lab.; Frasch, Gerhard [Bundesamt fuer Strahlenschutz, Oberschleissheim/Neuherberg (Germany). Beruflicher Strahlenschutz und Strahlenschutzregister; Hammer, Ga el P. [Laboratoire National de Sante E.P., Dudelange (Luxembourg). Registre Morphologique des Tumeurs; Mares, Vladimir; Ruehm, Werner [Helmholtz Zentrum Muenchen Deutsches Forschungszentrum fuer Gesundheit und Umwelt GmbH, Neuherberg (Germany); Voelkle, Hansruedi [Fribourg Univ. (Switzerland). Physikdept.

    2014-09-01

    Extend and effects of radiation doses occuring during flights are treated under various aspects. Part of them are, in the first line, radiation exposure of the flying staff and the results of epidemiologic studies regarding the health consequences, as well as aspects of practical radiation protection for the flying staff. Computer programs for dose calculation on flights round off the theme. (orig.)

  10. 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

  11. Computer code for calculating personnel doses due to tritium exposures

    International Nuclear Information System (INIS)

    Graham, C.L.; Parlagreco, J.R.

    1977-01-01

    This report describes a computer code written in LLL modified Fortran IV that can be used on a CDC 7600 for calculating personnel doses due to internal exposures to tritium. The code is capable of handling various exposure situations and is also capable of detecting a large variety of data input errors that would lead to errors in the dose assessment. The critical organ is the body water

  12. 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.)

  13. 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

  14. Radiative flux calculations at UV and visible wavelengths

    International Nuclear Information System (INIS)

    Grossman, A.S.; Grant, K.E.; Wuebbles, D.J.

    1993-10-01

    A radiative transfer model to calculate the short wavelength fluxes at altitudes between 0 and 80 km has been developed at LLNL. The wavelength range extends from 175--735 nm. This spectral range covers the UV-B wavelength region, 250--350 nm, with sufficient resolution to allow comparison of UV-B measurements with theoretical predictions. Validation studies for the model have been made for both UV-B ground radiation calculations and tropospheric solar radiative forcing calculations for various ozone distributions. These studies indicate that the model produces results which agree well with respect to existing UV calculations from other published models

  15. 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 ...

  16. 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.

  17. MODELING ACUTE EXPOSURE TO SOLAR RADIATION

    Science.gov (United States)

    One of the major technical challenges in calculating solar flux on the human form has been the complexity of the surface geometry (i.e., the surface normal vis a vis the incident radiation). The American Cancer Society reports that over 80% of skin cancers occur on the face, he...

  18. Calculation of gamma ray exposure rates from uranium ore bodies

    International Nuclear Information System (INIS)

    Thomson, J.E.; Wilson, O.J.

    1980-02-01

    The planning of operations associated with uranium mines often requires that estimates be made of the exposure rates from various ore bodies. A straight-forward method of calculating the exposure rate from an arbitrarily shaped body is presented. Parameters for the calculation are evaluated under the assumption of secular equilibrium of uranium with its daughters and that the uranium is uniformly distributed throughout an average soil mixture. The spectral distribution of the emitted gamma rays and the effect of air attenuation are discussed. Worked examples are given of typical situations encountered in uranium mines

  19. 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)

  20. LDRD Final Review: Radiation Transport Calculations

    Energy Technology Data Exchange (ETDEWEB)

    Goorley, John Timothy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Morgan, George Lake [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lestone, John Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-06-22

    Both high-fidelity & toy simulations are being used to understand measured signals and improve the Area 11 NDSE diagnostic. We continue to gain more and more confidence in the ability for MCNP to simulate neutron and photon transport from source to radiation detector.

  1. 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

  2. Numerical investigations of radiation exposure in civil aviation

    International Nuclear Information System (INIS)

    Beck, P.; Felsberger, E.; O'Brien, K.; Kindl, P.

    1998-01-01

    Previous in-flight measurements of radiation exposure to air crews is compared with calculations by cosmic ray transport codes. Primary cosmic ray particle spectra modifications by solar modulation and by the geomagnetic field are discussed. The cosmic ray propagation and behaviour in the atmosphere is described by the Boltzmann equation. Results of calculations are shown in graphical form, including the altitude dependence of the effective dose rate at various geomagnetic latitudes, the effect of the 11-year solar modulation cycle, and 3 world maps of effective dose rates at usual flight altitudes. (A.K.)

  3. Radiation damage calculations for compound materials

    International Nuclear Information System (INIS)

    Greenwood, L.R.

    1989-01-01

    Displacement damage calculations can be performed for 40 elements in the energy range up to 20 MeV with the SPECTER computer code. A recent addition to the code, called SPECOMP, can intermix atomic recoil energy distributions for any four elements to calculate the proper displacement damage for compound materials. The calculations take advantage of the atomic recoil data in the SPECTER libraries, which were determined by the DISCS computer code, using evaluated neutron cross section and angular distribution data in ENDF/B-V. Resultant damage cross sections for any compound can be added to the SPECTER libraries for the routine calculation of displacements in any given neutron field. Users do not require access to neutron cross section files. Results are presented for a variety of fusion materials and a new ceramic superconductor material. Future plans and nuclear data needs are discussed. 11 refs., 6 figs., 1 tab

  4. 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

  5. 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)

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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)

  13. 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

  14. 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

  15. Statistics of Monte Carlo methods used in radiation transport calculation

    International Nuclear Information System (INIS)

    Datta, D.

    2009-01-01

    Radiation transport calculation can be carried out by using either deterministic or statistical methods. Radiation transport calculation based on statistical methods is basic theme of the Monte Carlo methods. The aim of this lecture is to describe the fundamental statistics required to build the foundations of Monte Carlo technique for radiation transport calculation. Lecture note is organized in the following way. Section (1) will describe the introduction of Basic Monte Carlo and its classification towards the respective field. Section (2) will describe the random sampling methods, a key component of Monte Carlo radiation transport calculation, Section (3) will provide the statistical uncertainty of Monte Carlo estimates, Section (4) will describe in brief the importance of variance reduction techniques while sampling particles such as photon, or neutron in the process of radiation transport

  16. Medical application of radionuclides and the resulting radiation exposure of parts of the population

    International Nuclear Information System (INIS)

    Keller, K.D.; Gloebel, B.; Andres, C.

    1985-01-01

    In a big hospital an investigation was made to find out to what extent the radionuclides used there contribute to the radiation exposure of the population living in the vicinity. The hospital used about 100 Ci of short-lived radionuclides a year. By applying the calculation basis stipulated by the Federal Ministry of the Interior, the radiation exposure was calculated for unfavourable cases. As a result, up to 30 mrem/a can theoretically be reached. (orig.) [de

  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 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

  19. 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)

  20. Variables influencing radiation exposure during extracorporeal shock wave lithotripsy. Review of 298 treatments

    International Nuclear Information System (INIS)

    Carter, H.B.; Naeslund, E.B.R.; Riehle, R.A. Jr.

    1987-01-01

    Retrospective review of 298 extracorporeal shock wave lithotripsy (ESWL) treatments was undertaken to determine the factors which influence radiation exposure during ESWL. Fluoroscopy time averaged 160 seconds (3-509), and the average number of spot films taken per patient was 26 (5-68). The average stone burden was 19.3 mm (3-64). Average calculated skin surface radiation exposure was 17.8 R per treatment. Radiation exposure increased with increasing stone burden and patient weight. Stones treated in the ureter resulted in a higher average patient radiation exposure than for renal stones (19 R vs 16 R), even though the average size of these ureteral stones (11.3 mm) was significantly less than the mean. However, type of anesthetic (general or regional) used was not a significant factor. Operator training, experience, and familiarity with radiation physics should significantly decrease the amount of imaging time and consequent patient radiation exposure during ESWL

  1. Variables influencing radiation exposure during extracorporeal shock wave lithotripsy. Review of 298 treatments

    Energy Technology Data Exchange (ETDEWEB)

    Carter, H.B.; Naeslund, E.B.R.; Riehle, R.A. Jr.

    1987-12-01

    Retrospective review of 298 extracorporeal shock wave lithotripsy (ESWL) treatments was undertaken to determine the factors which influence radiation exposure during ESWL. Fluoroscopy time averaged 160 seconds (3-509), and the average number of spot films taken per patient was 26 (5-68). The average stone burden was 19.3 mm (3-64). Average calculated skin surface radiation exposure was 17.8 R per treatment. Radiation exposure increased with increasing stone burden and patient weight. Stones treated in the ureter resulted in a higher average patient radiation exposure than for renal stones (19 R vs 16 R), even though the average size of these ureteral stones (11.3 mm) was significantly less than the mean. However, type of anesthetic (general or regional) used was not a significant factor. Operator training, experience, and familiarity with radiation physics should significantly decrease the amount of imaging time and consequent patient radiation exposure during ESWL.

  2. Radiation exposure and risk assessment for critical female body organs

    International Nuclear Information System (INIS)

    Atwell, W.; Weyland, M.D.; Hardy, A.C.

    1991-07-01

    Space radiation exposure limits for astronauts are based on recommendations of the National Council on Radiation Protection and Measurements. These limits now include the age at exposure and sex of the astronaut. A recently-developed computerized anatomical female (CAF) model is discussed in detail. Computer-generated, cross-sectional data are presented to illustrate the completeness of the CAF model. By applying ray-tracing techniques, shield distribution functions have been computed to calculate absorbed dose and dose equivalent values for a variety of critical body organs (e.g., breasts, lungs, thyroid gland, etc.) and mission scenarios. Specific risk assessments, i.e., cancer induction and mortality, are reviewed. 13 refs

  3. 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.)

  4. External exposure from gamma radiation in uranium mines

    International Nuclear Information System (INIS)

    Thomson, J.E.

    1982-01-01

    Radiation doses received by workers in a high ore grade uranium mine are compared to those of other radiation workers and the need to be able to calculate the exposure rate from an ore body is indicated. The uranium-238 decay chain is presented and particular reference is made to the main gamma emitters and secular equilibrium of the members of the chain. Difficulties in dealing with a self attenuating volume source, in which scattering is important, are pointed out and traditional methods of solution are mentioned. It is shown that in the special case of an infinite ore body a simple solution may be obtained using the energy conservation principle. A straightforward method for calculating the exposure rate from an arbitrarily shaped ore body is given and corrections due to air attenuation, different soil types and possible lack of secular equilibrium are dealt with. The gamma ray spectrum from the ore is discussed with specific reference to the selection of suitable exposure monitors and the calculation of transmission through shields

  5. Assessment of genetic risk for human exposure to radiation

    International Nuclear Information System (INIS)

    Sevcenko, V.A.; Rubanovic, A.V.

    2002-01-01

    Full text: The methodology of assessing the genetic risk of radiation exposure is based on the concept of 'hitting the target' in development of which N.V. Timofeeff-Ressovsky has played and important role. To predict genetic risk posed by irradiation, the U N Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has worked out direct and indirect methods of assessment, extrapolation, integral and palpitation criteria of risk analysis that together permit calculating the risk from human exposure on the basis of data obtained for mice. Based on the reports of UNSCEAR for the period from 1958 to 2001 the paper presents a retrospective analysis of the use of direct methods and the doubling dose method for quantitative determination of the genetic risk of human exposure expressed as different hereditary diseases. As early as 1962 UNSCEAR estimated the doubling dose (a dose causing as many mutations as those occurring spontaneously during one generation) at 1 Gy for cases of exposure to ionizing radiations with low LET at a low dose rate and this value was confirmed in the next UNSCEAR reports up to now. For cases of acute irradiation the doubling dose was estimated at 0,3-0,4 Gy for the period under review. The paper considers the evolution of the concepts of human natural hereditary variability which is a basis for assessing the risk of exposure by the doubling dose method. The level of human natural genetic variability per 1 000 000 newborns is estimated at 738 000 hereditary diseases including mendelian, chromosomal and multifactorial ones. The greatest difficulties in assessing the doubling dose value were found to occur in the case of multifactorial diseases the pheno typical expression of which depends on mutational events in polygenic systems and on numerous environmental factors. The introduction in calculations of the potential recoverability correction factor (RPCF) made it possible to assess the genetic risk taking into account this class of

  6. 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.

  7. Exposure calculation code module for reactor core analysis: BURNER

    Energy Technology Data Exchange (ETDEWEB)

    Vondy, D.R.; Cunningham, G.W.

    1979-02-01

    The code module BURNER for nuclear reactor exposure calculations is presented. The computer requirements are shown, as are the reference data and interface data file requirements, and the programmed equations and procedure of calculation are described. The operating history of a reactor is followed over the period between solutions of the space, energy neutronics problem. The end-of-period nuclide concentrations are determined given the necessary information. A steady state, continuous fueling model is treated in addition to the usual fixed fuel model. The control options provide flexibility to select among an unusually wide variety of programmed procedures. The code also provides user option to make a number of auxiliary calculations and print such information as the local gamma source, cumulative exposure, and a fine scale power density distribution in a selected zone. The code is used locally in a system for computation which contains the VENTURE diffusion theory neutronics code and other modules.

  8. Exposure calculation code module for reactor core analysis: BURNER

    International Nuclear Information System (INIS)

    Vondy, D.R.; Cunningham, G.W.

    1979-02-01

    The code module BURNER for nuclear reactor exposure calculations is presented. The computer requirements are shown, as are the reference data and interface data file requirements, and the programmed equations and procedure of calculation are described. The operating history of a reactor is followed over the period between solutions of the space, energy neutronics problem. The end-of-period nuclide concentrations are determined given the necessary information. A steady state, continuous fueling model is treated in addition to the usual fixed fuel model. The control options provide flexibility to select among an unusually wide variety of programmed procedures. The code also provides user option to make a number of auxiliary calculations and print such information as the local gamma source, cumulative exposure, and a fine scale power density distribution in a selected zone. The code is used locally in a system for computation which contains the VENTURE diffusion theory neutronics code and other modules

  9. 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

  10. 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

  11. 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)

  12. Radiation Exposure Monitoring and Information Transmittal (REMIT) system

    International Nuclear Information System (INIS)

    Cale, R.; Clark, T.; Dixson, R.; Hagemeyer, D.

    1993-06-01

    The Radiation Exposure Monitoring and Information Transmittal (REMIT) system is designed to assist US Nuclear Regulatory Commission (NRC)licensees in meeting the reporting requirements of the revised 10 CFR 20 and in agreement with the guidance contained in R.G. 8.7, Rev. 1, ''Instructions for Recording and Reporting Occupational Exposure Data.'' REMIT is a personal computer (PC) based menu driven system that facilitates the manipulation of data base files to record and report radiation exposure information. REMIT is designed to be user-friendly and contains the full text of R. G. 8.7, Rev. 1, on-line as well as context-sensitive help throughout the program. The user can enter data directly from NRC Forms 4 or 5, REMIT allows the user to view the individual's exposure in relation to regulatory or administrative limits and alerts the user to exposures in excess of these limits. The system also provides for the calculation and summation of dose from intakes and the determination of the dose to the maximally exposed extremity for the monitoring year. REMIT can produce NRC Forms 4 and 5 in paper and electronic format and can import/export data from ASCII and data base files

  13. Calculation of dose-rate conversion factors for external exposure to photons and electrons

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1978-01-01

    Methods are presented for the calculation of dose-rate conversion factors for external exposure to photon and electron radiation from radioactive decay. A dose-rate conversion factor is defined as the dose-equivalent rate per unit radionuclide concentration. Exposure modes considered are immersion in contaminated air, immersion in contaminated water, and irradiation from a contaminated ground surface. For each radiation type and exposure mode, dose-rate conversion factors are derived for tissue-equivalent material at the body surface of an exposed individual. In addition, photon dose-rate conversion factors are estimated for 22 body organs. The calculations are based on the assumption that the exposure medium is infinite in extent and that the radionuclide concentration is uniform. The dose-rate conversion factors for immersion in contaminated air and water then follow from the requirement that all of the energy emitted in the radioactive decay is absorbed in the infinite medium. Dose-rate conversion factors for ground-surface exposure are calculated at a reference location above a smooth, infinite plane using the point-kernel integration method and known specific absorbed fractions for photons and electrons in air

  14. 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

  15. 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.

  16. 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.

  17. 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)

  18. 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

  19. Methods for calculating radiation attenuation in shields

    Energy Technology Data Exchange (ETDEWEB)

    Butler, J; Bueneman, D; Etemad, A; Lafore, P; Moncassoli, A M; Penkuhn, H; Shindo, M; Stoces, B

    1964-10-01

    In recent years the development of high-speed digital computers of large capacity has revolutionized the field of reactor shield design. For compact special-purpose reactor shields, Monte-Carlo codes in two- and three dimensional geometries are now available for the proper treatment of both the neutron and gamma- ray problems. Furthermore, techniques are being developed for the theoretical optimization of minimum-weight shield configurations for this type of reactor system. In the design of land-based power reactors, on the other hand, there is a strong incentive to reduce the capital cost of the plant, and economic considerations are also relevant to reactors designed for merchant ship propulsion. In this context simple methods are needed which are economic in their data input and computing time requirements and which, at the same time, are sufficiently accurate for design work. In general the computing time required for Monte-Carlo calculations in complex geometry is excessive for routine design calculations and the capacity of the present codes is inadequate for the proper treatment of large reactor shield systems in three dimensions. In these circumstances a wide range of simpler techniques are currently being employed for design calculations. The methods of calculation for neutrons in reactor shields fall naturally into four categories: Multigroup diffusion theory; Multigroup diffusion with removal sources; Transport codes; and Monte Carlo methods. In spite of the numerous Monte- Carlo techniques which are available for penetration and back scattering, serious problems are still encountered in practice with the scattering of gamma rays from walls of buildings which contain critical facilities and also concrete-lined discharge shafts containing irradiated fuel elements. The considerable volume of data in the unclassified literature on the solution of problems of this type in civil defence work appears not to have been evaluated for reactor shield design. In

  20. 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)

  1. Bivariational calculations for radiation transfer in an inhomogeneous participating media

    International Nuclear Information System (INIS)

    El Wakil, S.A.; Machali, H.M.; Haggag, M.H.; Attia, M.T.

    1986-07-01

    Equations for radiation transfer are obtained for dispersive media with space dependent albedo. Bivariational bound principle is used to calculate the reflection and transmission coefficients for such media. Numerical results are given and compared. (author)

  2. Diagnosis, injury and prevention of internal radiation exposure

    International Nuclear Information System (INIS)

    Tatsuzaki, Hideo

    2012-01-01

    Radiation exposure is classified into three categories: external exposure, surface contamination, and internal exposure (also called internal contamination). Internal exposure is an exposure by the ionizing radiation emitted from radioactive materials taken into a human body. Uptake of radioactive materials can go through inhalation, ingestion, or wound contamination. Not like external exposure, alpha ray or beta ray, which has a limited penetration, is also important in internal exposure. Diagnosis of internal exposure is based on measurement and dose assessment in addition to the history taking. Two methods, direct measurement and/or bioassay (indirect measurement), are used for the measurement. These measurements provide information of radioactive materials in the body at the time of the measurement. The exposure dose to the body needs to be calculated in a process of dose assessment, based on the results of these measurements and history of intake, either acute intake or chronic intake. Another method, measurement of environmental samples or food stuff, is also used for dose assessment. For internal exposure, radiation dose to the body is expressed as committed effective dose or committed equivalent dose, which are accumulation of dose over a defined period. Radioactive materials taken into body are transferred among many body components depending on the type of radionuclide or chemicals etc. Some radioactive materials concentrate in a specific organ. Symptoms and signs depend on the distribution of the radioactive materials in the body. Monitoring the concentration in air or foods is conducted in order to control human activities and foods and consequently reduce the amount of intake to human bodies as a preventive measure. Prevention of internal exposure is also conducted by protective gears such as full face masks. Iodine prophylaxis could be used against radioactive iodine intake. Stable iodine, mostly potassium iodide, could be taken into the thyroid and

  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. Radiation exposure inside reinforced concrete buildings at Nagasaki

    International Nuclear Information System (INIS)

    Rhoades, W.A.; Childs, R.L.; Ingersoll, D.T.

    1989-05-01

    The biological effects on the residents of Hiroshima and Nagasaki due to initial-irradiation exposure during the nuclear attacks of World War II was recognized immediately as an important source of information. After the war, an extensive effort gathered data concerning the locations of individuals at the time of the attack and their subsequent medical histories. The data from personnel located in reinforced concrete buildings are particularly significant, since large groups of occupants received radiation injury without complications due to blast and thermal effects. In order to correlate the radiation dose with physiological effects, the dose to each individual must be calculated. Enough information about the construction of the buildings was available after the war to allow a radiation transport model to be constructed, but the accurate calculation of penetration into such large, thick-walled three dimensional structures was beyond the scope of computing technology until recently. Now, the availability of Cray vector computers and the development of a specially-constructed discrete ordinates transport code, TORT, have combined to allow the successful completion of such a study. This document describes the radiation transport calculations and tabulates the resulting doses by source component and individual case location. An extensive uncertainty analysis is also included. These data are to be used in another study as input to a formal statistical analysis, resulting in a new value for the LD50 dose, i.e., the dose at which the mortality risk is 50%. 55 refs., 67 figs., 70 tabs

  5. Comparison and application study on cosmic radiation dose calculation received by air crew

    International Nuclear Information System (INIS)

    Zhou Qiang; Xu Cuihua; Ren Tianshan; Li Wenhong; Zhang Jing; Lu Xu

    2009-01-01

    Objective: To facilitate evaluation on Cosmic radiation dose received by flight crew by developing a convenient and effective measuring method. Methods: In comparison with several commonly used evaluating methods, this research employs CARI-6 software issued by FAA (Federal Aviation Administration) to measure Cosmic radiation dose for flight crew members exposed to. Results: Compared with other methods, CARI-6 is capable of providing reliable calculating results on radiation dose and applicable to all flight crew of different airlines. Conclusion: Cosmic radiation received by flight crew is on the list of occupational radiation. For a smooth running of Standards for controlling exposure to cosmic radiation of air crew, CARI software may be a widely applied tool in radiation close estimation of for flight crew. (authors)

  6. Health effects and radiation dose from exposure to radon indoors

    International Nuclear Information System (INIS)

    Swedjemark, G.A.

    1998-01-01

    Radon exposure has been declared a health hazard by several organisations, for example the International Commission on Radiological Protection (ICRP) and the World Health Organisation (WHO). The basis for the risk estimate has been the results from epidemiological studies on miners exposed to radon, supported by the results of residential epidemiology. Only few of the many residential epidemiological studies carried out hitherto have a design applicable for a risk estimate. The largest is the Swedish national study but several large well designed studies are ongoing. An excess risk has also been found in animal research. The model describes smoking and radon exposure as between additive and multiplicative, found in both miners and residential studies. The relatively few non-smokers among the miners and also among the residents give a problem at estimating the radon risk for these groups. It would also be desirable to know more about the importance of the age and the time period at exposure. Lung dose calculations from radon exposure are not recommended by ICRP in their publication 66. For comparison with other radiation sources the ICRP recommends the concept 'dose conversion convention' obtained as the risk estimate divided by the detriment. Other effects of radon exposure than lung cancer have not been shown epidemiologically, but dose calculations indicate an excess risk of about 5% of the excess lung cancer risk. (author)

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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.)

  14. 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

  15. 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

  16. Comparison of the performance of net radiation calculation models

    DEFF Research Database (Denmark)

    Kjærsgaard, Jeppe Hvelplund; Cuenca, R.H.; Martinez-Cob, A.

    2009-01-01

    . The long-wave radiation models included a physically based model, an empirical model from the literature, and a new empirical model. Both empirical models used only solar radiation as required for meteorological input. The long-wave radiation models were used with model calibration coefficients from......Daily values of net radiation are used in many applications of crop-growth modeling and agricultural water management. Measurements of net radiation are not part of the routine measurement program at many weather stations and are commonly estimated based on other meteorological parameters. Daily...... values of net radiation were calculated using three net outgoing long-wave radiation models and compared to measured values. Four meteorological datasets representing two climate regimes, a sub-humid, high-latitude environment and a semi-arid mid-latitude environment, were used to test the models...

  17. Effects of occupational exposure to ionizing radiation on reproductive and child health

    International Nuclear Information System (INIS)

    Bienefeld, M.K.; McLaughlin, J.R.

    1998-01-01

    The evidence regarding the effects of occupational exposure to low levels of ionizing radiation on reproductive health is limited. However, exposure to high doses of ionizing radiation is associated with increased risk of adverse reproductive outcomes. The resulting uncertainty about the effects of occupational exposures has caused concern among some workers, therefore, we have designed a study to examine this question among Canadian medical radiation technologists. A short mailed questionnaire will be sent to all CAMRT members to obtain information about reproductive history, and a sample of respondents will receive a second questionnaire requesting information about other important exposures. Occupational dose records will be retrieved from the National Dose Registry. Using this information, relative risks for each outcome will be calculated for different radiation dose levels. This article provides a brief review of the literature on ionizing radiation exposure and reproductive outcomes, and an outline of the proposed study

  18. Radiation exposure with 3D rotational angiography of the skull

    International Nuclear Information System (INIS)

    Gosch, D.; Deckert, F.; Schulz, T.; Kahn, T.; Kurze, W.; Patz, A.

    2006-01-01

    Purpose: determination and comparison of radiation exposure for examinations of the skull with unsubtracted 3D rotational angiography (3D RA) and 2D digital subtraction angiography (2D DSA). Materials and methods: measurements were carried out with a skull of an Alderson phantom for 3D RA and for 2D DSA in p.a. and lateral projections using an Innova 4100 angiography system with a digital flat panel detector from GE Healthcare. 45 thermoluminescent dosimeters TLD 100H from Harshaw were placed inside the phantom to measure organ doses. In addition the dose area product was recorded and the effective dose was calculated using the Monte Carlo program PCXMC. Results: for a biplanar DSA run (lateral and p.a. projection), the organ doses were 4 to 5 times higher and the effective dose was 4 times higher than for a 3D RA even though the number of images for the two DSA runs was only half of that for 3D RA. Conclusion: the radiation exposure for unsubtracted 3D RA using a flat panel detector is significantly lower than for biplanar DSA. Using 3D RA in place of 2D DSA can reduce the radiation exposure of patients in neuroradiology procedures. (orig.)

  19. Calculation of dietary exposure to acrylamide in the Norwegian population

    OpenAIRE

    Norwegian Scientific Committee for Food Safety

    2015-01-01

    The Norwegian Scientific Committee for Food Safety (VKM) is requested by the Norwegian Food Safety Authority (NFSA) to calculate the dietary exposure to acrylamide in the Norwegian population. NFSA refers to the recent scientific opinion on acrylamide in food by the European Food Safety Authority (EFSA). EFSA concludes that acrylamide in food potentially increases the risk of developing cancer for consumers in all age groups.

  20. 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

  1. Radiation by the numbers: developing an on-line Canadian radiation dose calculator as a public engagement and education tool

    Energy Technology Data Exchange (ETDEWEB)

    Dalzell, M.T.J. [Sylvia Fedoruk Canadian Centre for Nuclear Innovation, Saskatoon, Saskatchewan (Canada)

    2016-06-15

    Concerns arising from misunderstandings about radiation are often cited as a main reason for public antipathy towards nuclear development and impede decision-making by governments and individuals. A lack of information about everyday sources of radiation exposure that is accessible, relatable and factual contributes to the problem. As part of its efforts to be a fact-based source of information on nuclear issues, the Sylvia Fedoruk Canadian Centre for Nuclear Innovation has developed an on-line Canadian Radiation Dose Calculator as a tool to provide context about common sources of radiation. This paper discusses the development of the calculator and describes how the Fedoruk Centre is using it and other tools to support public engagement on nuclear topics. (author)

  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. 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)

  4. 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...

  5. 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.

  6. 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

  7. 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)

  8. Measurement and Calculation of Gamma Radiation from HWZPR Reactor

    International Nuclear Information System (INIS)

    Jalali, Majid

    2006-01-01

    HWZPR is a research reactor with natural uranium fuel, D 2 O moderator and graphite reflector with maximum power of 100 W. It is a suitable means for theoretical research and heavy water reactor experiments. Neutrons from the core participate in different nuclear reactions by interactions with fuel, moderator, graphite and the concrete around the reactor. The results of these interactions are the production of prompt gammas in the environment. Useful information is gained by the reactor gamma spectrum measurement from point of view of relative quantity and energy distribution of direct and scattered radiations. Reactor gamma ray spectrum has been gathered in different places around the reactor by HPGe detector. In analysis of these spectra, 1 H(n,γ) 2 H, 16 O(n,n'γ) 16 O, 2 H(n,γ) 3 H and 238 U(n,γ) 239 U reactions occurring in reactor moderator and fuel, are important. The measured spectrum has been primarily estimated by the MCNP code. There is agreement between the code and the experiments in some points. The scattered gamma rays from 27 Al (n,γ) 28 Al reaction in the reactor tank, are the most among the gammas scattered in the reactor environment. Also the dose calculations by MCNP code show that 72% of gamma dose belongs to the energy range 3-11 MeV from reactor gamma spectrum and the danger of exposure from the reactor high-energy photons is serious. (author)

  9. An Accurate Technique for Calculation of Radiation From Printed Reflectarrays

    DEFF Research Database (Denmark)

    Zhou, Min; Sorensen, Stig B.; Jorgensen, Erik

    2011-01-01

    The accuracy of various techniques for calculating the radiation from printed reflectarrays is examined, and an improved technique based on the equivalent currents approach is proposed. The equivalent currents are found from a continuous plane wave spectrum calculated by use of the spectral dyadic...... Green's function. This ensures a correct relation between the equivalent electric and magnetic currents and thus allows an accurate calculation of the radiation over the entire far-field sphere. A comparison to DTU-ESA Facility measurements of a reference offset reflectarray designed and manufactured...

  10. Ocular ultraviolet radiation exposure of welders.

    Science.gov (United States)

    Tenkate, Thomas D

    2017-05-01

    I read with interest a recent paper in your journal by Slagor et al on the risk of cataract in relation to metal arc welding (1). The authors highlight that even though welders are exposed to substantial levels of ultraviolet radiation (UVR), "no studies have reported data on how much UVR welders' eyes are exposed to during a working day. Thus, we do not know whether welders are more or less exposed to UVR than outdoor workers" (1, p451). Undertaking accurate exposure assessment of UVR from welding arcs is difficult, however, two studies have reported ocular/facial UVR levels underneath welding helmets (2, 3). In the first paper, UVR levels were measured using polysulphone film dosimeters applied to the cheeks of a patient who suffered from severe facial dermatitis (2). UVR levels of four times the American Conference of Governmental Industrial Hygienists (ACGIH) maximum permissible exposure (MPE) (4) were measured on the workers left cheek and nine times the MPE on the right cheek. The authors concluded that the workers dermatitis was likely to have been due to the UVR exposure received during welding. In the other paper, a comprehensive exposure assessment of personal UVR exposure of workers in a welding environment was reported (3). The study was conducted at a metal fabrication workshop with participants being welders, boilermakers and non-welders (eg, supervisors, fitters, machinists). Polysulphone film dosimeters were again used to measure UVR exposure of the workers, with badges worn on the clothing of workers (in the chest area), on the exterior of welding helmets, attached to 11 locations on the inside of welding helmets, and on the bridge and side-shields of safety spectacles. Dosimeters were also attached to surfaces throughout the workshop to measure ambient UVR levels. For welding subjects, mean 8-hour UVR doses within the welding helmets ranged from around 9 mJ/cm 2 (3×MPE) on the inside of the helmets to around 15 mJ/cm 2 (5×MPE) on the headband (a

  11. 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

  12. 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.)

  13. 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.)

  14. 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)

  15. 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)

  16. Design And Measurement Of Radiation Exposure Rates At An X-Ray Diagnostic Radiological Unit

    International Nuclear Information System (INIS)

    Tito-Sutjipto

    2003-01-01

    Every radiation employees suffers radiation exposure risk while doing his job. It is important therefore to investigate the occupational health and safety of radiation employees on its relationship with the design and measurement of radiation exposure rates at an X-ray diagnostic radiological unit in this work, a case study was held on the radiological unit at BP-4 Yogyakarta for patient diagnostics, This research armed to investigate the relationship between the design of radiological unit for X-ray diagnostics and the location of the X-ray machine, based on the distance variable and radiation exposure rate during patient diagnostics. This was performed using radiological unit design data for X-ray diagnostics and the measurement of radiation exposure rates throughout patient diagnostics. The design data can then be used for determining the requirement of primary and secondary shielding materials for radiological unit as well as a calculation basis of radiation exposure rates during patient diagnostics. From the result of the research, it can be concluded that from the occupational health and safety point of view, radiation exposure around the X-ray machines are fairly good, both for the shielding materials in each X-ray room and the radiation exposures received by the workers, because they are far beyond the maximum permittable average limit (16.67 m R/days). (author)

  17. 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

  18. Planning of optimal work path for minimizing exposure dose during radiation work in radwaste storage

    International Nuclear Information System (INIS)

    Kim, Yoon Hyuk; Park, Won Man; Kim, Kyung Soo; Whang, Joo Ho

    2005-01-01

    Since the safety of nuclear power plant has been becoming a big social issue, the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate dose not depend on the location within a work space, thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation during radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, the developed numerical method and simulation program could be useful tools in the planning of radiation work

  19. 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

  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. 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.

  2. 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...

  3. 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.

  4. 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

  5. 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)

  6. Prediction of LDEF exposure to the ionizing radiation environment

    Science.gov (United States)

    Watts, J. W.; Armstrong, T. W.; Colborn, B. L.

    1996-01-01

    Predictions of the LDEF mission's trapped proton and electron and galactic cosmic ray proton exposures have been made using the currently accepted models with improved resolution near mission end and better modeling of solar cycle effects. An extension of previous calculations, to provide a more definitive description of the LDEF exposure to ionizing radiation, is represented by trapped proton and electron flux as a function of mission time, presented considering altitude and solar activity variation during the mission and the change in galactic cosmic ray proton flux over the mission. Modifications of the AP8MAX and AP8MIN fluence led to a reduction of fluence by 20%. A modified interpolation model developed by Daly and Evans resulted in 30% higher dose and activation levels, which better agreed with measured values than results predicted using the Vette model.

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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.)

  12. Calculating the diffuse solar radiation in regions without solar radiation measurements

    International Nuclear Information System (INIS)

    Li, Huashan; Bu, Xianbiao; Long, Zhen; Zhao, Liang; Ma, Weibin

    2012-01-01

    Correlations for calculating diffuse solar radiation can be classified into models with global solar radiation (H-based method) and without it (Non-H method). The objective of the present study is to compare the performance of H-based and Non-H methods for calculating the diffuse solar radiation in regions without solar radiation measurements. The comparison is carried out at eight meteorological stations in China focusing on the monthly average daily diffuse solar radiation. Based on statistical error tests, the results show that the Non-H method that includes other readily available meteorological elements gives better estimates. Therefore, it can be concluded that the Non-H method is more appropriate than the H-based one for calculating the diffuse solar radiation in regions without solar radiation measurements. -- Highlights: ► Methods for calculating diffuse solar radiation in regions without solar radiation measurements are investigated. ► Diffuse solar radiation models can be classified into two groups according to global solar radiation. ► Two approaches are compared at the eight meteorological stations in China. ► The method without global solar radiation is recommended.

  13. A Monte Carlo program to calculate the exposure rate from airborne radioactive gases inside a nuclear reactor containment building.

    Science.gov (United States)

    Sherbini, S; Tamasanis, D; Sykes, J; Porter, S W

    1986-12-01

    A program was developed to calculate the exposure rate resulting from airborne gases inside a reactor containment building. The calculations were performed at the location of a wall-mounted area radiation monitor. The program uses Monte Carlo techniques and accounts for both the direct and scattered components of the radiation field at the detector. The scattered component was found to contribute about 30% of the total exposure rate at 50 keV and dropped to about 7% at 2000 keV. The results of the calculations were normalized to unit activity per unit volume of air in the containment. This allows the exposure rate readings of the area monitor to be used to estimate the airborne activity in containment in the early phases of an accident. Such estimates, coupled with containment leak rates, provide a method to obtain a release rate for use in offsite dose projection calculations.

  14. The ICRP opinion of the calculation of doses and risks associated with exposures to tritium

    International Nuclear Information System (INIS)

    Paquetla, F.; Harrison, J.

    2009-01-01

    As the management of exposures to tritium, just like for other radionuclides, relies on the effective dose calculation, it also requires the application of coefficients to take the variety of radiations and the sensitivity of the different irradiated tissues into account. The authors discuss the determination and the use of the weighting factor (Wr) which reflects the relative biological effectiveness (RBE) of different types of radiation. They outline that some researchers asked for a review of this factor, and that the RBE is related to several parameters. All this and other issues entail uncertainties. The authors then give the opinion of the ICRP on this issue and notably for the assessment of the individual risk of cancer after exposure to tritium

  15. Numerical calculation of radiation pattern of plasma channel antenna

    International Nuclear Information System (INIS)

    Xia Xinren; Yin Chengyou

    2010-01-01

    The idea of plasma channel antenna (PCA) for high power microwave weapon is presented in this paper. The radiation pattern of PCA is calculated. The directivity functions of general antenna are derived. The near electromagnetic model of PCA is created based on physical circumstances. The electromagnetic fields of PCA and surrounding air in cylindrical coordinate are given. The dispersion equation of PCA is deduced by applying the boundary conditions of electromagnetic fields. The surface wave vector of PCA is achieved. The variations of radiation characteristic with plasma density, antenna length and antenna radius are emphatically discussed. The controllability of PCA's radiation patterns is confirmed. (authors)

  16. 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.

  17. 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)

  18. Survival of human lymphocytes after exposure to densely ionizing radiations

    International Nuclear Information System (INIS)

    Madhvanath, U.; Raju, M.R.; Kelly, L.S.

    1976-01-01

    Interphase death of human blood lymphocytes cultured in vitro was studied after exposure to 60 Co gamma rays and to accelerated ions of 1 H, 4 He, 7 Li, 11 B, 12 C, 20 Ne, 40 Ar, and π - meson beam under aerobic conditions. Exposures were also conducted under hypoxic conditions with 60 Co gamma rays, 4 He, 7 Li, and 12 C ion beams. Time course of interphase death was followed for 6 days after irradiation. Percent survivals were determined by using the trypan blue exclusion method. Survival curves at 5 days postirradiation were exponential for all radiations studied. These observations indicate that the production of interphase death of lymphocytes by densely ionizing radiations follows a pattern similar to that observed with colony-forming mammalian cells. However, the reproductive capacity of the latter cells is impaired with maximum effectiveness at energy densities associated with 220 keV/μm for the beam conditions used in this investigation. The much lower energy densities required to kill a lymphocyte suggest that a sensitive structure other than DNA may be responsible for the production of lymphocyte death, perhaps the membranes. The calculated inactivation cross sections for high-LET radiations above 650 keV/μm yielded values larger than the actual cell dimensions. It appears that contributions from delta rays become appreciable in this system at these LET's

  19. 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

  20. The philosophy and assumptions underlying exposure limits for ionising radiation, inorganic lead, asbestos and noise

    International Nuclear Information System (INIS)

    Akber, R.

    1996-01-01

    Full text: A review of the literature relating to exposure to, and exposure limits for, ionising radiation, inorganic lead, asbestos and noise was undertaken. The four hazards were chosen because they were insidious and ubiquitous, were potential hazards in both occupational and environmental settings and had early and late effects depending on dose and dose rate. For all four hazards, the effect of the hazard was enhanced by other exposures such as smoking or organic solvents. In the cases of inorganic lead and noise, there were documented health effects which affected a significant percentage of the exposed populations at or below the [effective] exposure limits. This was not the case for ionising radiation and asbestos. None of the exposure limits considered exposure to multiple mutagens/carcinogens in the calculation of risk. Ionising radiation was the only one of the hazards to have a model of all likely exposures, occupational, environmental and medical, as the basis for the exposure limits. The other three considered occupational exposure in isolation from environmental exposure. Inorganic lead and noise had economic considerations underlying the exposure limits and the exposure limits for asbestos were based on the current limit of detection. All four hazards had many variables associated with exposure, including idiosyncratic factors, that made modelling the risk very complex. The scientific idea of a time weighted average based on an eight hour day, and forty hour week on which the exposure limits for lead, asbestos and noise were based was underpinned by neither empirical evidence or scientific hypothesis. The methodology of the ACGIH in the setting of limits later brought into law, may have been unduly influenced by the industries most closely affected by those limits. Measuring exposure over part of an eight hour day and extrapolating to model exposure over the longer term is not the most effective way to model exposure. The statistical techniques used

  1. 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%

  2. 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.)

  3. 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

  4. 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

  5. The influence of potential exposure to radiation protection system of accelerator installation TESLA

    International Nuclear Information System (INIS)

    Orlic, M.; Cuknic, O.

    2000-01-01

    Potential exposure of individuals at big nuclear machines like Accelerator Installation Tesla (AIT) generates direct requirements to reliability of radiation protection system. Starting from technical characteristics of AlT and international recommendation concerning potential exposure and the probability of death has been calculated. The reference risk has been specified. Comparing then we calculated the probability of the failure of the protective system. The reliability of the system has to be better (author)

  6. 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.

  7. 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)

  8. 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)

  9. Problems in radiation shielding calculations with Monte Carlo methods

    International Nuclear Information System (INIS)

    Ueki, Kohtaro

    1985-01-01

    The Monte Carlo method is a very useful tool for solving a large class of radiation transport problem. In contrast with deterministic method, geometric complexity is a much less significant problem for Monte Carlo calculations. However, the accuracy of Monte Carlo calculations is of course, limited by statistical error of the quantities to be estimated. In this report, we point out some typical problems to solve a large shielding system including radiation streaming. The Monte Carlo coupling technique was developed to settle such a shielding problem accurately. However, the variance of the Monte Carlo results using the coupling technique of which detectors were located outside the radiation streaming, was still not enough. So as to bring on more accurate results for the detectors located outside the streaming and also for a multi-legged-duct streaming problem, a practicable way of ''Prism Scattering technique'' is proposed in the study. (author)

  10. 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)

  11. 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)

  12. 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

  13. Dosimetry Methods for Human Exposure to Non-Ionising Radiation

    International Nuclear Information System (INIS)

    Poljak, D.; Sarolic, A.; Doric, V.; Peratta, C.; Peratta, A.

    2011-01-01

    The paper deals with human exposure to electromagnetic fields from extremely low frequencies (ELF) to GSM frequencies. The problem requires (1) the assessment of external field generated by electromagnetic interference (EMI) source at a given frequency (incident field dosimetry) and then (2) the assessment of corresponding fields induced inside the human body (internal field dosimetry). Several methods used in theoretical and experimental dosimetry are discussed within this work. Theoretical dosimetry models at low frequencies are based on quasistatic approaches, while analyses at higher frequencies use the full-wave models. Experimental techniques involve near and far field measurement. Human exposure to power lines, transformer substations, power line communication (PLC) systems, Radio Frequency Identification (RFID) antennas and GSM base station antenna systems is analyzed. The results o are compared to the exposure limits proposed by relevant safety guidelines. Theoretical incident dosimetry used in this paper is based on the set of Pocklington integro-differential equations for the calculation of the current distribution and subsequently radiated field from power lines. Experimental incident dosimetry techniques involve measurement techniques of fields radiated by RFID antennas and GSM base station antennas. First example set of numerical results is related to the internal dosimetry of realistic well-grounded body model exposed to vertical component of the electric field E = 10 kV/m generated by high voltage power line. The results obtained via the HNA model exceed the ICNIRP basic restrictions for public exposure (2 mA/m 2 ) in knee (8.6 mA/m 2 ) and neck (9.8 mA/m 2 ) and for occupational exposure (10 mA/m 2 ) in ankle (32 mA/m 2 ). In the case of a conceptual model of a realistic human body inside a transformer substation room touching a control panel at the potential φ0 = 400 V and with two scenarios for dry-air between worker's hand and panel, the values

  14. 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.

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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)

  1. 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

  2. Dose reconstruction in radioactively contaminated areas based on radiation transport calculations and measurements

    International Nuclear Information System (INIS)

    Hiller, Mauritius Michael

    2015-01-01

    The external radiation exposure at the former village of Metlino, Russia, was reconstructed. The Techa river in Metlino was contaminated by water from the Majak plant. The village was evacuated in 1956 and a reservoir lake created. Absorbed doses in bricks were measured and a model of the present-day and the historic Metlino was created for Monte Carlo calculations. By combining both, the air kerma at shoreline could be reconstructed to evaluate the Techa River Dosimetry System.

  3. 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)

  4. 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

  5. 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.

  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. 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

  8. 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)

  9. 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)

  10. 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

  11. Review of the radiation protection calculations for the encapsulation plant

    International Nuclear Information System (INIS)

    Ranta-aho, A.

    2008-09-01

    The radiation protection calculations of the encapsulation plant have been carried out with the MCNP5 Monte Carlo code. The focus of the study has been in the parts of the encapsulation plant where the spent fuel is handled after discharge from the transportation casks i.e. the fuel handling cell, the fuel drying station, the canister transfer corridor, the welding chamber, the weld inspection room, the canister buffer storage and the canister lift. The protection against radiation hazard has been mainly designed with thick concrete walls. Additionally, the entrances to the rooms with shielding requirements have been equipped with mazes. The present design excludes doors with shielding properties. The aim of this work was to verify and evaluate the necessary wall thicknesses and the functioning of the mazes in the current design. The calculations verified that for the most parts of the facility, the currently designed walls thicknesses provide adequate protection against radiation from the different spent fuel assembly configurations. Some corrective actions however seem necessary in order to stay clearly below desired radiation limits. For the most parts the functioning of the mazes was inadequate. In some of the cases a different design of the maze will be sufficient action but in some cases the radiation protection can only be secured by heavy doors for practical reasons. (orig.)

  12. Internal exposure by natural radiation and decontamination of swimming pool

    International Nuclear Information System (INIS)

    Seki, Hideyuki

    2012-01-01

    This explanation concerns the scientific knowledge and finding of the title subjects for general public to understand their present radiation environment, id est (i.e.), at about 1 year after the Fukushima Daiichi Power Plant Accident (FDPPA). The first described is the world history of radiation exposure, where A-bomb explosion in Hiroshima and Nagasaki, Three Mile Island Power Plant Accident and Chernobyl Accident are told about their teachings and about internal nuclides at FDPPA: the author points out the natural high abundance of K-40 in contrast to the release of I-131, and Cs-137/-134 in the accident. The second is described about the effect of radiations on human cells, where characteristics, measurements, unit and their derived radionuclides of alpha, beta and gamma rays are explained together with their biological influences. Also explained are hydroxy-radical formation by alpha and beta rays in the internal exposure, and comparison of external photons, gamma and more risky ultraviolet rays. Third, the author mentions about man's natural functions to protect radiation hazard. Presented are an easy calculation and a comparison of K-40 and Cs-137 contents (weight and Bq) in the body and in the swimming pool with reference to Chernobyl standards. Internal exposure by natural radionuclides like K-40 and others, is also calculated, which is found equivalent to 0.29 mSv/y based on about 5,630 Bq/60 kg body weight. Finally, explained are the knowledge and practice of decontamination, where various adsorbents like zeolite (molecular sieve), ion exchanger, charcoal and natural zeolites (alumino-silicate) are compared and the last agent, clay easily and economically available, is recommended for decontamination. Clay material is said to adsorb 87% of Cs-137 at as low level as 750 mg/L and the author has an experience to use it successfully for decontamination of the pool. Importantly, the radioactivity of the resultant sludge should not exceed 8,000 Bq/kg. (T.T.)

  13. Risk estimates of stochastic effects due to exposure to radiation - a stochastic harm index

    International Nuclear Information System (INIS)

    Gonen, Y.G.

    1980-01-01

    The effects of exposure to low level radiation on the survival probability and life expectancy were investigated. The 1977 vital statistics of Jewish males in Israel were used as a baseline, mainly the data on normalized survival probability and life expectation as functions of age. Assumed effects of exposure were superposed on these data and the net differences calculated. It was found that the realistic rate effects of exposure to radiation are generally less than calculated by multiplying the collective dose by the risk factor. The effects are strongly age-dependent, decreasing sharply with age at exposure. The assumed harm due to exposure can be more than offset by improvements in medical care and safety. (H.K.)

  14. Somatic and genetic radiation exposure of the patient in digital subtraction angiography (DSA)

    International Nuclear Information System (INIS)

    Neufang, K.F.R.; Ewen, K.

    1986-01-01

    The somatic and genetic radiation exposure of patients undergoing Digital Subtraction Angiography (DSA) and traditional Film Arteriography (FA) of cranial, cervical, thoracic and abdominal vascular territories are compared. The radiation doses absorbed within the critical organs - red bone marrow, lung, thyroid gland and female breast - and in the gonads were measured using an anthropomorphic Alderson phantom. A Somatic Dose Index was calculated in order to estimate the somatic radiation risk. The somatic radiation exposure depends upon the location of the critical organs with respect to the entrance site of the x-ray beam, and can be reduced by an appropriate choice of the angiographic projection. Under this condition, the radiation exposure of the patient during DSA can be lower than during FA. For renal DSA an a.p. projection, the use of an abdominal compression device and careful caudal shielding of the field are advocated. (orig.)

  15. 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

  16. Radiation exposure due to agricultural uses of phosphate fertilizers

    International Nuclear Information System (INIS)

    Khater, Ashraf E.M.; AL-Sewaidan, H.A.

    2008-01-01

    Radiological impacts of phosphate rocks mining and manufacture could be significant due to the elevated radioactivity contents of the naturally occurring radioactive materials (NORM), such as 238 U series, 232 Th series and 40 K, in some phosphate deposits. Over the last decades, the land reclamation and agriculture activities in Saudi Arabia and other countries have been widely expanded. Therefore, the usage of chemical fertilizers is increased. Selected phosphate fertilizers samples were collected and the specific activities of NORM were measured using a gamma ray spectrometer based on a hyper pure germanium detector and alpha spectrometer based on surface barrier detector. The obtained results show remarkable wide variations in the radioactivity contents of the different phosphate fertilizer samples. The mean (ranges) of specific activities for 226 Ra, 210 Po, 232 Th and 40 K, and radium equivalent activity are 75 (3-283), 25 (0.5-110), 23 (2-74), 2818 (9-6501) Bq/kg and 283 (7-589) Bq/kg, respectively. Based on dose calculations, the increment of the public radiation exposure due to the regular agricultural usage of phosphate fertilizers is negligible. Its average value 1 m above the ground is about 0.12 nGy/h where the world average value due to the NORM in soil is 51 nGy/h. Direct radiation exposures of the farmers due to phosphate fertilizers application was not considered in our study

  17. Patient radiation exposure dose evaluation of whole spine scanography due to exposure direction

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Su; Seo, Deok Nam [Dept. of Bio-convergence Engineering, Graduate School of Korea University, Seoul (Korea, Republic of); Kwon, Soon Mu [Dept. of Radiologic Technology, Daegu Health College, Daegu (Korea, Republic of); Kim, Jung Min [Dept. of Radiological Science, Korea University, Seoul (Korea, Republic of)

    2015-04-15

    Whole spine scanography (WSS) is a radiological examination that exposes the whole body of the individual being examined to x-ray radiation. WSS is often repeated during the treatment period, which results in a much greater radiation exposure than that in routine x-ray examinations. The aims of the current study were to evaluate the patient dose of WSS using computer simulation, image magnification and angulation of phantom image using different patient position. We evaluated the effective dose(ED) of 23 consecutive patients (M : F = 13:10) who underwent WSS, based on the automatic image pasting method for multiple exposure digital radiography. The Anterior-Posterior position(AP) and Posterior-Anterior position( PA) projection EDs were evaluated based on the PC based Monte Carlo simulation. We measured spine transverse process distance and angulation using DICOM measurement. For all patient, the average ED was 0.069 mSv for AP position and 0.0361 mSv for PA position. AP position calculated double exposure then PA position. For male patient, the average ED was 0.089 mSv(AP) and 0.050 mSv(PA). For female patient, the average ED was 0.0431 mSv(AP) and 0.026 mSv(PA). The transverse process of PA spine image measured 5% higher than AP but angulation of transverse process was no significant differences. In clinical practice, just by change the patient position was conformed to reduce the ED of patient. Therefore we need to redefine of protocol for digital radiography such as WSS, whole spine scanography, effective dose, patient exposure dose, exposure direction, protocol optimization.

  18. Calculating the Responses of Self-Powered Radiation Detectors.

    Science.gov (United States)

    Thornton, D. A.

    Available from UMI in association with The British Library. The aim of this research is to review and develop the theoretical understanding of the responses of Self -Powered Radiation Detectors (SPDs) in Pressurized Water Reactors (PWRs). Two very different models are considered. A simple analytic model of the responses of SPDs to neutrons and gamma radiation is presented. It is a development of the work of several previous authors and has been incorporated into a computer program (called GENSPD), the predictions of which have been compared with experimental and theoretical results reported in the literature. Generally, the comparisons show reasonable consistency; where there is poor agreement explanations have been sought and presented. Two major limitations of analytic models have been identified; neglect of current generation in insulators and over-simplified electron transport treatments. Both of these are developed in the current work. A second model based on the Explicit Representation of Radiation Sources and Transport (ERRST) is presented and evaluated for several SPDs in a PWR at beginning of life. The model incorporates simulation of the production and subsequent transport of neutrons, gamma rays and electrons, both internal and external to the detector. Neutron fluxes and fuel power ratings have been evaluated with core physics calculations. Neutron interaction rates in assembly and detector materials have been evaluated in lattice calculations employing deterministic transport and diffusion methods. The transport of the reactor gamma radiation has been calculated with Monte Carlo, adjusted diffusion and point-kernel methods. The electron flux associated with the reactor gamma field as well as the internal charge deposition effects of the transport of photons and electrons have been calculated with coupled Monte Carlo calculations of photon and electron transport. The predicted response of a SPD is evaluated as the sum of contributions from individual

  19. 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

  20. Application of γ field theory based calculation method to the monitoring of mine nuclear radiation environment

    International Nuclear Information System (INIS)

    Du Yanjun; Liu Qingcheng; Liu Hongzhang; Qin Guoxiu

    2009-01-01

    In order to find the feasibility of calculating mine radiation dose based on γ field theory, this paper calculates the γ radiation dose of a mine by means of γ field theory based calculation method. The results show that the calculated radiation dose is of small error and can be used to monitor mine environment of nuclear radiation. (authors)

  1. Study of the accuracy of radiation field calculations in media

    International Nuclear Information System (INIS)

    Bolyatko, V.V.; Vyrskij, M.Yu.; Ilyushkin, A.I.; Mashkovich, V.P.; Sakharov, V.K.; Stroganov, A.A.

    1981-01-01

    The sensitivity p of the radiation transport calculations to variations of input parameters Xsub(i) is theoretically analyzed, and the calculational errors induced by uncertainties of initial data are evaluated. Two calculational methods are considered: the direct substitution method using the ROZ-5 code and method using the linear perturbation theory. In order to calculate p(Xsub(i)) and bilinear convolutions of the conjugated transport equations the ZAKAT code has been developed. The calculations use the ZAKAT, ROZ-11 and APAMAKO-2F codes. As an example of practical use of the method proposed a shielding composition characteristic for fast reactors was analyzed. A plane monodirectional neutron beam of the BR-10 reactor falls onto a 5-layer stainless steel (1Kh18N10T)-carbon barrier. The sensitivily of the neutron dose absorbed in tissue to the cross sections of all the shielding constituents and to the source and detector representation functions has been calculated. A comparison of the calculations with experimental data proves the validity of the calculational method [ru

  2. Radiation shielding calculation for the MOX fuel fabrication plant Melox

    International Nuclear Information System (INIS)

    Lee, Y.K.; Nimal, J.C.; Chiron, M.

    1994-01-01

    Radiation shielding calculation is an important engineering work in the design of the MOX fuel fabrication plant MELOX. Due to the recycle of plutonium and uranium from UO2 spent fuel reprocessing and the large capacity of production (120t HM/yr.), the shielding design requires more attention in this LWR fuel plant. In MELOX, besides several temporary storage facilities of massive fissile material, about one thousand radioactive sources with different geometries, forms, densities, quantities and Pu concentrations, are distributed through different workshops from the PuO 2 powder reception unit to the fuel assembly packing room. These sources, with or without close shield, stay temporarily in different locations, containers and glove boxes. In order to optimize the dimensions, the material and the cost of shield as well as to limit the calculation work in a reasonable engineer-hours, a calculation scheme for shielding design of MELOX is developed. This calculation scheme has been proved to be useful in consideration of the feedback from the evolutionary design and construction. The validated shielding calculations give a predictive but reliable radiation doses information. (authors). 2 figs., 10 refs

  3. Effects of scattering anisotropy approximation in multigroup radiation shielding calculations

    International Nuclear Information System (INIS)

    Altiparmakov, D.

    1983-01-01

    Expansion of the scattering cross sections into Legendre series is the usual way of solving neutron transport problems. Because of the large space gradients of the neutron flux, the effects of that approximation become especially remarkable in the radiation shielding calculations. In this paper, a method taking into account the scattering anisotropy is presented. From the point od view of the accuracy and computing rate, the optimal approximation of the scattering anisotropy is established for the basic protective materials on the basis of simple problem calculations. (author)

  4. 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

  5. Occupational radiation exposure in upper Austrian water supplies and Spas

    International Nuclear Information System (INIS)

    Ringer, W.; Simader, M.; Bernreiter, M.; Aspek, W.; Kaineder, H.

    2006-01-01

    The Council Directive 96/29/EURATOM lays down the basic safety standards for the protection of the workers and the general public against the dangers arising from ionising radiation, including natural radiation. Based on the directive and on the corresponding Austrian legislation a comprehensive study was conducted to determine the occupational radiation exposure in Upper Austrian water supplies and spas. The study comprises 45 water supplies and 3 spas, one of them being a radon spa. Most measurements taken were to determine the radon concentration in air at different workplaces (n = 184), but also measurements of the dose rate at dehumidifiers (n = 7) and gamma spectrometric measurements of back washing water (n = 4) were conducted. To determine the maximum occupational radon exposure in a water supply measurements were carried out in all water purification buildings and in at least half o f the drinking water reservoirs of the water supply. The results were combined with the respective working times in these locations (these data having been collected by means of a questionnaire). Where the calculated exposure was greater than 1 MBq h/m then all drinking water reservoirs of the concerned water suppl y were measured for their radon concentration to ensure a reliable assessment of the exposure. The results show that the radon concentrations in the water supplies were lower as expected, being in 55% of all measurement sites below 1000 Bq/m in 91% below 5000 Bq/m and with a maximum value of 38700 Bq/m.This leads to exposures that are below 2 MBq h/m (corresponding to approx. 6 mSv/a) in 42 water supplies. However, for the remaining three water supplies maximal occupational exposures due to radon of 2.8 MBq h/m (∼ 10 mSv/a), 15 MBq h/m (∼ 50 mSv/a), and 17 MBq h/m ( ∼ 56 mSv/a), respectively, were determined. In these water supplies remediation measures were proposed, based mainly on improved ventilation of and/or reduction of working time in the building

  6. 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.

  7. 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

  8. Radiation exposure by radio-iodine release of the planned nuclear power plant Wyhl

    Energy Technology Data Exchange (ETDEWEB)

    Bleck-Neuhaus, J

    1981-01-01

    The radioecology of iodine-131 in the off-air of a nuclear power plant is subject to investigation of the critical exposure pathway air - pasture ground - cow - milk. According to the findings on the factors influencing the radiation exposure of man presented in scientific publication we have to deviate today from static equilibrium models. Such models can no longer satisfy at the present state of the art. The viewing of the short-term time behaviour of the radioecological parameter that is imperative with iodine-131 shows that the conventional calculation, chiefly with mean values of many years, does not satisfy the requirements to replace the calculation of the radiation exposure at the most unfavourable points of exposure demanded by the Radiation Protection Ordinance. This report proves that in a number of possible events under normal operating conditions the radiation exposure is far more important and the limiting dose rates are unmistakably exceeded. If favourable conditions coincide it can in fact be expected that the radiation exposure by radio iodine remains below the limiting close rate.

  9. 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

  10. Occupational Radiation Exposure Analysis of US ITER DCLL TBM

    Energy Technology Data Exchange (ETDEWEB)

    Merrill, Brad J; Cadwallader, Lee C; Dagher, Mohamad

    2007-08-01

    This report documents an Occupational Radiation Exposure (ORE) analysis that was performed for the US International Thermonuclear Experimental Reactor (ITER) Dual Coolant Lead Lithium (DCLL) Test Blanket Module (TBM). This analysis was performed with the QADMOD dose code for anticipated maintenance activities for this TBM concept and its ancillary systems. The QADMOD code was used to model the PbLi cooling loop of this TBM concept by specifying gamma ray source terms that simulated radioactive material within the piping, valves, heat exchanger, permeator, pump, drain tank, and cold trap of this cooling system. Estimates of the maintenance tasks that will have to be performed and the time required to perform these tasks where developed based on either expert opinion or on industrial maintenance experience for similar technologies. This report details the modeling activity and the calculated doses for the maintenance activities envisioned for the US DCLL TBM.

  11. 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)

  12. 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.

  13. 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.)

  14. 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

  15. 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

  16. Mathematical models for calculating radiation dose to the fetus

    International Nuclear Information System (INIS)

    Watson, E.E.

    1992-01-01

    Estimates of radiation dose from radionuclides inside the body are calculated on the basis of energy deposition in mathematical models representing the organs and tissues of the human body. Complex models may be used with radiation transport codes to calculate the fraction of emitted energy that is absorbed in a target tissue even at a distance from the source. Other models may be simple geometric shapes for which absorbed fractions of energy have already been calculated. Models of Reference Man, the 15-year-old (Reference Woman), the 10-year-old, the five-year-old, the one-year-old, and the newborn have been developed and used for calculating specific absorbed fractions (absorbed fractions of energy per unit mass) for several different photon energies and many different source-target combinations. The Reference woman model is adequate for calculating energy deposition in the uterus during the first few weeks of pregnancy. During the course of pregnancy, the embryo/fetus increases rapidly in size and thus requires several models for calculating absorbed fractions. In addition, the increases in size and changes in shape of the uterus and fetus result in the repositioning of the maternal organs and in different geometric relationships among the organs and the fetus. This is especially true of the excretory organs such as the urinary bladder and the various sections of the gastrointestinal tract. Several models have been developed for calculating absorbed fractions of energy in the fetus, including models of the uterus and fetus for each month of pregnancy and complete models of the pregnant woman at the end of each trimester. In this paper, the available models and the appropriate use of each will be discussed. (Author) 19 refs., 7 figs

  17. 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).

  18. 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

  19. 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)

  20. 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

  1. Calculation of the quantities of radiation risk in Japanese population

    International Nuclear Information System (INIS)

    Nakamura, Yuji

    1993-01-01

    The purpose of this study was to reevaluate various kinds of indicators of radiation risks using additive projection and multiplicative projection models, as proposed by ICRP. Total death probability rate (1985) and probability rate of cancer death (1983 to 1987) were used as data base. The following indicators were calculated: total conditional death probability rate and conditional death probability rate; normalized death age probability density and unconditional death probability rate; attributable life-time probability of cancer death; and other risk indicators, including mean loss of life expectancy, reduction of life expectancy, mean annually committed probability of attributable cancer deaths, annual extra probability of cancer death, probability density of the age of death, maximum relative death probability rate (age at maximum relative rate), and probabilistic aging. In terms of calculations of these risk indicators for the comprehensive cancer death, there was no great difference between the Japanese population and ICRP. When calculating according to sites of cancer, calculations of indicators for cancer mortality (or cancer cure rate) in the Japanese population might bedifferent from ICRP's calculation. (N.K.) different from ICRP's calculations. (N.K.)

  2. Calculation of the line shapes of radiators immersed in plasma

    International Nuclear Information System (INIS)

    Hayrapetian, A.S.

    1987-01-01

    This work reports the results of theoretical calculations of line shapes of radiators immersed in plasma. The fluctuating electric field of the plasma perturbs the atomic structure of the immersed ions or atoms. The perturbed line shape is an important diagnostic tool for the temperature and density measurements of plasma. The line-shape calculation here is done by first deriving the line-shape expression, then it is shown that the problem is equivalent to calculating the temperature Green's function of the bound electron. The total Hamiltonian of the system includes the atomic, plasma, and atom-plasma parts. The temperature Green's function is calculated perturbatively by expanding in orders of atom-plasma interaction. By solving a Dyson equation, the dressed Green's functions of the bound electrons are obtained. At this point, the line shape is calculated by an analytic continuation from the complex frequency plane to real line. To derive the atomic electron Green's function, the momentum integral in the self-energy is approximated by a Riemann sum. With this approximation, the algebraic form of the line shape is obtained for an undetermined number of terms in the Riemann sum. Numerical calculation of line shape is done by using this result

  3. 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

  4. Aspects of radiation exposure amongst the population after release of radionuclides from terminal stores

    International Nuclear Information System (INIS)

    Proehl, G.; Mueller, H.; Paretzke, H.G.

    1989-08-01

    The release of radionuclides from terminal stores may lead to the contamination of ground water lying close to the surface, after the radionuclides have migrated within the covering rock. Use of this water can result in radiation exposure for human beings along many exposure pathways. In order to assess the radiation exposure from these exposure pathways the model ECOSYS-87-B was developed, as an extension of ECOSYS (Jacobi et al. 1985). On the basis of a standardized contamination of the ground water, the potential radiation exposure of a one-year-old and an adult are calculated, under the assumption that the entire food supply of these persons was produced using radioactively contaminated water. Special questions on the transfer of radionuclides in food chains are discussed, and, in particular, the mineral content of the water and the influence of the chemical form of the radionuclides dissolved in the ground water on their transfer within the food chain are explained. There is also a study of the extent to which various physiologically-based nutritional habits influence the radiation exposure of a human being. Various criteria for the evaluation of radiation exposure are discussed. (orig./HP) [de

  5. 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

  6. 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)

  7. 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...

  8. 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)

  9. Measurements and simulations of the radiation exposure to aircraft crew workplaces due to cosmic radiation in the atmosphere

    International Nuclear Information System (INIS)

    Beck, P.; Latocha, M.; Dorman, L.; Pelliccioni, M.; Rollet, S.

    2007-01-01

    As required by the European Directive 96/29/Euratom, radiation exposure due to natural ionizing radiation has to be taken into account at workplaces if the effective dose could become more than 1 mSv per year. An example of workers concerned by this directive is aircraft crew due to cosmic radiation exposure in the atmosphere. Extensive measurement campaigns on board aircraft have been carried out to assess ambient dose equivalent. A consortium of European dosimetry institutes within EURADOS WG5 summarized experimental data and results of calculations, together with detailed descriptions of the methods for measurements and calculations. The radiation protection quantity of interest is the effective dose, E (ISO). The comparison of results by measurements and calculations is done in terms of the operational quantity ambient dose equivalent, H*(10). This paper gives an overview of the EURADOS Aircraft Crew In-Flight Database and it presents a new empirical model describing fitting functions for this data. Furthermore, it describes numerical simulations performed with the Monte Carlo code FLUKA-2005 using an updated version of the cosmic radiation primary spectra. The ratio between ambient dose equivalent and effective dose at commercial flight altitudes, calculated with FLUKA-2005, is discussed. Finally, it presents the aviation dosimetry model AVIDOS based on FLUKA-2005 simulations for routine dose assessment. The code has been developed by Austrian Research Centers (ARC) for the public usage (http://avidos.healthphysics.at. (authors)

  10. Patient radiation exposure during pediatric cardiac catheterization

    International Nuclear Information System (INIS)

    Fellows, K.E.; Leibovic, S.J.

    1983-01-01

    Exposure air product (EAP) and center field entrance exposure (free-in-air) were measured in seventeen pediatric patients undergoing cardiac catheterization. Exposures were recorded separately for biplane fluoroscopy and cine angiocardiography using flat-plate ionization chambers. In the posterior-anterior (PA) projections, median EAP was 425 Roentgen-square centimeter (R-cm 2 ), with a range of 90.5-3,882 R-cm 2 ; 29-35% of this exposure occurred during cine filming. In the lateral projection, median EAP was 276 R-cm 2 (range 117-1,173); 52-59% of this exposure was due to cine filming. Median center field entrance exposure in the PA view was 7.86 Roentgens (R) with a range 2.16-73.9 of and in the lateral projection 7.39 R (range 2.64-24.6). As much as 25% of the exposure from the entire examination was contributed by manual ''test'' exposures to set cine radiographic kVp. We recommend use of testing circuits, which determine cine radiographic factors automatically and thus should lower levels of exposure

  11. Patient radiation exposure during pediatric cardiac catheterization

    International Nuclear Information System (INIS)

    Fellows, K.E.; Leibovic, S.J.

    1983-01-01

    Exposure are product (EAP) and center field entrance exposure (free-in-air) were measured in seventeen pediatric patients undergoing cardiac catheterization. Exposures were recorded separately for biplane fluoroscopy and cine angiocardiography using flat-plate ionization chambers. In the posterior-anterior (PA) projections, median EAP was 425 Roentgen-square centimeter (R-cm 2 ), with a range of 90.5-3,882 R-cm 2 ; 29-35% of this exposure occurred during cine filming. In the lateral projection, median EAP was 276 R-cm 2 (range 117-1,173); 52-59% of this exposure was due to cine filming. Median center field entrance exposure in the PA view was 7.86 Roentgens (R) with a range 2.16-73.9 of and in the lateral projection 7.39 R (range 2.64-24.6). As much as 25% of the exposure from the entire examination was contributed by manual ''test'' exposures to set cine radiographic kVp. We recommend use of testing circuits, which determine cine radiographic factors automatically and thus should lower levels of exposure. (orig.)

  12. Radiation exposure to patients during extracorporeal shock wave lithotripsy

    International Nuclear Information System (INIS)

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

    1987-01-01

    Extracorporeal shock wave lithotripsy is rapidly becoming an accepted treatment of renal calculi. Since fluoroscopy is involved to image the stones it is important to know how much radiation the patient receives during this procedure. Surface radiation exposure to the patient was measured in more than 300 fluoroscopic and radiographic procedures using thermoluminescent dosimeters. Initial results showed an average skin exposure of 10.1 rad per procedure for each x-ray unit, comparing favorably with exposure rates for percutaneous nephrostolithotomy and other routine radiological procedures. Factors influencing exposure levels include stone characteristics (location, size and opacity), physician experience and number of shocks required. Suggestions are given that may result in a 50 per cent reduction of radiation exposure

  13. Monitoring of radiation exposure and registration of doses

    International Nuclear Information System (INIS)

    1996-01-01

    The guide defines the concepts relevant to the monitoring of radiation exposure and working conditions and provides guidelines for determining the necessity of monitoring and subsequently organizing it. In addition, instructions are given for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK). Also the procedures are described for situations leading to exceptional exposures. (10 refs., 1 tab.)

  14. Protection from potential exposures: application to selected radiation sources

    International Nuclear Information System (INIS)

    1997-09-01

    This ICRP Report begins with the general principles of radiation protection in the case of potential exposures, followed by special issues in application and compliance with regulatory aims. The rest of the report uses event trees or fault trees to derive the logical structure of six scenarios of potential exposure, i.e. two irradiators, a large research accelerator, an accelerator for industrial isotope production, an industrial radiography device using a mobile source of radiation, and finally a medical gamma radiotherapy device. (UK)

  15. Childhood cancer and occupational radiation exposure in parents

    International Nuclear Information System (INIS)

    Hicks, N.; Zack, M.; Caldwell, G.G.; Fernbach, D.J.; Falletta, J.M.

    1984-01-01

    To test the hypothesis that a parent's job exposure to radiation affeOR). its his or her child's risk of cancer, the authors compared this exposure during the year before the child's birth for parents of children with and without cancer. Parents of children with cancer were no more likely to have worked in occupations, industries, or combined occupations and industries with potential ionizing radiation exposure. Bone cancer and Wilms' tumor occurred more frequently among children of fathers in all industries with moderate potential ionizing radiation exposure. Children with cancer more often had fathers who were aircraft mechanics (odds ratio (OR)) . infinity, one-sided 95% lower limit . 1.5; P . 0.04). Although four of these six were military aircraft mechanics, only children whose fathers had military jobs with potential ionizing radiation exposure had an increased cancer risk (OR . 2.73; P . 0.01). Four cancer types occurred more often among children of fathers in specific radiation-related occupations: rhabdomyosarcoma among children whose fathers were petroleum industry foremen; retinoblastoma among children whose fathers were radio and television repairmen; central nervous system cancers and other lymphatic cancers among children of Air Force fathers. Because numbers of case fathers are small and confidence limits are broad, the associations identified by this study need to be confirmed in other studies. Better identification and gradation of occupational exposure to radiation would increase the sensitivity to detect associations

  16. Radio frequency (RF) radiation exposure and health

    NARCIS (Netherlands)

    Visser, H.J.; Mahmoudi, R.; Iniewski, K.

    2013-01-01

    Through the history of wireless communication I show the explosive growth in time of mobile telephony and explain how this affects the perception of fear of the general public for electromagnetic radiation. Then, after explaining the physics of electromagnetic radiation, I discuss the interaction

  17. Calculation and Measurement of Low-Energy Radiative Moller Scattering

    Science.gov (United States)

    Epstein, Charles; DarkLight Collaboration

    2017-09-01

    A number of current nuclear physics experiments have come to rely on precise knowledge of electron-electron (Moller) and positron-electron (Bhabha) scattering. Some of these experiments, having lepton beams on targets containing atomic electrons, use these purely-QED processes as normalization. In other scenarios, with electron beams at low energy and very high intensity, Moller scattering and radiative Moller scattering have such enormous cross-sections that the backgrounds they produce must be understood. In this low-energy regime, the electron mass is also not negligible in the calculation of the cross section. This is important, for example, in the DarkLight experiment (100 MeV). As a result, we have developed a new event generator for the radiative Moller and Bhabha processes, with new calculations that keep all terms of the electron mass. The MIT High Voltage Research Laboratory provides us a unique opportunity to study this process experimentally and compare it with our work, at a low beam energy of 2.5 MeV where the effects of the electron mass are significant. We are preparing a dedicated apparatus consisting of a magnetic spectrometer in order to directly measure this process. An overview of the calculation and the status of the experiment will be presented.

  18. REMIT, Radiation Exposure Monitoring and Information Transmittal System

    International Nuclear Information System (INIS)

    Cale, R.; Clark, T.; Dixson, P.; Hagemeyer, D.; Hardwick, C.; Pippen, H.

    1997-01-01

    1 - Description of program or function: The Radiation Exposure Monitoring and Information Transmittal (REMIT) system is designed to assist U.S. Nuclear Regulatory Commission (NRC) licensees in meeting the reporting requirements of the Revised 10 CFR Part 20 and in agreement with the guidance contained in Regulatory Guide 8.7, Rev.1, Instructions for Recording and Reporting Occupational Exposure Data. REMIT is a personal computer (PC) -based menu driven system that facilitates the manipulation of data base files to record and report radiation exposure information. REMIT is designed to be user-friendly and contains the full text of Regulatory Guide 8.7, Rev.1, on-line as well as context-sensitive help throughout the program. The user can enter data directly from NRC Form 5s or Form 4s. REMIT allows the user to view the individual's exposure in relation to regulatory or administrative limits and will alert the user to exposures in excess of these limits. The system also provides for the calculation and summation of dose from intakes and the determination of the dose to the maximally exposed extremity for the monitoring year. REMIT can produce NRC Form 5s and 4s in paper and electronic format and can import/export data from ASCII and data base files. 2 - Method of solution: REMIT makes use of the dose conversion factors from EPA Report 11 Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submission, and Ingestion, to calculate the Committed Dose Equivalent to the maximally exposed organ and the committed Effective Dose Equivalent from intakes measured in micro-curies. REMIT also estimates the amount (in micrograms) of uranium intake from the activity entered in micro-curies. This calculation is based on the specific activities of the uranium isotopes. 3 - Restrictions on the complexity of the problem: REMIT is a single- user system that only runs on IBM compatible PC systems under DOS and supports only Hewlett

  19. Cost benefit analysis for occupational radiation exposure

    International Nuclear Information System (INIS)

    Caruthers, G.F.; Rodgers, R.C.; Donohue, J.P.; Swartz, H.M.

    1978-01-01

    In the course of system design, many decisions must be made concerning different aspects of that particular system. The design of systems and components in a nuclear power plant has the added faction of occupational exposure experienced as a result of that design. This paper will deal with the different methods available to factor occupational exposure into design decisions. The ultimate goal is to have exposures related to the design 'As Low As Reasonably Achievable' or ALARA. To do this an analysis should be performed to show that the cost of reducing exposures any further cannot be justified in a cost-benefit analysis. In this paper examples will be given that will show that it is possible to change to a design which would increase occupational exposure somewhat but would increase the benefit over the cost of the extra exposure received. It will also be shown that some changes in design or additional equipment could be justified due to a reduction in exposure while some changes could not be justified on a reduction in exposure aspect alone but are justified on a time saving aspect such as during a refueling outage. (author)

  20. Radiation exposure of workers in nuclear medicine

    International Nuclear Information System (INIS)

    Bujnova, A.

    2008-01-01

    Nuclear medicine is an interdisciplinary department that deals with diagnosis and therapy using open sources. Therefore workers in nuclear medicine are in daily contact with ionizing radiation and thus it is essential to monitor a radiation load. Each work must therefore carry out monitoring of workers. It monitors compliance with the radiation limits set by law, allows an early detection of deviations from normal operation and to demonstrate whether the radiation protection at the workplace is optimized. This work describes the principles of monitoring of workers in nuclear medicine and monitoring methods for personal dosimetry. In the next section the author specifically deals with personal dosimetry at the Department of Nuclear Medicine St. Elizabeth Cancer Institute, Bratislava (KNM-Ba-OUSA). The main part of the work is to evaluate the results of a one-year monitoring of radiation workers KNM-Ba-OUSA. (author)

  1. Radiation exposure during travelling in Malaysia

    International Nuclear Information System (INIS)

    Omar, M.; Hassan, A.; Sulaiman, I.

    2006-01-01

    Absorbed dose rates in vehicles during travelling by different modes of transport in Malaysia were measured. Radiation levels measured on roads in Peninsular Malaysia were within a broad range, i.e. between 36 and 1560 nGy h -1 . The highest reading, recorded while travelling near monazite and zircon mineral dumps, was 13 times the mean environmental radiation level of Malaysia. It is evident that radioactive material dumps on the roadsides can influence the radiation level on the road. The absorbed dose rates measured while travelling on an ordinary train were between 60 and 350 nGy h -1 . The highest reading was measured when the train passed a tunnel built through a granite rock hill. The measurement during sea travelling by ferries gave the lowest radiation level owing to merely cosmic radiation at the sea level. (authors)

  2. Cancer risks following diagnostic and therapeutic radiation exposure in children

    Energy Technology Data Exchange (ETDEWEB)

    Kleinerman, Ruth A. [National Institutes of Health, Division of Cancer Epidemiology and Genetics, National Cancer Institute, EPS 7044, Rockville, MD (United States)

    2006-09-15

    The growing use of interventional and fluoroscopic imaging in children represents a tremendous benefit for the diagnosis and treatment of benign conditions. Along with the increasing use and complexity of these procedures comes concern about the cancer risk associated with ionizing radiation exposure to children. Children are considerably more sensitive to the carcinogenic effects of ionizing radiation than adults, and children have a longer life expectancy in which to express risk. Numerous epidemiologic cohort studies of childhood exposure to radiation for treatment of benign diseases have demonstrated radiation-related risks of cancer of the thyroid, breast, brain and skin, as well as leukemia. Many fewer studies have evaluated cancer risk following diagnostic radiation exposure in children. Although radiation dose for a single procedure might be low, pediatric patients often receive repeated examinations over time to evaluate their conditions, which could result in relatively high cumulative doses. Several cohort studies of girls and young women subjected to multiple diagnostic radiation exposures have been informative about increased mortality from breast cancer with increasing radiation dose, and case-control studies of childhood leukemia and postnatal diagnostic radiation exposure have suggested increased risks with an increasing number of examinations. Only two long-term follow-up studies of cancer following cardiac catheterization in childhood have been conducted, and neither reported an overall increased risk of cancer. Most cancers can be induced by radiation, and a linear dose-response has been noted for most solid cancers. Risks of radiation-related cancer are greatest for those exposed early in life, and these risks appear to persist throughout life. (orig.)

  3. Cancer risks following diagnostic and therapeutic radiation exposure in children

    International Nuclear Information System (INIS)

    Kleinerman, Ruth A.

    2006-01-01

    The growing use of interventional and fluoroscopic imaging in children represents a tremendous benefit for the diagnosis and treatment of benign conditions. Along with the increasing use and complexity of these procedures comes concern about the cancer risk associated with ionizing radiation exposure to children. Children are considerably more sensitive to the carcinogenic effects of ionizing radiation than adults, and children have a longer life expectancy in which to express risk. Numerous epidemiologic cohort studies of childhood exposure to radiation for treatment of benign diseases have demonstrated radiation-related risks of cancer of the thyroid, breast, brain and skin, as well as leukemia. Many fewer studies have evaluated cancer risk following diagnostic radiation exposure in children. Although radiation dose for a single procedure might be low, pediatric patients often receive repeated examinations over time to evaluate their conditions, which could result in relatively high cumulative doses. Several cohort studies of girls and young women subjected to multiple diagnostic radiation exposures have been informative about increased mortality from breast cancer with increasing radiation dose, and case-control studies of childhood leukemia and postnatal diagnostic radiation exposure have suggested increased risks with an increasing number of examinations. Only two long-term follow-up studies of cancer following cardiac catheterization in childhood have been conducted, and neither reported an overall increased risk of cancer. Most cancers can be induced by radiation, and a linear dose-response has been noted for most solid cancers. Risks of radiation-related cancer are greatest for those exposed early in life, and these risks appear to persist throughout life. (orig.)

  4. Radiation exposure from Chest CT: Issues and Strategies

    Science.gov (United States)

    Maher, Michael M.; Rizzo, Stefania; Kanarek, David; Shephard, Jo-Anne O.

    2004-01-01

    Concerns have been raised over alleged overuse of CT scanning and inappropriate selection of scanning methods, all of which expose patients to unnecessary radiation. Thus, it is important to identify clinical situations in which techniques with lower radiation dose such as plain radiography or no radiation such as MRI and occasionally ultrasonography can be chosen over CT scanning. This article proposes the arguments for radiation dose reduction in CT scanning of the chest and discusses recommended practices and studies that address means of reducing radiation exposure associated with CT scanning of the chest. PMID:15082885

  5. 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

  6. Effects of radiation exposure from radiopharmaceuticals used in diagnostic studies

    International Nuclear Information System (INIS)

    Witcofski, R.L.

    1981-01-01

    In the United States about 90 percent of man-made radiation exposure to the general population is from the use of radiation in diagnostic medicine. Although the doses of radiation from these procedures to individuals are generally quite small, large numbers of people are exposed. Estimates of the radiation doses associated with such use in the healing arts are approximately 15 million person-rem to the general population from diagnostic x ray and 3.3 million person-rem from the diagnostic use of radiopharmaceuticals. The purpose of this paper is to present what is known about the possible effects of radiation from diagnostic radiopharmaceuticals

  7. Radiation exposure of radiographers who handle 18 F ...

    African Journals Online (AJOL)

    18F-fluorodeoxyglucose (18F-FDG) is used in most diagnostic applications of Positron Emission Tomography (PET). It has high annihilation energy of 511 keV, which results in potentially high radiation doses for staff. This study investigated radiographer radiation exposure during receipt, administration and scanning of ...

  8. Radiation exposure from diagnostic imaging among patients with gastrointestinal disorders.

    LENUS (Irish Health Repository)

    Desmond, Alan N

    2012-03-01

    There are concerns about levels of radiation exposure among patients who undergo diagnostic imaging for inflammatory bowel disease (IBD), compared with other gastrointestinal (GI) disorders. We quantified imaging studies and estimated the cumulative effective dose (CED) of radiation received by patients with organic and functional GI disorders. We also identified factors and diagnoses associated with high CEDs.

  9. 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.)

  10. Improvement of NSSS design to reduce occupational radiation exposure (ORE)

    International Nuclear Information System (INIS)

    Dubourg, M.

    1985-05-01

    As a result of its R and D activities, FRAMATOME has initiated concrete measures to help to reduce personnel radiation exposure. These measures include reduction in the sources and quantity of activable products, and in the duration of personnel exposure during maintenance

  11. The recovery of the human organism after radiation exposure

    International Nuclear Information System (INIS)

    Gerber, G.B.

    1976-01-01

    The repair of radiation damage in the human organism is reviewed. A distinction is made between the single repair steps, first the molecular repair of sublethal damage during the periods of 30 min to 2 h and several days to months, second the substitution of the whole cells during a period of reproduction which is specific for the kind and persistence of the cells. One example is the radiosensitive stem cell with a reproduction rate of 40% and a redoublication time of 10 d at 100 rads and the very low reproduction rate of 1% with redoublication time of 7 d after a dose of 400 rads. 5 rads seems to be acceptable for systems with recovery and repeated exposure, single doses normally should not exceed 25 rads, not 100 rads/d for to save human life, and not a total dose of 500 rads. About 20% of irradiation damage is not repaired and leads to late effects, for example the induction of tumors, the shortening of life span and an increase in embryonic mortality. The author recommends the acceptance of a radiation dose leading to 20 additional cases of leucemia in the whole population of Germany and an increase of tumor frequency of 1%. The shortening of life span should not exceed 0,5%. The equivalent residual dose (ERD) can be calculated by the following equation: ERD = last effective dose minus 5 rads x number of days. (AJ) [de

  12. Assessment of occupational exposures to external radiation - IAEA recommendation 1995

    Energy Technology Data Exchange (ETDEWEB)

    Trousil, J; Plichta, J [CSOD, Praha (Czech Republic); Nikodemova, D [SOD, Bratislava (Slovakia)

    1996-12-31

    The IAEA recommendation contains the guidance on: (1) establishing monitoring programmes; (2) the interpretation of results; (3) records keeping; (4) quality assurance. The objectives for workplace monitoring including the recommended methods are also involved. The choice of personal dosemeter depends not only on the type of radiation but also on the method of interpretation what will be used: (1) photon dosemeters giving information only on the personal dose equivalent Hp(10) - mostly TL or RPL dosemeters are used; (2) photon dosemeter of discriminating type giving, in addition to Hp(10) and Hp(0.07), some indication of radiation type and effective energy and detection of electrons - data which must be known for E calculation -mostly film badge is used; (3) extremity dosemeters giving information on Hp(0.07) - mostly TL dosemeters are used; (4) neutron dosemeters giving information on Hp(10) -track-etch or albedo dosemeters are used. The monitoring service should have quality assurance testing which is an organization`s internal system of procedures and practices which assures the quality of its service. This process may be part of the approval performance testing which is a part of approved procedures carried out be the authoritative organization in regular intervals. The approved monitoring service should perform the dose records keeping which serve the protection of the workers and these data are the part of the Register of the Professional Exposures which is mostly organized by the authoritative body. (J.K.).

  13. Assessment of occupational exposures to external radiation - IAEA recommendation 1995

    International Nuclear Information System (INIS)

    Trousil, J.; Plichta, J.; Nikodemova, D.

    1995-01-01

    The IAEA recommendation contains the guidance on: (1) establishing monitoring programmes; (2) the interpretation of results; (3) records keeping; (4) quality assurance. The objectives for workplace monitoring including the recommended methods are also involved. The choice of personal dosemeter depends not only on the type of radiation but also on the method of interpretation what will be used: (1) photon dosemeters giving information only on the personal dose equivalent Hp(10) - mostly TL or RPL dosemeters are used; (2) photon dosemeter of discriminating type giving, in addition to Hp(10) and Hp(0.07), some indication of radiation type and effective energy and detection of electrons - data which must be known for E calculation -mostly film badge is used; (3) extremity dosemeters giving information on Hp(0.07) - mostly TL dosemeters are used; (4) neutron dosemeters giving information on Hp(10) -track-etch or albedo dosemeters are used. The monitoring service should have quality assurance testing which is an organization's internal system of procedures and practices which assures the quality of its service. This process may be part of the approval performance testing which is a part of approved procedures carried out be the authoritative organization in regular intervals. The approved monitoring service should perform the dose records keeping which serve the protection of the workers and these data are the part of the Register of the Professional Exposures which is mostly organized by the authoritative body. (J.K.)

  14. 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)

  15. 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)

  16. Econometric model for age- and population-dependent radiation exposures

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Slaughter, D.M.; Rogers, V.C.

    1991-01-01

    The economic impact associated with ionizing radiation exposures in a given human population depends on numerous factors including the individual's mean economic status as a function age, the age distribution of the population, the future life expectancy at each age, and the latency period for the occurrence of radiation-induced health effects. A simple mathematical model has been developed that provides an analytical methodology for estimating the societal econometrics associated with radiation effects are to be assessed and compared for economic evaluation

  17. Solid cancer risks from radiation exposure for the Australian population

    International Nuclear Information System (INIS)

    Wise, K.N.

    2003-01-01

    Estimates are made of the risks to the Australian population as a function of age and gender for mortality or morbidity for all solid cancers after exposure to radiation. Excess relative risk (ERR) and excess absolute risk (EAR) models are used. The model coefficients are re-evaluated for radiation doses expressed as effective dose using data from the Japanese Life Span Study. Life-table methods are used throughout and the risk measures studied are: the risk of exposure related death, RERD and the risk of exposure related cancer, RERC. Australian life-table data and the age-specific cancer incidence and mortality rates of Australian males and females are taken from recent published tables. No dose and dose-rate effectiveness factor is applied. Sources of uncertainty used to calculate the confidence regions for the estimated risks include the statistical uncertainties of the model parameters and of the extrapolation of the risks beyond the period supported by the epidemiological data. Summary values of the risks are reported as averages of those calculated from the ERR and the EAR models. For males, the mortality risks per sievert range from 14% for 0-9 year age group, 7% at 30-39 years and 4% at 50-59 years. Corresponding values for females are 20%, 10% and 6%. Incidence risks are higher: for males the estimates are 32% for the 0-9 year group, 12% at 30-39 and 5% at 50-59. Corresponding values for females are 56%, 20% and 8%. The 90% confidence regions are about ± 50% of these values. Estimates are given for the risks from CT whole-body scanning or virtual colonoscopy which could be used for cancer screening. If used at 3 year intervals and the effective dose per procedure is 10 mSv, then the RERD for males beginning screening at 40, 50 and 60 years is 0.4%, 0.3% and 0.1%, respectively and for females, 0.6%, 0.4% and 0.2%, respectively. RERD estimates for a 5 year interval between screens are about one-third smaller. Copyright (2003) Australasian College of

  18. The internal radiation dose calculations based on Chinese mathematical phantom

    International Nuclear Information System (INIS)

    Wang Haiyan; Li Junli; Cheng Jianping; Fan Jiajin

    2006-01-01

    The internal radiation dose calculations built on Chinese facts become more and more important according to the development of nuclear medicine. the MIRD method developed and consummated by the society of Nuclear Medicine (America) is based on the European and American mathematical phantom and can't fit Chinese well. The transport of γ-ray in the Chinese mathematical phantom was simulated with Monte Carlo method in programs as MCNP4C. the specific absorbed fraction (Φ) of Chinese were calculated and the Chinese Φ database was created. The results were compared with the recommended values by ORNL. the method was proved correct by the coherence when the target organ was the same with the source organ. Else, the difference was due to the different phantom and the choice of different physical model. (authors)

  19. Recent Progress of the Synchrotron Radiation Calculation Code SPECTRA

    International Nuclear Information System (INIS)

    Tanaka, T.; Kitamura, H.

    2007-01-01

    SPECTRA is a computer software to calculate optical properties of synchrotron radiation (SR) emitted by electrons passing through magnetic devices such as bending magnets, wigglers and undulators. It has been used to design various devices in the SR beamline, such as high heat-load components in the front-end section and optical elements in the optics hutch. In addition, the electron beam quality can be estimated by comparison between the measured and calculated properties of SR. Since the first announcement, numerous improvements have been made to SPECTRA to achieve less computation time with higher numerical accuracy. In addition, a number of functions have been added to follow the user's demand. In this paper, recent progress of SPECTRA is presented and details of the new functions are explained together with several examples

  20. Occupational radiation exposure monitoring among radiation workers in Nepal

    International Nuclear Information System (INIS)

    Bhatt, Chhavi Raj; Shrestha, Shanta Lall; Khanal, Tara; Ween, Borgny

    2008-01-01

    Nepal was accepted as a member of the IAEA in 2007. Nepal is one of the world's least developed countries and is defined in Health Level IV. The population counted 26.4 millions in 2007. The health care sector increases with new hospitals and clinics, however, Nepal has no radiation protection authority or radiation protection regulation in the country until now. The radiation producing equipment in the health sector includes conventional X-ray and dental X-ray equipment, fluoroscopes, mammography, CT, catheterization laboratory equipment, nuclear medicine facilities, a few linear accelerators, Co 60 teletherapy and High Dose Rate brachytherapy sources. The situation regarding dosimetry service for radiation workers is unclear. A survey has been carried out to give an overview of the situation. The data collection of the survey was performed by phone call interviews with responsible staff at the different hospitals and clinics. Data about different occupationally exposed staff, use of personal radiation monitoring and type of dosimetry system were collected. In addition, it was asked if dosimetry reports were compiled in files or databases for further follow-up of staff, if needed. The survey shows that less of 25% of the procedures performed on the surveyed hospitals and clinics are performed by staff with personnel radiation monitoring. Radiation monitoring service for exposed staff is not compulsory or standardized, since there is no radiation protection authority. Nepal has taken a step forward regarding radiation protection, with the IAEA membership, although there are still major problems that have to be solved. An evaluation of the existing practice of staff dosimetry can be the first helpful step for further work in building a national radiation protection authority. (author)

  1. Health Effects of Exposure to Low Dose of Radiation

    International Nuclear Information System (INIS)

    Alatas, Zubaidah

    2003-01-01

    Human beings are exposed to natural radiation from external sources include radionuclides in the earth and cosmic radiation, and by internal radiation from radionuclides, mainly uranium and thorium series, incorporated into the body. Living systems have adapted to the natural levels of radiation and radioactivity. But some industrial practices involving natural resources enhance these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Biological effects of ionizing radiation are the outcomes of physical and chemical processes that occur immediately after the exposure, then followed by biological process in the body. These processes will involve successive changes in the molecular, cellular, tissue and whole organism levels. Any dose of radiation, no matter how small, may produce health effects since even a single ionizing event can result in DNA damage. The damage to DNA in the nucleus is considered to be the main initiating event by which radiation causes damage to cells that results in the development of cancer and hereditary disease. It has also been indicated that cytogenetic damage can occur in cells that receive no direct radiation exposure, known as bystander effects. This paper reviews health risks of low dose radiation exposure to human body causing stochastic effects, i.e. cancer induction in somatic cells and hereditary disease in genetic cells. (author)

  2. Occupational radiation exposure and mortality study

    International Nuclear Information System (INIS)

    Coppock, E.; Dobson, D.; Fair, M.

    1992-06-01

    An epidemiological cohort study of some 300,000 Canadians enrolled in the National Dose Registry (NDR) is being undertaken to determine if there is excess cancer or other causes of mortality among those workers who are occupationally exposed to low levels of ionizing radiation. The results of this study may provide better understanding of the dose-response relationship for low doses of ionizing radiation and aid in the verification of risk estimates for radiation-induced cancer mortality. The Department of National Health and Welfare (DNHW) is responsible for the Registry; this study is being carried out by the Bureau of Radiation and Medical Devices (BRMD) with financial assistance and co-operation of various agencies including Statistics Canada and the Atomic Energy Control Board

  3. electromagnetic radiation exposure from cellular base station

    African Journals Online (AJOL)

    eobe

    2DEPARTMENT OF ELECTRICAL/ELECTRONIC ENGINEERING, FEDERAL ... equipment comply with international standards and thus the radiated field propagated from their installation ... adverse health effects such as blood brain barrier,.

  4. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    De Angelis, G. E-mail: gianni.deangelis@iol.it; Caldora, M.; Santaquilani, M.; Scipione, R.; Verdecchia, A

    2001-06-01

    A study of radiation exposures in the ionizing radiation environment of the atmosphere is currently in progress for the Italian civil aviation flight personnel. After a description of the considered data sources/ the philosophy of the study is presented/ and an overview is given of the data processing with regard to flight routes/ the computational techniques for radiation dose evaluation along the flight paths and for the exposure matrix building/ along with an indication of the results that the study should provide.

  6. Monitoring of radiation exposure and registration of doses

    International Nuclear Information System (INIS)

    1993-01-01

    The Section 32 of the Finnish Radiation Act (592/91) defines the requirements to be applied to the monitoring of the radiation exposure and working conditions in Finland. The concepts relevant to the monitoring and guidelines for determining the necessity of the monitoring as well as its organizing are given in the guide. Instructions for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK) are given, also procedures for situations leading to exceptional exposures are described. (9 refs.)

  7. Fitness of equipment used for medical exposures to ionising radiation

    International Nuclear Information System (INIS)

    1998-01-01

    The advice in this guidance note is aimed at employers in control of equipment used for medical exposures to ionising radiation and ancillary equipment. This includes NHS trusts, health authorities or boards, private hospitals, clinics, surgeries, medical X-ray facilities in industry, dentists and chiropractors. The guidance should also be useful to radiation protection advisers appointed by such employers. The guidance provides advice on the requirements of regulation 33 of the Ionising Radiations Regulations 1985 (IRR85). In particular, it covers: (a) the selection, installation, maintenance, calibration and replacement of equipment to ensure that it is capable of restricting, so far as reasonably practicable, the medical exposure of any person to the extent that this is compatible with the intended diagnostic or therapeutic purpose; (b) recommended procedures for the definitive calibration of radiotherapy treatment; and (c) the need to investigate incidents involving a malfunction or defect in any 'radiation equipment' which result in medical exposures much greater than intended and to notify the Health and Safety Executive (HSE). 'Medical exposure' is defined in IRR85 as exposure of a person to ionising radiation for the purpose of his or her medical or dental examination or treatment which is conducted under the direction of a suitably qualified person and includes any such examination or treatment conducted for the purposes of research. For convenience, people undergoing medical exposure will be referred to as 'patients' in this guidance. Nothing in this publication is intended to indicate whether or not patients should be informed of any incident resulting from malfunction or defect in equipment used for medical exposure and the possible consequences of that exposure. As stated above, this guidance concerns medical exposures much greater than intended and although exposures much lower than intended can also have serious consequences, the incident would not

  8. Radiation exposure of the population due to medical procedures

    International Nuclear Information System (INIS)

    Frischauf, H.

    1976-01-01

    The question of individual benefit-risk ratio in X-ray exposures is considered. The growth rate of the number of radiological examinations in New Zealand, Sweden, UK and USA is stated to be between 2 and 6 per cent per annum. The risks of internal radioisotope tests are emphasised and reductions of exposure are reported when 99Tc isotopes are used, counterbalanced by the increasing number of exposures made; the question of radiation-induced leukemia is raised in this respect. The problems of analysing delayed radiation effects are discussed, and the possibility of animal tests is suggested. (G.M.E.)

  9. 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

  10. Radiation exposure and risk of death

    International Nuclear Information System (INIS)

    Hongo, Syozo

    1979-01-01

    By using the risk factor given in ICRP publication 26 and an assumption of linear relationship between risk and dose, death rate and death number which correspond to radiation dose level and collective dose level of Japanese are estimated and they are compared with vital statistics of Japanese in 1975 to get out some ideas about radiation risk relative to the risks of everyday life. (author)

  11. Radiation Resistance Test of Wireless Sensor Node and the Radiation Shielding Calculation

    Energy Technology Data Exchange (ETDEWEB)

    Li, Liqan; Sur, Bhaskar [Atomic Energy of Canada Limited, Ontario (Canada); Wang, Quan [University of Western Ontario, Ontario (Canada); Deng, Changjian [The University of Electronic Science and Technology, Chengdu (China); Chen, Dongyi; Jiang, Jin [Applied Physics Branch, Ontario (Korea, Republic of)

    2014-08-15

    A wireless sensor network (WSN) is being developed for nuclear power plants. Amongst others, ionizing radiation resistance is one essential requirement for WSN to be successful. This paper documents the work done in Chalk River Laboratories of Atomic Energy of Canada Limited (AECL) to test the resistance to neutron and gamma radiation of some WSN nodes. The recorded dose limit that the nodes can withstand before being damaged by the radiation is compared with the radiation environment inside a typical CANDU (CANada Deuterium Uranium) power plant reactor building. Shielding effects of polyethylene, cadmium and lead to neutron and gamma radiations are also analyzed using MCNP simulation. The shielding calculation can be a reference for the node case design when high dose rate or accidental condition (like Fukushima) is to be considered.

  12. Understanding of radiation protection in medicine. Pt. 2. Occupational exposure and system of radiation protection

    International Nuclear Information System (INIS)

    Iida, Hiroji; Yamamoto, Tomoyuki; Shimada, Yasuhiro

    1997-01-01

    Using a questionnaire we investigated whether radiation protection is correctly understood by medical doctors (n=140) and nurses (n=496). Although medical exposure is usually understood by medical doctors and dentists, their knowledge was found to be insufficient. Sixty-eight percent of medical doctors and 50% of dentists did not know about the system of radiation protection. Dose monitoring was not correctly carried out by approximately 20% of medical staff members, and medical personnel generally complained of anxiety about occupational exposure rather than medical exposure. They did not receive sufficient education on radiation exposure and protection in school. In conclusion, the results of this questionnaire suggested that they do not have adequate knowledge about radiation exposure and protection. The lack of knowledge about protection results in anxiety about exposure. To protect oneself from occupational exposure, individual radiation doses must be monitored, and medical practice should be reconsidered based on the results of monitoring. To eliminate unnecessary medical and occupational exposure and to justify practices such as radiological examinations, radiation protection should be well understood and appropriately carried out by medical doctors and dentists. Therefore, the education of medical students on the subject of radiation protection is required as is postgraduate education for medical doctors, dentists and nurses. (author)

  13. Radiation exposure of the population around Chernobyl

    International Nuclear Information System (INIS)

    Botsch, W.; Beltz, D.; Handl, J.; Michel, R.

    1999-01-01

    Although the population in large parts of northern Ukraine, the region around Chernobyl, was resettled, these people are now returning to their accustomed agricultural environment - illegally, but tolerated. In order for evacuated villages to be cleared for resettlement, the dose commitment due to continuous external and internal exposures of the persons returning must be determined. Examination concentrates on the fallout of reactor nuclides, the path of radionuclides through the food chain to people, and on present and post exposures. Special attention in this respect is paid to the deposition density of cesium. On the basis of the data collected so far, the village inhabitants considered in 1998/99 suffer an average external exposure of 0.7±0.2 mSv/a in addition to the natural external exposure of 0.8 mSv/a and, with a conversion factor of 0.038 mSv/a per kBq of 137 Cs whole body activity [8], 0.5±0.2 mSv/a (excluding inhabitants 17 and 18) of additional internal exposure, mainly as a function of mushroom intake. The ban on consumption of mushrooms and fruit growing in the forests, and education of the public about the reasons for it, could help to reduce the additional internal exposure further to approx. 0.1 mSv/a. (orig.) [de

  14. Cytogenetics observation and radiation influence evaluation of exposed persons in a discontinuous radiation exposure event

    International Nuclear Information System (INIS)

    Chen Ying; Liu Xiulin; Yang Guoshan; Ge Shili; Jin Cuizhen; Yao Bo

    2003-01-01

    The cytogenetics results and dose estimation of exposed and related persons in an discontinuous radiation exposure event were reported in this paper. According to dicentrics + ring and micronucleus results combined with clinical data, slight (middle) degree of subacute radiation symptom of the victim was diagnosed. A part of 52 examined persons were exposed to radiation in a certain degree

  15. 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)

  16. Occupational radiation protection: Protecting workers against exposure to ionizing radiation. Contributed papers

    International Nuclear Information System (INIS)

    2003-07-01

    Occupational exposure to ionizing radiation can occur in a range of industries, mining and milling; medical institutions, educational and research establishments and nuclear fuel cycle facilities. The term 'occupational exposure' refers to the radiation exposure incurred by a worker, which is attributable to the worker's occupation and committed during a period of work. According to the latest (2000) Report of the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), an estimated 11 million workers are monitored for exposure to ionizing radiation. They incur radiation doses attributable to their occupation, which range from a small fraction of the global average background exposure to natural radiation up to several times that value. It should be noted that the UNSCEAR 2000 Report describes a downward trend in the exposure of several groups of workers, but it also indicates that occupational exposure is affecting an increasingly large group of people worldwide. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), which are co-sponsored by, inter alia, the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (NEA) and the World Health Organization (WHO), establish a system of radiation protection which includes radiation dose limits for occupational exposure. Guidance supporting the requirements of the BSS for occupational protection is provided in three interrelated Safety Guides, jointly sponsored by the IAEA and the ILO. These Guides describe, for example, the implications for employers in discharging their main responsibilities (such as setting up appropriate radiation protection programmes) and similarly for workers (such as properly using the radiation monitoring devices provided to them). The IAEA i organized its first International Conference on Occupational Radiation Protection. The

  17. Leukaemia risks and exposure to ionizing radiations. ASN seminar, Tuesday, June 9, 2015, report

    International Nuclear Information System (INIS)

    Niel, Jean-Christophe; Samain, Jean-Paul; Colonna, Marc; Maynadie, Marc; Richardson, David; Bey, Pierre; Leuraud, Klervi; Laurier, Dominique; Hemon, Denis; Spycher, Ben; Kosti, Ourania; Bouville, Andre; Grosche, Bernd; Ziegelberger, Gunde; Kesminiene, Ausrele; Clavel, Jacqueline; Smeesters, Patrick; Murith, Christophe

    2015-08-01

    This seminar aims at proposing a review of present knowledge on leukaemia risks for children and adults associated with ionizing radiations, and at sharing knowledge between experts. After an introduction which outlined the interest of the ASN in research issues, and the importance awarded by the ASN to the variety of points of view, a first session addressed leukaemia and exposures to ionizing radiations. The contributions addressed some general aspects (an overview of leukaemia in France, the different types of adult and child leukaemia), leukaemia and acute exposures to ionizing radiations (ionizing radiation and leukaemia among Japanese bomb survivors, risks of leukaemia after radiotherapy), leukaemia and chronic exposures to ionizing radiations (assessment of epidemiological studies for adult chronic exposures). The second session addressed childhood leukaemia and ionizing radiations. The contributions of this second session more particularly addressed the following topics: childhood leukaemia and natural radioactivity (French studies, synthesis of international studies and a new Swiss study), childhood leukaemia and proximity of nuclear base installations (assessment of national and international studies, analysis of cancer risks in populations near nuclear facilities in the US, calculation of dose at the medulla as example of dosimetry of ionizing radiations and leukaemia, conclusions of the 2012 MELODI workshop), childhood leukaemia and scanner (recent results and perspectives), childhood leukaemia and other risk factors (etiology of childhood leukaemia - presentation of French studies initiated by the INSERM, and presentation of studies initiated by BfS)

  18. A computer system for occupational radiation exposure information

    International Nuclear Information System (INIS)

    Hunt, H.W.

    1984-01-01

    A computerized occupational radiation exposure information system has been developed to maintain records for contractors at the U.S. Department of Energy's (DOE) Hanford Site. The system also allows indexing and retrieval of three million documents from microfilm, thus significantly reducing storage needs and costs. The users are linked by display terminals to the data base permitting them instant access to dosemetry and other radiation exposure information. Personnel dosemeter and bioassay results, radiation training, respirator fittings, skin contaminations and other radiation occurrence records are included in the data base. The system yields immediate analysis of radiological exposures for operating management and health physics personnel, thereby releasing personnel to use their time more effectively

  19. Environmental radioactivity and radiation exposure in 2015; Umweltradioaktivitaet und Strahlenbelastung im Jahr 2015

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-07-20

    The information of the German Federal Government on the environmental radioactivity and radiation exposure in 2015 covers the following issues: selected topics of radiation protection, natural radiation exposure; civilizing (artificial) radiation exposure: nuclear power plants and other nuclear facilities, uranium mine recultivation, radioactive materials in industry and households, fallout from nuclear weapon testing and reactor accidents; occupational radiation exposure: exposed personnel in nuclear facilities, aviation personnel, radiation accidents; medical radiation exposure: nuclear medical diagnostics and therapy; non-ionizing radiation: electromagnetic fields, UV radiation, optical radiation.

  20. Natural and anthropogenic radiation exposure of humans in Germany; Natuerliche und zivilisatorische Strahlenexposition des Menschen in Deutschland

    Energy Technology Data Exchange (ETDEWEB)

    Koelzer, Winfried

    2016-12-15

    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.