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

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)

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

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

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

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.

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

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...

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.

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.

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.

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)

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)

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...

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.

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

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

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

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

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)

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)

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

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

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

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.

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.

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).

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)

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

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.

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

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

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.

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

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

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

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)

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.

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

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

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)

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

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.

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

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

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

Radiation exposure by radio-iodine release of the planned nuclear power plant Wyhl. Expert's opinion on thyroid exposure due to radioactive I-131

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.

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

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

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

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

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

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)

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.)

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

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.

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.

Radiation transport modeling and assessment to better predict radiation exposure, dose, and toxicological effects to human organs on long duration space flights

Science.gov (United States)

Denkins, P.; Badhwar, G.; Obot, V.; Wilson, B.; Jejelewo, O.

2001-01-01

NASA is very interested in improving its ability to monitor and forecast the radiation levels that pose a health risk to space-walking astronauts as they construct the International Space Station and astronauts that will participate in long-term and deep-space missions. Human exploratory missions to the moon and Mars within the next quarter century, will expose crews to transient radiation from solar particle events which include high-energy galactic cosmic rays and high-energy protons. Because the radiation levels in space are high and solar activity is presently unpredictable, adequate shielding is needed to minimize the deleterious health effects of exposure to radiation. Today, numerous models have been developed and used to predict radiation exposure. Such a model is the Space Environment Information Systems (SPENVIS) modeling program, developed by the Belgian Institute for Space Aeronautics. SPENVIS, which has been assessed to be an excellent tool in characterizing the radiation environment for microelectronics and investigating orbital debris, is being evaluated for its usefulness with determining the dose and dose-equivalent for human exposure. Thus far. the calculations for dose-depth relations under varying shielding conditions have been in agreement with calculations done using HZETRN and PDOSE, which are well-known and widely used models for characterizing the environments for human exploratory missions. There is disagreement when assessing the impact of secondary radiation particles since SPENVIS does a crude estimation of the secondary radiation particles when calculating LET versus Flux. SPENVIS was used to model dose-depth relations for the blood-forming organs. Radiation sickness and cancer are life-threatening consequences resulting from radiation exposure. In space. exposure to radiation generally includes all of the critical organs. Biological and toxicological impacts have been included for discussion along with alternative risk mitigation

Radiation transport modeling and assessment to better predict radiation exposure, dose, and toxicological effects to human organs on long duration space flights

Science.gov (United States)

Denkins, Pamela; Badhwar, Gautam; Obot, Victor; Wilson, Bobby; Jejelewo, Olufisayo

2001-08-01

NASA is very interested in improving its ability to monitor and forecast the radiation levels that pose a health risk to space-walking astronauts as they construct the International Space Station and astronauts that will participate in long-term and deep-space missions. Human exploratory missions to the moon and Mars within the next quarter century, will expose crews to transient radiation from solar particle events which include high-energy galactic cosmic rays and high-energy protons. Because the radiation levels in space are high and solar activity is presently unpredictable, adequate shielding is needed to minimize the deleterious health effects of exposure to radiation. Today, numerous models have been developed and used to predict radiation exposure. Such a model is the Space Environment Information Systems (SPENVIS) modeling program, developed by the Belgian Institute for Space Aeronautics. SPENVIS, which has been assessed to be an excellent tool in characterizing the radiation environment for microelectronics and investigating orbital debris, is being evaluated for its usefulness with determining the dose and dose-equivalent for human exposure. Thus far, the calculations for dose-depth relations under varying shielding conditions have been in agreement with calculations done using HZETRN and PDOSE, which are well-known and widely used models for characterizing the environments for human exploratory missions. There is disagreement when assessing the impact of secondary radiation particles since SPENVIS does a crude estimation of the secondary radiation particles when calculating LET versus Flux. SPENVIS was used to model dose-depth relations for the blood-forming organs. Radiation sickness and cancer are life-threatening consequences resulting from radiation exposure. In space, exposure to radiation generally includes all of the critical organs. Biological and toxicological impacts have been included for discussion along with alternative risk mitigation

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.

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)

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)

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

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

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

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.

ICRP PUBLICATION 123: Assessment of Radiation Exposure of Astronauts in Space

International Nuclear Information System (INIS)

Dietze, G.; Bartlett, D.T.; Cool, D.A.; Cucinotta, F.A.; Jia, X.; McAulay, I.R.; Pelliccioni, M.; Petrov, V.; Reitz, G.; Sato, T.

2013-01-01

During their occupational activities in space, astronauts are exposed to ionising radiation from natural radiation sources present in this environment. They are, however, not usually classified as being occupationally exposed in the sense of the general ICRP system for radiation protection of workers applied on Earth. The exposure assessment and risk-related approach described in this report is clearly restricted to the special situation in space, and should not be applied to any other exposure situation on Earth. The report describes the terms and methods used to assess the radiation exposure of astronauts, and provides data for the assessment of organ doses. Chapter 1 describes the specific situation of astronauts in space, and the differences in the radiation fields compared with those on Earth. In Chapter 2, the radiation fields in space are described in detail, including galactic cosmic radiation, radiation from the Sun and its special solar particle events, and the radiation belts surrounding the Earth. Chapter 3 deals with the quantities used in radiological protection, describing the Publication 103 (ICRP, 2007) system of dose quantities, and subsequently presenting the special approach for applications in space; due to the strong contribution of heavy ions in the radiation field, radiation weighting is based on the radiation quality factor, Q, instead of the radiation weighting factor, w R . In Chapter 4, the methods of fluence and dose measurement in space are described, including instrumentation for fluence measurements, radiation spectrometry, and area and individual monitoring. The use of biomarkers for the assessment of mission doses is also described. The methods of determining quantities describing the radiation fields within a spacecraft are given in Chapter 5. Radiation transport calculations are the most important tool. Some physical data used in radiation transport codes are presented, and the various codes used for calculations in high

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.

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.)

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.

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.

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.

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.

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

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

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)

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)

Cytogenetic biodosimetry to estimate radiation doses received in accidental radiological exposures

International Nuclear Information System (INIS)

AIsbeih, Ghazi

2014-01-01

The tremendous applications of nuclear technologies in various aspects of life increase the probability of over exposure due to involuntary or premeditated nuclear accidents. National radiation-protection preparedness requires adequate estimate of dose received for efficient medical assistance of victims. Cytogenetic biodosimetry is an ISO and IAEA standardized biotechnology technique. We have established a reference biological dosimetry laboratory to boost the nation's ability to respond to sporadic and mass radiation casualty incidents and to assess the magnitude of radiation overexposure. Accurate calculation of radiation doses received will result in evidence based treatment decisions and better management of valuable emergency resources. It will also contribute to the 'National Radiation Protection Program' by playing a role in nuclear emergency plans. The cytogenetic method is standardized and scalable. In addition to diagnosis of over exposure, it provides triage capability for rapid stratification of patients who need more specialized medical care. It can also detect false positives and false negatives exposure particularly in cases of legal allegations

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

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

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

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

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

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

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

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)

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

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)

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.

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.)

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)

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.

High-efficiency particulate air (HEPA) filter performance following service and radiation exposure

International Nuclear Information System (INIS)

Jones, L.R.

1975-01-01

Small HEPA filters were exposed to a 60 Co source with a radiation strength of 3 x 10 7 rads per hour and then exposed to steam--air mixtures at several times filter design flow, followed by extended exposure to steam and air at reduced flow. Additional filters were exposed to air flow in a reactor confinement system and then similarly tested with steam--air mixture flows. The test data and calculated effects of filter pluggage with moisture on confinement system performance following potential reactor accidents are described. Gamma radiation exposure impaired the performance of new filters only slightly and temporarily improved performance of service aged filters. Normal confinement system service significantly impaired filter performance although not sufficiently to prevent adequate performance of the SRP confinement system following an unlikely reactor accident. Calculations based on measured filter pluggage indicate that during an accident air flow could be reduced approximately 50 percent with service-degraded HEPA filters present, or approximately 10 percent with new filters damaged by the radiation exposure. (U.S.)

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)

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

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 ...

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.)

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

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

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)

Comparison of occupational radiation dose exposures in nuclear medicine and PET

International Nuclear Information System (INIS)

White, S.A.; Binns, D.S.; Johnston, V.K.; Fawcett, M.F.; Greer, B.; Hicks, R.J.

1999-01-01

Full text: With the increasing use of high-dose 64 Ga, 201 TI and 18 F-fluorodeoxyglucose (FDG) PET for scanning in oncology in our centre, a radiation dose survey was performed to determine the impact on staff exposure in a multi-modality department. This study was set up in part to counter 'radio-phobia' (the fear of working with radioactive patients) in allied health professionals. The patients were measured using a hand-held radiation monitor at various distances and times which replicate typical patient contact scenarios in the Diagnostic Imaging Department. An average exposure rate per hour was calculated and thus the relative radiation hazard was determined for staff who will interact with the patient outside of the hot laboratory. We present our findings from the survey and the implications these have on staff radiation exposure. In conclusion, these data suggest that emerging oncologic techniques such as PET, high-dose 67 Ga and high-dose 201 Tl do not represent a significantly greater occupational radiation hazard than conventional nuclear medicine procedures

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

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

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

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

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)

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.

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.

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.

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.)

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

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

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

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)

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.)

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)

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

Shielding effect of snow cover on indoor exposure due to terrestrial gamma radiation

International Nuclear Information System (INIS)

Fujimoto, Kenzo; Kobayashi, Sadayoshi

1988-01-01

Many people in the world live in high latitude region where it snows frequently in winter. When snow covers the ground, it considerably reduces the external exposure from the radiation sources in the ground. Therefore, the evaluation of snow effect on exposure due to terrestrial gamma radiation is necessary to obtain the population dose as well as the absorbed dose in air in snowy regions. Especially the shielding effect on indoor exposure is essentially important in the assessment of population dose since most individuals spend a large portion of their time indoors. The snow effect, however, has been rather neglected or assumed to be the same both indoors and outdoors in the population dose calculation. Snow has been recognized only as a cause of temporal variation of outdoor exposure rate due firstly to radon daughters deposition with snow fall and secondly to the shielding effect of snow cover. This paper describes an approach to the evaluation of shielding effect of snow cover on exposure and introduces population dose calculation as numerical example for the people who live in wooden houses in Japan

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

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.)

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.)

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).

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

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

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

Evaluation on the Radiation Exposure of Radiation Workers in Proton Therapy

International Nuclear Information System (INIS)

Lee, Seung Hyun; Jang, Yo Jong; Kim, Tae Yoon; Jeong, Do Hyung; Choi, Gye Suk

2012-01-01

Unlike the existing linear accelerator with photon, proton therapy produces a number of second radiation due to the kinds of nuclide including neutron that is produced from the interaction with matter, and more attention must be paid on the exposure level of radiation workers for this reason. Therefore, thermoluminescence dosimeter (TLD) that is being widely used to measure radiation was utilized to analyze the exposure level of the radiation workers and propose a basic data about the radiation exposure level during the proton therapy. The subjects were radiation workers who worked at the proton therapy center of National Cancer Center and TLD Badge was used to compare the measured data of exposure level. In order to check the dispersion of exposure dose on body parts from the second radiation coming out surrounding the beam line of proton, TLD (width and length: 3 mm each) was attached to on the body spots (lateral canthi, neck, nipples, umbilicus, back, wrists) and retained them for 8 working hours, and the average data was obtained after measuring them for 80 hours. Moreover, in order to look into the dispersion of spatial exposure in the treatment room, TLD was attached on the snout, PPS (Patient Positioning System), Pendant, block closet, DIPS (Digital Image Positioning System), Console, doors and measured its exposure dose level during the working hours per day. As a result of measuring exposure level of TLD Badge of radiation workers, quarterly average was 0.174 mSv, yearly average was 0.543 mSv, and after measuring the exposure level of body spots, it showed that the highest exposed body spot was neck and the lowest exposed body spot was back (the middle point of a line connecting both scapula superior angles). Investigation into the spatial exposure according to the workers' movement revealed that the exposure level was highest near the snout and as the distance becomes distant, it went lower. Even a small amount of exposure will eventually increase

Galactic and solar radiation exposure to aircrew during a solar cycle

International Nuclear Information System (INIS)

Lewis, B.J.; Bennett, L.G.I.; Green, A.R.; McCall, M.J.; Ellaschuk, B.; Butler, A.; Pierre, M.

2002-01-01

An on-going investigation using a tissue-equivalent proportional counter (TEPC) has been carried out to measure the ambient dose equivalent rate of the cosmic radiation exposure of aircrew during a solar cycle. A semi-empirical model has been derived from these data to allow for the interpolation of the dose rate for any global position. The model has been extended to an altitude of up to 32 km with further measurements made on board aircraft and several balloon flights. The effects of changing solar modulation during the solar cycle are characterised by correlating the dose rate data to different solar potential models. Through integration of the dose-rate function over a great circle flight path or between given waypoints, a Predictive Code for Aircrew Radiation Exposure has been further developed for estimation of the route dose from galactic cosmic radiation exposure. This estimate is provided in units of ambient dose equivalent as well as effective dose, based on E/H*(10) scaling functions as determined from transport code calculations with LUIN and FLUKA. This experimentally based treatment has also been compared with the CARI-6 and EPCARD codes that are derived solely from theoretical transport calculations. Using TEPC measurements taken aboard the International Space Station, ground based neutron monitoring, GOES satellite data and transport code analysis, an empirical model has been further proposed for estimation of aircrew exposure during solar particle events. This model has been compared to results obtained during recent solar flare events. (author)

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)

Assessment of effectiveness of geologic isolation systems. ARRRG and FOOD: computer programs for calculating radiation dose to man from radionuclides in the environment

International Nuclear Information System (INIS)

Napier, B.A.; Roswell, R.L.; Kennedy, W.E. Jr.; Strenge, D.L.

1980-06-01

The computer programs ARRRG and FOOD were written to facilitate the calculation of internal radiation doses to man from the radionuclides in the environment and external radiation doses from radionuclides in the environment. Using ARRRG, radiation doses to man may be calculated for radionuclides released to bodies of water from which people might obtain fish, other aquatic foods, or drinking water, and in which they might fish, swim or boat. With the FOOD program, radiation doses to man may be calculated from deposition on farm or garden soil and crops during either an atmospheric or water release of radionuclides. Deposition may be either directly from the air or from irrigation water. Fifteen crop or animal product pathways may be chosen. ARRAG and FOOD doses may be calculated for either a maximum-exposed individual or for a population group. Doses calculated are a one-year dose and a committed dose from one year of exposure. The exposure is usually considered as chronic; however, equations are included to calculate dose and dose commitment from acute (one-time) exposure. The equations for calculating internal dose and dose commitment are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and Maximum Permissible Concentration (MPC) of each radionuclide. The radiation doses from external exposure to contaminated farm fields or shorelines are calculated assuming an infinite flat plane source of radionuclides. A factor of two is included for surface roughness. A modifying factor to compensate for finite extent is included in the shoreline calculations

Assessment of effectiveness of geologic isolation systems. ARRRG and FOOD: computer programs for calculating radiation dose to man from radionuclides in the environment

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Roswell, R.L.; Kennedy, W.E. Jr.; Strenge, D.L.

1980-06-01

The computer programs ARRRG and FOOD were written to facilitate the calculation of internal radiation doses to man from the radionuclides in the environment and external radiation doses from radionuclides in the environment. Using ARRRG, radiation doses to man may be calculated for radionuclides released to bodies of water from which people might obtain fish, other aquatic foods, or drinking water, and in which they might fish, swim or boat. With the FOOD program, radiation doses to man may be calculated from deposition on farm or garden soil and crops during either an atmospheric or water release of radionuclides. Deposition may be either directly from the air or from irrigation water. Fifteen crop or animal product pathways may be chosen. ARRAG and FOOD doses may be calculated for either a maximum-exposed individual or for a population group. Doses calculated are a one-year dose and a committed dose from one year of exposure. The exposure is usually considered as chronic; however, equations are included to calculate dose and dose commitment from acute (one-time) exposure. The equations for calculating internal dose and dose commitment are derived from those given by the International Commission on Radiological Protection (ICRP) for body burdens and Maximum Permissible Concentration (MPC) of each radionuclide. The radiation doses from external exposure to contaminated farm fields or shorelines are calculated assuming an infinite flat plane source of radionuclides. A factor of two is included for surface roughness. A modifying factor to compensate for finite extent is included in the shoreline calculations.

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

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

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

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

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

Public safety assessment of electromagnetic radiation exposure from mobile base stations.

Science.gov (United States)

Alhekail, Z O; Hadi, M A; Alkanhal, M A

2012-09-01

Exposure of the general public to electromagnetic radiation originating from randomly selected GSM/WCDMA base stations in Riyadh, Kingdom of Saudi Arabia has been assessed in the context of the International Commission on Non-Ionising Radiation Protection (ICNIRP) guidelines. The purpose of the measurement was to record the maximum power density of signals to estimate possible worst case exposure at each measurement location. These power density measurements were carried out at 60 mobile base stations located in different regions of the city. For each of these sites, three sectors were operational, yielding a total of 180 sectors. Two positions were identified per site with the greatest power density values. Exposures from these base stations were generally found to be in the range of 0.313 to 0.00000149% of the ICNIRP general public reference level, and the greatest exposure near any of the base stations was 21.96 mW m(-2) for a wideband measurement in the 75-3000 MHz frequency range. Analysis of the measured data reveals several trends for different mobile bands with respect to maximum exposure in those locations. Additionally, a simplified calculation method for the electromagnetic fields was used to compare calculated and the measured data. It was determined, on the basis of both results of the measurements and calculations carried out for these selected base stations, that members of the public would not be exposed to in excess of a small fraction of the ICNIRP guidelines at any of those sites. These are first such measurements to be made in the Middle East and provide assurance that exposures in this region of the world do not seem to be any greater than elsewhere.

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.)

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.)

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.

The assessment of radiation exposures in native American communities from nuclear weapons testing in Nevada

International Nuclear Information System (INIS)

Frohmberg, E.; Goble, R.; Sanchez, V.; Quigley, D.

2000-01-01

Native Americans residing in a broad region downwind from the Nevada Test Site during the 1950s and 1960s received significant radiation exposures from nuclear weapons testing. Because of differences in diet, activities, and housing, their radiation exposures are only very imperfectly represented in the Department of Energy dose reconstructions. There are important missing pathways, including exposures to radioactive iodine from eating small game. The dose reconstruction model assumptions about cattle feeding practices across a year are unlikely to apply to the native communities as are other model assumptions about diet. Thus exposures from drinking milk and eating vegetables have not yet been properly estimated for these communities. Through consultations with members of the affected communities, these deficiencies could be corrected and the dose reconstruction extended to Native Americans. An illustration of the feasibility of extending the dose reconstruction is provided by a sample calculation to estimate radiation exposures to the thyroid from eating radio-iodine-contaminated rabbit thyroids after the Dedan test. The illustration is continued with a discussion of how the calculation results may be used to make estimates for other tests and other locations

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.

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.

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)

REMIT5.1, Radiation exposure monitoring and information transmittal system

International Nuclear Information System (INIS)

2007-01-01

1 - Description of program or function - The Radiation Exposure Monitoring and Information Transmittal (REMIT) is a 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 Forms 4 or 5. 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 Forms 4 and 5 in paper and electronic format and can import/export data from ASCII and data base files. Additional information is available from the web page www.reirs.com. REMIT system is designed to assist U.S. Nuclear Regulatory Commission (NRC) licensees in meeting the reporting requirements of the Revised 10 CFR Parts 20.1001 through 20.2401 as outlined in Regulatory Guide 8.7, Rev.1, Instructions for Recording and Reporting Occupational Exposure Data. 2 - Methods - 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 microcuries. REMIT also estimates the amount (in micrograms) of uranium intake from the activity entered in microcuries. This calculation is based on the specific activities of the uranium isotopes. 3 - Restrictions on the complexity of the problem - None noted

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.)

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

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)

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

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.

Probability that a specific cancer and a specified radiation exposure are causally related

International Nuclear Information System (INIS)

Breitenstein, B.D.

1988-01-01

It is fundamental that a given cancer case cannot be attributed with absolute certainty to a prior ionizing radiation exposure, whatever the level of exposure. It is possible to estimate the probability of a causal relationship based on data and models that have been inferred from group statistics. Two types of information are needed to make these probability calculations: natural cancer incidence rates and risks of cancer induction from ionizing radiation. Cancer incidence rates for the United States are available in the report of the Surveillance, Epidemiology and End Results (SEER) program of the National Cancer Institute. Estimates of the risk of cancer induction from ionizing radiation have been published by the Advisory Committee on the Biological Effects of Ionizing Radiation (BEIR) of the National Academy of Sciences, the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), and the International Commission on Radiological Protection (ICRP). Using the parameters discussed above, the probability of causation formulation estimates the probability that a person who develops a particular cancer after a known quantifiable radiation exposure has the cancer as a result of the exposure. In 1985, the National Institutes of Health, responding to a U.S. Congressional mandate, published radioepidemiologic tables using the probability-of-causation method

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 (

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

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)

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.

Investigations of aircrews exposure to cosmic radiation - results, conclusions and suggestions

CERN Document Server

Bilski, P; Horwacik, T; Marczewska, B; Ochab, E; Olko, P

2002-01-01

In frame of a research project undertaken in collaboration with Polish airlines LOT, analysis of aircrews exposure to cosmic radiation has been performed. The applied methods included measurements of radiation doses with thermoluminescent detectors (MTS-N, MCP-N) and track detectors (CR-39) and also calculations of route doses with the CARI computer code. The obtained results indicate that aircrews of nearly all airplanes, with exception of these flying only on ATR aircraft, exceed regularly or may exceed in some conditions, effective doses of 1 mSv. In case of Boeing-767 aircrews such exceeding occurs always, independently of solar activity. Investigations revealed, that during these periods of the solar cycle, when intensity of cosmic radiation is high, exceeding of 6 mSv level is also possible. These results indicate, that according to Polish and European regulations it is necessary for airlines to provide regular estimations of radiation exposure of aircrews. Basing on the obtained results a system for pe...

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)

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

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

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)

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

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.

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

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.

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.)

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

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.

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)

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)

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

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

Radiation exposure dose on persons engaged in radiation-related industries in Korea

International Nuclear Information System (INIS)

Lim, Bong Sik

2006-01-01

This study investigated the status of radiation exposure doses since the establishment of the 'Regulations on Safety Management of Diagnostic Radiation Generation Device' in January 6, 1995. The level of radiation exposure in people engaged or having been engaged in radiation-related industries of inspection organizations, educational organization, military units, hospitals, public health centers, businesses, research organizations or clinics over a 5 year period from Jan. 1, 2000 to Dec. 31, 2004 was measured. The 149,205 measurement data of 57,136 workers registered in a measurement organization were analysed in this study. Frequency analysis, a Chi-square test, Chi-square trend test, and ANOVA was used for data analysis. Among 57,136 men were 40,870 (71.5%). 50.3% of them were radiologic technologists, otherwise medical doctors (22.7%), nurse (2.9%) and others (24.1%). The average of depth radiation and surface radiation during the 5-year period were found to decrease each year. Both the depth radiation and surface radiation exposure were significantly higher in males, in older age groups, in radiological technologists of occupation. The departments of nuclear medicine had the highest exposure of both depth and surface radiation of the divisions of labor. There were 1.98 and 2.57 per 1,000 person-year were exposed more than 20 mSv (limit recommended by International Commission on Radiological Protection) in depth and surface radiation consequently. The total exposure per worker was significantly decreased by year. But Careful awareness is needed for the workers who exposed over 20 mSv per year. In order to minimize exposure to radiation, each person engaged in a radiation-related industry must adhere to the individual safety management guidelines more thoroughly. In addition, systematic education and continuous guidance aimed at increasing the awareness of safety must be provided

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.

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.

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

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)

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

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

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.

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).

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)

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)

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)

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

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

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

International Nuclear Information System (INIS)

1986-12-01

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

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)

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.)

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

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

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)

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.)

Safety of natural radiation exposure. A meta-analysis of epidemiological studies on natural radiation

International Nuclear Information System (INIS)

Osaki, S.

2000-01-01

People have been exposed every time and everywhere to natural radiation and ''intuitively'' know the safety of this radiation exposure. On the other hand the theory of no threshold value on radiological carcinogenesis is known widely, and many people feel danger with even a smallest dose of radiation exposure. The safety of natural radiation exposure can be used for the risk communication with the public. For this communication, the safety of natural radiation exposure should be proved ''scientifically''. Safety is often discussed scientifically as the risks of the mortality from many practices, and the absolute risks of safe practices on the public are 1E-5 to 1E-6. The risks based on the difference of natural radiation exposure on carcinogenesis have been analyzed by epidemiological studies. Much of the epidemiological studies have been focused on the relationship between radiation doses and cancer mortalities, and their results have been described as relative risks or correlation factors. In respect to the safety, however, absolute risks are necessary for the discussion. Cancer mortalities depend not only on radiation exposure, but also on ethnic groups, sexes, ages, social classes, foods, smoking, environmental chemicals, medical radiation, etc. In order to control these confounding factors, the data are collected from restricted groups or/and localities, but any these ecological studies can not perfectly compensate the confounding factors. So positive or negative values of relative risks or the meaningful correlation factors can not be confirmed that their values are derived originally from the difference of their exposure doses. The absolute risks on these epidemiological studies are also affected by many factors containing radiation exposure. The absolute risk or the upper value of the confidence limit obtained from the epidemiological study which is well regulated confounding factors is possible to be a maximum risk on the difference of the exposure doses

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.

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.

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

Dosemetry for exposures to cosmic radiation in civilian aircraft - Part 1: Conceptual basis for measurements

International Nuclear Information System (INIS)

2006-01-01

Aircraft crew are exposed to elevated levels of cosmic radiation of galactic and solar origin and secondary radiation produced in the atmosphere, the aircraft structure and its contents. Following recommendations of the International Commission on Radiological Protection in Publication 60, the European Union (EU) introduced a revised Basic Safety Standards Directive, which included exposure to natural sources of ionizing radiation, including cosmic radiation, as occupational exposure. The Directive requires account to be taken of the exposure of aircraft crew liable to receive more than 1 mSv per year. It then identifies the following four protection measures: (i) to assess the exposure of the crew concerned; (ii) to take into account the assessed exposure, when organizing working schedules with a view to reducing the doses of highly exposed crew; (iii) to inform the workers concerned of the health risks their work involves; and (iv) to apply the same special protection during pregnancy to female crew in respect of the 'child to be born' as to other female workers. The EU Council Directive has already been incorporated into laws and regulations of EU Member States and is being included in the aviation safety standards and procedures of the Joint Aviation Authorities and the European Air Safety Agency. For regulatory and legislative purposes, the radiation protection quantities of interest are equivalent dose (to the foetus) and effective dose. The cosmic radiation exposure of the body is essentially uniform and the maternal abdomen provides no effective shielding to the foetus. As a result, the magnitude of equivalent dose to the foetus can be put equal to that of the effective dose received by the mother. Doses on board aircraft are generally predictable, and events comparable to unplanned exposure in other radiological workplaces cannot normally occur (with the rare exceptions of extremely intense and energetic solar particle events). Personal dosemeters for

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

International Nuclear Information System (INIS)

Lowder, W.M.; Hajnal, F.

1992-01-01

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

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

Physician exposure to ionizing radiation during trauma resuscitation: A prospective clinical study

International Nuclear Information System (INIS)

Weiss, E.L.; Singer, C.M.; Benedict, S.H.; Baraff, L.J.

1990-01-01

A prospective study of emergency physician whole body and extremity exposure to ionizing radiation during trauma resuscitation over a three-month period was conducted. Radiation film badges and thermoluminescent dosimeter finger rings were permanently attached to leaded aprons worn by emergency medicine residents during all trauma resuscitations. One set of apron and finger ring dosimeters was designated for the resident who managed the airway and stabilized the neck, when necessary, during cervical spine radiography (A-CS resident). A separate set of dosimeters was designated for the resident supervising the resuscitation. During the study period, 150 major trauma patients requiring 481 radiographic studies were treated. The mean monthly cumulative whole body exposures were 136.7 +/- 85.0 and 103.3 +/- 60.3 mrem for A-CS and supervising residents, respectively. The mean weekly cumulative extremity exposures were 523.3 +/- 611.0 and 46.7 +/- 18.6 mrem for A-CS and supervising residents, respectively. Calculated whole body exposures per patient were 2.7 mrem for the A-CS resident and 2.1 mrem for the supervising resident. Calculated extremity exposures per patient were 41.9 +/- 48.9 and 3.7 +/- 1.5 mrem, respectively. To exceed the annual whole body exposure limit established by the National Council of Radiologic Protection, the A-CS resident, working 200 shifts per year, would have to treat 9.2 trauma patients per shift. To exceed the annual extremity exposure limit, the A-CS resident would have to treat 5.9 trauma patients per shift. Of note, European exposure limits are 10% of current US limits. We conclude that significant exposures may occur to physicians working in trauma centers and that the use of shielding devices is indicated

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.

Summary of ionizing radiation analysis on the Long Duration Exposure Facility

Science.gov (United States)

Parnell, T. A.

1992-01-01

The ionizing radiation measurements flown on the Long Duration Exposure Facility (LDEF) were contained in 15 experiments which utilized passive detectors to pursue objectives in astrophysics and to measure the radiation environment and dosimetric quantities. The spacecraft structure became sufficiently radioactive to permit additional important studies. The induced activity allows extensive radiation mapping in the structure, and independent comparison with experiment dosimetric techniques, and significant studies of secondary effects. The long exposure time, attitude stability, and number and types of measurements produced a unique and critical set of data for low Earth orbit that will not be duplicated for more than a decade. The data allow an unprecedented test, and improvement if required, of models of the radiation environment and the radiation transport methods that are used to calculate the internal radiation and its effects in spacecraft. Results of measurements in the experiments, as well as from radioactivity in the structure, have clearly shown effects from the directional properties of the radiation environment, and progress was made in the dosimetric mapping of LDEF. These measurements have already influenced some Space Station Freedom design requirements. Preliminary results from experiments, reported at this symposium and in earlier papers, show that the 5.8 years exposure considerably enhanced the scientific return of the radiation measurements. The early results give confidence that the experiments will make significant advances in the knowledge of ultra heavy cosmic rays, anomalous cosmic rays, and heavy ions trapped in the radiation belts. Unexpected phenomena were observed, which require explanation. These include stopping iron group ions between the energy ranges anticipated for anomalous and galactic cosmic rays in the LDEF orbit. A surprising concentration of the Be-7 nuclide was discovered on the 'front' surface of LDEF, apparently

Radiation exposure rate and liquid level measurement inside a high level liquid waste (HLLW) storage tank

International Nuclear Information System (INIS)

Sur, B.; Yue, S.; Thekkevarriam, A.

2007-01-01

An instrument based on an inexpensive, small silicon diode has been developed and used to measure, for the first time, the gamma radiation exposure rate profile inside a 6.4 mm diameter reentrant thermo-well tube, immersed in the highly radioactive liquid solution in an HLLW storage tank. The measurement agrees with previous calculations of exposure rate, and provides confirmation for safe and effective radiation work plans and material selection for investigations and remediation of the storage tank facility. The measured radiation exposure rate profile is also used to confirm that the position of tank internal structures have not changed because of aging and corrosion, and to obtain, within a few mm, the level of liquid inside the tank. (author)

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.

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...

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.

Construction of a computational exposure model for dosimetric calculations using the EGS4 Monte Carlo code and voxel phantoms

International Nuclear Information System (INIS)

Vieira, Jose Wilson

2004-07-01

The MAX phantom has been developed from existing segmented images of a male adult body, in order to achieve a representation as close as possible to the anatomical properties of the reference adult male specified by the ICRP. In computational dosimetry, MAX can simulate the geometry of a human body under exposure to ionizing radiations, internal or external, with the objective of calculating the equivalent dose in organs and tissues for occupational, medical or environmental purposes of the radiation protection. This study presents a methodology used to build a new computational exposure model MAX/EGS4: the geometric construction of the phantom; the development of the algorithm of one-directional, divergent, and isotropic radioactive sources; new methods for calculating the equivalent dose in the red bone marrow and in the skin, and the coupling of the MAX phantom with the EGS4 Monte Carlo code. Finally, some results of radiation protection, in the form of conversion coefficients between equivalent dose (or effective dose) and free air-kerma for external photon irradiation are presented and discussed. Comparing the results presented with similar data from other human phantoms it is possible to conclude that the coupling MAX/EGS4 is satisfactory for the calculation of the equivalent dose in radiation protection. (author)

Exposure to the atmospheric ionizing radiation environment: a study on Italian civilian aviation flight personnel

International Nuclear Information System (INIS)

De Angelis, G.; Caldora, M.; Santaquilani, M.; Scipione, R.; Verdecchia, A.

2003-01-01

A study of the effects of high-LET, low-dose and low-dose-rate ionizing radiation and associated risk analysis is underway. This study involves analyzing the atmospheric ionizing radiation exposure (including high-energy neutrons) and associated effects for members of civilian aviation flight personnel, in an attempt to better understand low-dose long-term radiation effects on human subjects. The study population includes all Italian civilian airline flight personnel, both cockpit and cabin crew members, whose work history records and actual flights (route, aircraft type, and date for each individual flight for each person where possible) are available. The dose calculations are performed along specific flight legs, taking into account the actual flight profiles for all different routes and the variations with time of solar and geomagnetic parameters. Dose values for each flight are applied to the flight history of study participants in order to estimate the individual annual and lifetime occupational radiation dose. An update of the study of the physical atmospheric ionizing radiation exposure is given here, in terms of environmental modeling, flight routes, radiation dose evaluation along different flight paths, and exposure matrix construction. The exposure analysis is still in progress, and the first results are expected soon

An observation study of radiation exposure to nurses during interventional radiology procedure

International Nuclear Information System (INIS)

Komemushi, Atsushi; Tanigawa, Noboru; Aoki, Atsuko

2010-01-01

The purpose of this study was to prospectively measure the level of radiation exposure among nursing staff during interventional radiology procedures. All interventional radiology procedures performed at our institution between April 20 and June 19, 2009 were included in this study. Radiation exposure was measured as the equivalent dose penetrating tissue to a depth of 10 mm using electronic personal dosimeters attached outside (Ha) and inside (Hb) lead aprons. Effective dose (HE) was estimated by calculating from Ha and Hb. In total, data from 68 procedures were included in this study. Four nurses performed 71 nursing cares. The mean Ha was 0.70±1.0 μSv, while the mean Hb was 0.06±0.2 μSv. The mean HE was 0.14±0.3 μSv. The present findings indicate that during interventional radiology procedures, nurses were exposed to very low levels of radiation. (author)

Radiation exposure and disease questionnaires of early entrants after the Hiroshima bombing

International Nuclear Information System (INIS)

Imanaka, T.; Endo, S.; Kawano, N.; Tanaka, K.

2012-01-01

It is popularly known that people who entered into the ground-zero area shortly after the atomic bombings in Hiroshima and Nagasaki suffered from various syndromes similar to acute radiation effects. External exposures from neutron-induced radionuclides in soil have recently been reassessed based on DS02 calculations as functions of both distance from the hypo-centres and elapsed time after the explosions. Significant exposure due to induced radiation can be determined for those who entered the area within 1000 m from the hypo-centres shortly after the bombing. Although it was impossible to track the action of each of the survivors over the days or weeks following the bombings in order to make reliable dose estimates for their exposures to soil activation or fallout, four individuals among those early entrants were investigated here to describe useful information of what happened shortly after the bombing. (authors)

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.)

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)

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)

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

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.

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)

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

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.

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

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

Occupational radiation exposure in the GDR in 1978

International Nuclear Information System (INIS)

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

1980-01-01

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

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)

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.

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

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

International Nuclear Information System (INIS)

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

2003-01-01

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

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 ...

Radiation and health: low-level-ionizing radiation exposure and effects

International Nuclear Information System (INIS)

Kant, Krishan

2013-01-01

In the present paper, brief review of the available literature, data and reports of various radiation exposure and protection studies is presented. An in-depth analysis of reports available suggests that the possible beneficial outcomes of exposure to LLIR are: increased Growth rate, Development, Neurogenesis, Memory, Fecundity (Fertility), Immunity (Resistance to diseases due to large doses of radiation) and Lifespan (Longevity) Decreased Cancer deaths, Cardiovascular deaths, Respiratory deaths, Neonatal deaths, Sterility, Infection, Premature deaths. The findings also suggest that the LNT theory is overly stated for assessing carcinogenic risks at low doses. It is not scientifically justified and should be banned as it creates radio phobia thereby blocking the efforts to supply reliable, environmentally friendly nuclear energy and important medical therapies. There is no need for anyone to live in fear of serious health consequences from the radioactivity that comes out from nuclear installations and exposures in the range of background radiation. A linear quadratic model has been given illustrating the validity of radiation hormesis, besides the comparison of the dose rates arising from natural and manmade sources to Indian population

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.)

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)

The risks of leukaemia and other cancers in Seascale from radiation exposure

International Nuclear Information System (INIS)

Stather, J.W.; Dionian, J.; Brown, J.; Fell, T.P.; Muirhead, C.R.

1986-04-01

Including new data in the radiation dose calculations for the Seascale study population of 1225 children and young persons, followed to 20 years of age or 1980, has, with modifications to dosimetric models, increased the predicted number of radiation-induced leukaemia resulting from Sallafield discharges from 0.01 to 0.016. Risk to the average child in the study, from the discharges, is now calculated as about 1 in 75,000 with a maximum risk of about 1 in 30,000 for children born in the mid-1950s. For the four fatal leukemias to be attributed to the Sellafield operations, the calculated average risk for all the children would have to be increased about 250 times. Estimate of the overall risk of radiation-induced leukaemia in the study population, from combined sources, has increased by less than 10% of the previous estimate and the total number of cases is still rounded to 0.1, as in R171. Risk to the average child is now calculated as about 1 in 12,250, about two thirds from natural background, 16% from Sellafield discharges, and 9% each from weapons fallout and medical exposure. (U.K.)

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 ...

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

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.)

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.)

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

Understanding of radiation protection in medicine. Pt. 1. Knowledge about radiation exposure and anxiety about radiation injury

International Nuclear Information System (INIS)

Iida, Hiroji; Yamamoto, Tomoyuki; Shimada, Yasuhiro

1997-01-01

Using a questionnaire we investigated whether radiation exposure in correctly understood by medical doctors (n=140), nurses (n=496) and the general public (n=236). Thirty-three percent of medical doctors, 53% of nurses and the general public did not know who is legally allowed to irradiate the human body. Forty-five percent of doctors, 63% of nurses and 48% of the general public complained of anxiety about radiation injury. Fifty-six percent of patients did not ask medical doctors or nurses for an explanation of the risk of exposure. Moreover, 64% of doctors did not explain the risk to patients. In addition, 21% of doctors, 46% of nurses and the general public incorrectly understood that x-rays remain in the examination room. Twenty-seven percent of doctors, 49% of nurses and 80% of the general public did not know the t en-day rule . In conclusion, the results of this questionnaire indicated that basic knowledge about radiation exposure was not adequate. To protect against medical radiation exposure, personnel who are licensed to irradiate to the human body should be well recognized by medical staff and the general public. It is also important that informed consent for radiological examinations be based on fundamental knowledge about radiation exposure. Therefore, to reach a general consensus on radiological examinations and to reduce individual exposure, general public education regarding radiation protection is required. Postgraduate education on radiation protection for medical doctors and nurses is also strongly recommended. (author)

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

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

Occupational radiation exposure in nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1979-01-01

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

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

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

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

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.

Radiation risk from terrestrial exposure for population in cities of Serbia

International Nuclear Information System (INIS)

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

2007-01-01

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

An overview of measuring and modelling dose and risk from ionising radiation for medical exposures

International Nuclear Information System (INIS)

Tootell, Andrew; Szczepura, Katy; Hogg, Peter

2014-01-01

Purpose: This paper gives an overview of the methods that are used to calculate dose and risk from exposure to ionizing radiation as a support to other papers in this special issue. Background: The optimization of radiation dose is a legal requirement in medical exposures. This review paper aims to provide the reader with knowledge of dose by providing definitions and concepts of absorbed, effective and equivalent dose. Criticisms of the use of effective dose to infer the risk of an exposure to an individual will be discussed and an alternative approach considering the lifetime risks of cancer incidence will be considered. Prior to any dose or risk calculation, data concerning the dose absorbed by the patient needs to be collected. This paper will describe and discuss the main concepts and methods that can be utilised by a researcher in dose assessments. Concepts behind figures generated by imaging equipment such as dose-area-product, computed tomography dose index, dose length product and their use in effective dose calculations will be discussed. Processes, advantages and disadvantages in the simulation of exposures using the Monte Carlo method and direct measurement using digital dosimeters or thermoluminescent dosimeters will be considered. Beyond this special issue, it is proposed that this paper could serve as a teaching or CPD tool for personnel working or studying medical imaging

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

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.

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)

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.

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.

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)

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)

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)

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

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

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

Evaluation of secondary exposure doses to transportation and medical personnel in the radiation emergency medicine

International Nuclear Information System (INIS)

Kato, Hideki; Suzuki, Shoichi; Koga, Sukehiko; Mukoyama, Takashi; Tomatsu, Hirotaka; Suzuki, Yusuke

2009-01-01

Radionuclide contamination is one of the accidents that might occur while carrying out a periodical inspection of nuclear power stations during normal reactor operation. When such an accident occurs, rescue and medical personnel, involved in transporting and treating affected workers run the risk of exposure to secondary radiation. In this study, the ambient dose equivalent rate at a certain distance from the surface of the human body contaminated with typical radioactive corrosion products was calculated. Further, the relationships among the adhesion area, contamination density, and secondary exposure dose were clarified. The secondary exposure dose and permissible working hours in a radiation emergency medicine were estimated by presenting these relationships in the form of a chart and by specifying the contamination levels. (author)

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)

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...

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

Effective doses and standardised risk factors from paediatric diagnostic medical radiation exposures: Information for radiation risk communication

International Nuclear Information System (INIS)

Bibbo, Giovanni

2018-01-01

In the paediatric medical radiation setting, there is no consistency on the radiation risk information conveyed to the consumer (patient/carer). Each communicator may convey different information about the level of risk for the same radiation procedure, leaving the consumer confused and frustrated. There is a need to standardise risks resulting from medical radiation exposures. In this study, paediatric radiographic, fluoroscopic, CT and nuclear medicine examination data have been analysed to provide (i) effective doses and radiation induced cancer risk factors from common radiological and nuclear medicine diagnostic procedures in standardised formats, (II) awareness of the difficulties that may be encountered in communicating risks to the layperson, and (iii) an overview of the deleterious effects of ionising radiation so that the risk communicator can convey with confidence the risks resulting from medical radiation exposures. Paediatric patient dose data from general radiographic, computed tomography, fluoroscopic and nuclear medicine databases have been analysed in age groups 0 to <5 years, 5 to <10 years, 10 to <15 years and 15 to <18 years to determine standardised risk factors. Mean, minimum and maximum effective doses and the corresponding mean lifetime risks for general radiographic, fluoroscopic, CT and nuclear medicine examinations for different age groups have been calculated. For all examinations, the mean lifetime cancer induction risk is provided in three formats: statistical, fraction and category. Standardised risk factors for different radiological and nuclear medicine examinations and an overview of the deleterious effects of ionising radiation and the difficulties encountered in communicating the risks should facilitate risk communication to the patient/carer.

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.

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

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.

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.

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

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)

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

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

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.

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

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)

Radiation in complex exposure situations. Assessing health risks at low levels from concomitant exposures to radiation and chemicals

International Nuclear Information System (INIS)

Hornhardt, S.; Jung, T.; Burkart, W.

2000-01-01

Health effects from exposures to ionizing radiation are in general the result of complex multi-step reaction chains involving changes and responses on the level of molecules, cells, tissues and organisms. In environmental low dose exposure situations ionizing radiation only contributes a small fraction to the life-long attack on DNA by other exogenous and endogenous genotoxins. Nevertheless, efforts to assess and quantify deleterious effects at low exposure levels are directed mainly towards radiation as a single isolated agent, and rarely towards the concomitant presence of other natural and anthropogenic toxicants. Only these combined exposures may lead to observable health risk effects. In addition they might differ from those expected from simple addition of the individual risks due to interaction. The existing data base on combined effects is rudimentary, mainly descriptive and rarely covers exposure ranges large enough to make direct inferences to present day low dose exposure situations. Therefore, any risk assessment will have to consider the question whether combined effects, i.e. interaction between two or more agents will influence the health outcome from specific exposure situations in such a way that predictions derived from simple standard exposure situations would have to be revised. In view of the multitude of possible interactions between the large number of potentially harmful agents in the human environment, descriptive approaches will have to be supplemented by the use of mechanistic models for critical health endpoints such as cancer. Agents will have to be grouped depending on their physical or chemical mode of action at the molecular and cellular level, to generalize and predict the outcome of combined exposures at low exposure levels and the possibility of interactions. (author)

Radiation exposure of operator during various interventional procedures

International Nuclear Information System (INIS)

Yu, In Kyu; Chung, Jin Wook; Han, Joon Koo; Park, Jae Hyung; Kang, Wee Saing

1994-01-01

To investigate the levels of radiation exposure of an operator which may be influenced by the wearing an apron, type of procedure, duration of fluoroscopy and operator's skill during various interventional procedures. Radiation doses were measured both inside and outside the apron(0.5 mm lead equivalent) of the operator by a film badge monitoring method and the duration of fluoroscopy was measured in 96 procedures prospectively. The procedures were 30 transcatheter arterial embolization (TAE), 25 percutaneous transhepatic biliary drainages (PTBD), 16 stone removals (SR), 15 percutaneous needle aspirations (PNCA) and 10 percutaneous nephrostomies(PCN). To assess the difference of exposure by the operator's skill, the procedures of TAE and PTBD were done separately by groups of staffs and residents. Average protective effect of the apron was 72.8%. Average radiation exposure(unit: μ Sv/procedure was 23.3 in PTBD by residents, 10.0 in PTBD by staffs, 10.0 in SR, 8.7 in TAE by residents, 7.3 in TAE by staffs, 9.0 in PCN and 6.0 in PCNA. Average radiation exposure of residents were 1.9 times greater than those of staffs. Radiation exposure was not proportionally related to the duration of fluoroscopy, but influenced by wearing an apron, various types of procedure and operator's skills

Construction of computational program of aging in insulating materials for searching reversed sequential test conditions to give damage equivalent to simultaneous exposure of heat and radiation

International Nuclear Information System (INIS)

Fuse, Norikazu; Homma, Hiroya; Okamoto, Tatsuki

2013-01-01

Two consecutive numerical calculations on degradation of polymeric insulations under thermal and radiation environment are carried out to simulate so-called reversal sequential acceleration test. The aim of the calculation is to search testing conditions which provide material damage equivalent to the case of simultaneous exposure of heat and radiation. At least following four parameters are needed to be considered in the sequential method; dose rate and exposure time in radiation, as well as temperature and aging time in heating. The present paper discusses the handling of these parameters and shows some trial calculation results. (author)

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

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)

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)

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

Biological Dosimetry Using Micronucleus Assay in Simulated Partial-Body Exposure to Ionizing Radiation

Directory of Open Access Journals (Sweden)

S. Purnami

2017-08-01

Full Text Available In radiation accidents, it is common that only several parts of the body are exposed to radiation. As a consequence there is a mixture of exposed and unexposed lymphocytes in peripheral blood cells of the samples. This phenomenon will cause the dose value estimated using the exposed lymphocytes to be lower than the actual dose. In this study, an assessment of partial body exposures using micronucleus assay by estimating the partial body dose and fraction of irradiated blood was conducted. An optimal D0 value also has been determined in this study to estimate the fraction of irradiated cells. Peripheral blood lymphocytes (PBLs from three healthy donors were irradiated in vitro with 2 Gy of X-rays. Partial radiation exposure was simulated by mixing the irradiated and non-irradiated blood in different proportions. The proportions of mixtures of blood samples irradiated in vitro were 5, 10, 15, 20, and 30 %. Blood samples were then cultured and harvested based on micronuclei assay protocol. At least 2000 binucleated cells with well-preserved cytoplasm were scored for the MN frequency. Dose Estimate 5.1 software was used to calculate the dispersion index (σ2/y and normalized unit of this index (U in each proportion of bloods. The fractions of irradiated cells were calculated with CABAS (Chromosomal Aberration Calculation Software for several different D0 values (2.7; 3.8; 5.4. The results showed that D0 value at 5.4 gave the closest results to the actual proportion of irradiated bloods, while for the dose estimation the estimated doses value from all proportions in all donors were higher than the actual dose. The factor that may cause this phenomenon was that the dose response calibration curve used to predict the radiation dose was not constructed in the laboratory used. Overall it can be concluded that a biodosimetry using MN assay can be used to estimate the radiation dose in partial body exposure. In order to establish a biodosimetry using MN

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-04-15

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

Aircrew Exposure To Cosmic Radiation Evaluated By Means Of Several Methods; Results Obtained In 2006

International Nuclear Information System (INIS)

Ploc, Ondrej; Spurny, Frantisek; Jadrnickova, Iva; Turek, Karel

2008-01-01

Routine evaluation of aircraft crew exposure to cosmic radiation in the Czech Republic is performed by means of calculation method. Measurements onboard aircraft work as a control tool of the routine method, as well as a possibility of comparison of results measured by means of several methods. The following methods were used in 2006: (1) mobile dosimetry unit (MDU) type Liulin--a spectrometer of energy deposited in Si-detector; (2) two types of LET spectrometers based on the chemically etched track detectors (TED); (3) two types of thermoluminescent detectors; and (4) two calculation methods. MDU represents currently one of the most reliable equipments for evaluation of the aircraft crew exposure to cosmic radiation. It is an active device which measures total energy depositions (E dep ) in the semiconductor unit, and, after appropriate calibration, is able to give a separate estimation for non-neutron and neutron-like components of H*(10). This contribution consists mostly of results acquired by means of this equipment; measurements with passive detectors and calculations are mentioned because of comparison. Reasonably good agreement of all data sets could be stated

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

Overview of the hazards of low-level exposure to radiation

International Nuclear Information System (INIS)

Ritenour, E.R.

1984-01-01

In this chapter the authors are concerned with low-level radiation, doses of ionizing radiations that are ten to thousands of times smaller than those required to contract ARS. Low-level radiation may be defined as an absorbed dose of 10 rem or less delivered over a short period of time. A larger dose delivered over a long period of time, for instance, 50 rem in 10 years, may also be considered low level. The definition is purposely loose so as to cover a wide variety of sources of radiation exposure, such as natural background (100 mrem/year) occupational exposures (<5 rem/year), and medical applications, such as diagnostic radiography (<1 rem). Low-level radiation exposure does not produce ARS. The health effects that may be of concern in regard to low-level radiation are its long-term sequelae. Studies of survivors of high-level radiation exposure (both human and laboratory animals) have indicated that there are three health effects that should be examined at low levels of exposure: induction of cancer, birth abnormalities (from irradiation in utero), and genetic effects. No other long-term effects of low-level exposure have been conclusively demonstrated in animals or humans

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

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

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.

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

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.

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.

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)

Occupational radiation exposure in work with radioactive materials

International Nuclear Information System (INIS)

Georgiev, G.V.

1975-01-01

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

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)

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

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.

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.

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)

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

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.)

Contribution to a comparative environmental impact assessment for radiation exposure from the use of coal and nuclear energy for electricity generation

International Nuclear Information System (INIS)

Halbritter, G.; Braeutigam, K.R.; Fluck, F.W.; Lessmann, E.; Neumann-Hauf, G.

1982-01-01

The emissions from a model coal unit and from all relevant stages of a model nuclear fuel cycle (PWR) were compiled. For assessing radiation exposure a comparison of the model coal unit and the nuclear fuel cycle on the basis of local and collective exposure values was performed. A risk-specific comparison can only be made on the basis of collective dose commitment calculations. The collective dose equivalents for German siting and licensing conditions were made on the basis of results presented by UNSCEAR. These calculations comprise local, regional, and global expositions for the plants under normal operation. The estimates show a reduction of the collective dose equivalent for the nuclear fuel cycle from about 40 (gonads) to about 20 (effective) person-Sv/(GWe x a); for the coal-fired unit the estimates yield 4 (effective) as compared to 0.6 (gonads) person-Sv/(GWe x a) in the UNSCEAR report. A great part of the radiation exposure from the nuclear fuel cycle is caused by the global exposure of carbon-14, building up over the regarded exposure time of 500 years. On the local and regional scale, the radiation exposure due to the emissions from coal-fired units is comparable to the non-occupational radiation exposure from all relevant stages of the nuclear fuel cycle at normal operation. For a comprehensive risk estimate of the nuclear fuel cycle also accidental radiation exposure must be considered. Normal operation and accidental risk are compared on the detriment level, showing that the risk contribution from accidents is about twice that from normal operation. (orig./HP) [de

World high background natural radiation areas: Need to protect public from radiation exposure

International Nuclear Information System (INIS)

Sohrabi, Mehdi

2013-01-01

Highlights of findings on radiological measurements, radiobiological and epidemiological studies in some main world high background natural radiation (HBNR) areas such as in Brazil, China, India and Iran are presented and discussed with special regard to remediation of radiation exposure of inhabitants in such areas. The current radiation protection philosophy and recommendations applied to workers and public from operation of radiation and nuclear applications are based on the linear non-threshold (LNT) model. The inhabitants of HBNR and radon prone areas receive relatively high radiation doses. Therefore, according to the LNT concept, the inhabitants in HBNR areas and in particular those in Ramsar are considered at risk and their exposure should be regulated. The HBNR areas in the world have different conditions in terms of dose and population. In particular, the inhabitants in HBNR areas of Ramsar receive very high internal and external exposures. This author believes that the public in such areas should be protected and proposes a plan to remedy high exposure of the inhabitants of the HBNR areas of Ramsar, while maintaining these areas as they stand to establish a national environmental radioactivity park which can be provisionally called “Ramsar Research Natural Radioactivity Park” (RRNRP). The major HBNR areas, the public exposure and the need to remedy exposures of inhabitants are reviewed and discussed. - Highlights: ► Highlights of findings on studies in HBNR areas are reviewed and discussed. ► The need to protect HBNR area inhabitants and remedy public exposure is emphasized. ► A collective approach is proposed to remedy exposure of Ramsar HBNR area inhabitants. ► Relocation of HBNR area inhabitants and establishing a park at the location is proposed. ► The advantages and disadvantages of the methods are discussed and recommendations are made

Assessing the health effects associated with occupational radiation exposure in Korean radiation workers: protocol for a prospective cohort study.

Science.gov (United States)

Seo, Songwon; Lim, Wan Young; Lee, Dal Nim; Kim, Jung Un; Cha, Eun Shil; Bang, Ye Jin; Lee, Won Jin; Park, Sunhoo; Jin, Young Woo

2018-03-30

The cancer risk of radiation exposure in the moderate-to-high dose range has been well established. However, the risk remains unclear at low-dose ranges with protracted low-dose rate exposure, which is typical of occupational exposure. Several epidemiological studies of Korean radiation workers have been conducted, but the data were analysed retrospectively in most cases. Moreover, groups with relatively high exposure, such as industrial radiographers, have been neglected. Therefore, we have launched a prospective cohort study of all Korean radiation workers to assess the health effects associated with occupational radiation exposure. Approximately 42 000 Korean radiation workers registered with the Nuclear Safety and Security Commission from 2016 to 2017 are the initial target population of this study. Cohort participants are to be enrolled through a nationwide self-administered questionnaire survey between 24 May 2016 and 30 June 2017. As of 31 March 2017, 22 982 workers are enrolled in the study corresponding to a response rate of 75%. This enrolment will be continued at 5-year intervals to update information on existing study participants and recruit newly hired workers. Survey data will be linked with the national dose registry, the national cancer registry, the national vital statistics registry and national health insurance data via personal identification numbers. Age-specific and sex-specific standardised incidence and mortality ratios will be calculated for overall comparisons of cancer risk. For dose-response assessment, excess relative risk (per Gy) and excess absolute risk (per Gy) will be estimated with adjustments for birth year and potential confounders, such as lifestyle factors and socioeconomic status. This study has received ethical approval from the institutional review board of the Korea Institute of Radiological and Medical Sciences (IRB No. K-1603-002-034). All participants provided written informed consent prior to enrolment. The findings

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.

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.)

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)

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

The calculation of dose from external photon exposures using reference human phantoms and Monte Carlo methods. Pt. 7. Organ doses due to parallel and environmental exposure geometries

Energy Technology Data Exchange (ETDEWEB)

Zankl, M. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Drexler, G. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Petoussi-Henss, N. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Saito, K. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

1997-03-01

This report presents a tabulation of organ and tissue equivalent dose as well as effective dose conversion coefficients, normalised to air kerma free in air, for occupational exposures and environmental exposures of the public to external photon radiation. For occupational exposures, whole-body irradiation with idealised geometries, i.e. broad parallel beams and fully isotropic radiation incidence, is considered. The directions of incidence for the parallel beams are anterior-posterior, posterior-anterior, left lateral, right lateral and a full 360 rotation around the body`s longitudinal axis. The influence of beam divergence on the body doses is also considered as well as the dependence of effective dose on the angle of radiation incidence. Regarding exposure of the public to environmental sources, three source geometries are considered: exposure from a radioactive cloud, from ground contamination and from the natural radionuclides distributed homogeneously in the ground. The precise angular and energy distributions of the gamma rays incident on the human body were taken into account. The organ dose conversion coefficients given in this catalogue were calculated using a Monte Carlo code simulating the photon transport in mathematical models of an adult male and an adult female, respectively. Conversion coefficients are given for the equivalent dose of 23 organs and tissues as well as for effective dose and the equivalent dose of the so-called `remainder`. The organ equivalent dose conversion coefficients are given separately for the adult male and female models and - as arithmetic mean of the conversion coefficients of both - for an average adult. Fitted data of the coefficients are presented in tables; the primary raw data as resulting from the Monte Carlo calculation are shown in figures together with the fitted data. (orig.)

The calculation of dose from external photon exposures using reference human phantoms and Monte Carlo methods. Pt. 7. Organ doses due to parallel and environmental exposure geometries

International Nuclear Information System (INIS)

Zankl, M.

1997-03-01

This report presents a tabulation of organ and tissue equivalent dose as well as effective dose conversion coefficients, normalised to air kerma free in air, for occupational exposures and environmental exposures of the public to external photon radiation. For occupational exposures, whole-body irradiation with idealised geometries, i.e. broad parallel beams and fully isotropic radiation incidence, is considered. The directions of incidence for the parallel beams are anterior-posterior, posterior-anterior, left lateral, right lateral and a full 360 rotation around the body's longitudinal axis. The influence of beam divergence on the body doses is also considered as well as the dependence of effective dose on the angle of radiation incidence. Regarding exposure of the public to environmental sources, three source geometries are considered: exposure from a radioactive cloud, from ground contamination and from the natural radionuclides distributed homogeneously in the ground. The precise angular and energy distributions of the gamma rays incident on the human body were taken into account. The organ dose conversion coefficients given in this catalogue were calculated using a Monte Carlo code simulating the photon transport in mathematical models of an adult male and an adult female, respectively. Conversion coefficients are given for the equivalent dose of 23 organs and tissues as well as for effective dose and the equivalent dose of the so-called 'remainder'. The organ equivalent dose conversion coefficients are given separately for the adult male and female models and - as arithmetic mean of the conversion coefficients of both - for an average adult. Fitted data of the coefficients are presented in tables; the primary raw data as resulting from the Monte Carlo calculation are shown in figures together with the fitted data. (orig.)

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

Estimated Internal and External Radiation Exposure of Caregivers of Patients With Pediatric Neuroblastoma Undergoing 131I Metaiodobenzylguanidine Therapy: A Prospective Pilot Study.

Science.gov (United States)

Han, Sangwon; Yoo, Seon Hee; Koh, Kyung-Nam; Lee, Jong Jin

2017-04-01

Current recommendations suggest that family members should participate in the care of children receiving in-hospital I metaiodobenzylguanidine (MIBG) therapy for neuroblastoma. The present study aimed to measure the external radiation exposure and estimate the internal radiation exposure of caregivers during the hospital stay for I MIBG therapy. Caregivers received radiation safety instructions and a potassium iodide solution for thyroid blockade before patient admission. External radiation exposure was determined using a personal pocket dosimeter. Serial 24-hour urine samples were collected from caregivers during the hospital stay. Estimated internal radiation exposure was calculated based on the urine activity. Twelve cases (mean age, 6.2 ± 3.5 years; range, 2-13 years) were enrolled. The mean administered activity was 233.3 ± 74.9 (range, 150.0-350.0) mCi. The mean external radiation dose was 5.8 ± 7.2 (range, 0.8-19.9) mSv. Caregivers of children older than 4 years had significantly less external radiation exposure than those of children younger than 4 years (1.9 ± 1.0 vs 16.4 ± 5.0 mSv; P = 0.012). The mean estimated internal radiation dose was 11.3 ± 10.2 (range, 1.0-29.8) μSv. Caregivers receive both external and internal radiation exposure while providing in-hospital care to children receiving I MIBG therapy for neuroblastoma. However, the internal radiation exposure was negligible compared with the external radiation exposure.

Radiation dosimetry for crewmember exposure to cosmic radiation during astronaut training operations

International Nuclear Information System (INIS)

Shavers, M.R.; Gersey, B.B.; Wilkins, R.T.; Semones, E.J.; Cucinotta, F.A.

2003-01-01

'Atmospheric exposures' of astronauts to cosmic ions and secondary particles during air-flight training are being measured and analytically modeled for inclusion in the astronaut medical records database. For many of the ∼170 astronauts currently in the astronaut corps, their occupational radiation exposure history will be dominated by cosmic ion exposures during air-travel rather than short-duration spaceflight. Relatively low (usually <10 μSv hr -1 ) and uniform organ dose rates result from the penetrating mix of cosmic particles during atmospheric exposures at all altitudes, but at rates that vary greatly due to differences in flight profiles and the geomagnetic conditions at the time of flight. The precision and accuracy to which possible deleterious effects of the exposures can be assessed suffers from limitations that similarly impact assessment of human exposures in low-Earth orbit: uncertainties associated with the environmental measurements and their interpretation, uncertainties associated with the analytical tools that transport the cosmic radiation environment, and uncertain biological responses to low-dose-rate exposures to radiation fields of mixed radiation 'quality'. Lineal energy spectra will be measured using a Tissue Equivalent Proportional Counter designed for training and operational sorties frequently flown in T-38, Space Shuttle Trainer, and high altitude WB-57 aircraft. Linear energy spectra will be measured over multiple flights using CR-39 plastic nuclear track detectors, as well. Flight records are available for nearly 200,000 sorties flown in NASA aircraft by astronauts and flight officers in the Johnson Space Center Aircraft Operations Division over the past 25 years, yet this database only partially documents the complete exposure histories. Age-dependent risk analysis indicates significant impact, particularly to young women who anticipate lengthy on-orbit careers

Radiation Protection Concepts and Quantities for the Occupational Exposure to Cosmic Radiation

International Nuclear Information System (INIS)

Bartlett, D.T.

1999-01-01

For the purposes of dose limitation and dose control, the harm, or detriment, of exposure to radiation is assessed by the quantity effective dose. Effective dose is evaluated by the application of factors to the averaged absorbed dose in the organs and tissues of the body. Radiation monitoring instruments are generally calibrated in terms of the quantity ambient dose equivalent which is defined in a simple spherical phantom. The relationship of these quantities is described. Requirements for the radiation protection of aircraft crew are given in the European Union Council Directive 96/29/EURATOM. There are requirements to assess the exposure of aircraft crew, to inform them of health risks, to reduce higher doses, and to control the dose to the foetus. There are no explicit dose limits, other than a dose objective to be applied to the exposure of the foetus, and no requirements for designation of areas or classification of workers. There are significant differences between the exposure condition of aircraft crew and workers in most other industries where there is occupational exposure to radiation. There are greater ranges of radiation types and energy, and there are different dose distributions and characteristics of the working populations. However, the field intensity is predictable and, with the exception of rare solar events, there is no risk of significant unexpected exposures. Dose assessment is anticipated to be by folding staff roster information with estimates of route doses, since there is little variability of dose rate within an aircraft. Route doses, which may be either an agreed average value for a given airport pairing and aircraft type, or be flight specific, will be closely linked to measured values. Requirements as to the accuracy of dose assessment should be applied which are broadly similar to those used in individual monitoring generally. (author)

Realisation of dosimetric studies for working stations with a risk of exposure to ionizing radiations. Practical guide

International Nuclear Information System (INIS)

Donadille, L.; Queinnec, F.; Bottollier-Depois, J.F.; Clairand, I.; Rehel, J.L.; Deligne, J.M.; Aubert, B.; Jourdain, J.R.; Rannou, A.

2007-01-01

This guide proposes a methodological approach to help carry out dosimetric workplace studies complying with the French regulation, and necessary to identify risks of radiological exposure, optimize radiation protection, classify the workers into different categories and the workplaces into different areas. Additional information is provided relating the main objectives of a workplace study, the French regulatory context, main sources and pathways of exposure to ionizing radiation. Radiation protection and operational quantities are reminded. Recommendations about the selection and use of detectors and about the implementation of calculation methods are also provided. The general methodological approach is applied and developed into 'workplace sheets', each one devoted to a particular type of workplace. (author)

Radiation exposure and image quality in x-Ray diagnostic radiology physical principles and clinical applications

CERN Document Server

Aichinger, Horst; Joite-Barfuß, Sigrid; Säbel, Manfred

2012-01-01

The largest contribution to radiation exposure to the population as a whole arises from diagnostic X-rays. Protecting the patient from radiation is a major aim of modern health policy, and an understanding of the relationship between radiation dose and image quality is of pivotal importance in optimising medical diagnostic radiology. In this volume the data provided for exploring these concerns are partly based on X-ray spectra, measured on diagnostic X-ray tube assemblies, and are supplemented by the results of measurements on phantoms and simulation calculations.

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

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.

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

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.

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.)

Radiation exposure of nuclear medicine procedures in Germany

International Nuclear Information System (INIS)

Hacker, M.

2005-01-01

Nuclear Medicine procedures offer the possibility to detect abnormalities on the basis of physiological and metabolic changes and to treat a growing number of diseases in human beings. However, the use of radiopharmaceuticals for nuclear medicine examinations causes a significant component of the total radiation exposure of populations. In Germany it is an essential task of the Federal Office for Radiation Protection to determinate and assess radiation exposure of the population due to nuclear medicine diagnostics and therapy. An important input for this task is the frequency of nuclear-medical examinations with application of ionising radiation and the radiation exposure of patients related to the various procedures. Additional implementation of age- and gender-specific data today allows more exact risk stratification in focusing on different subgroups of patients. Moreover, the collective effective dose as well as the per caput effective dose of the German population may be estimated and compared with earlier collected data or foreign countries. These data reveal where the indication should be questioned particularly critically and if the dose for the various examinations can be reduced and, thus, contribute to the definition of diagnostic reference levels for nuclear medicine procedures in Germany with the aim of both a sufficient image quality and a minimum of radiation exposure. Exceeding the high- as well as the low-values requires documentation and explanation. (orig.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-04-15

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

Occupational radiation Exposure at Agreement State-Licensed Materials Facilities, 1997-2010

Energy Technology Data Exchange (ETDEWEB)

U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research

2012-07-07

The purpose of this report is to examine occupational radiation exposures received under Agreement State licensees. As such, this report reflects the occupational radiation exposure data contained in the Radiation Exposure Information and Reporting System (REIRS) database, for 1997 through 2010, from Agreement State-licensed materials facilities.

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.

Calculation of Radiation Protection Quantities and Analysis of Astronaut Orientation Dependence

Science.gov (United States)

Clowdsley, Martha S.; Nealy, John E.; Atwell, William; Anderson, Brooke M.; Luetke, Nathan J.; Wilson, John W.

2006-01-01

Health risk to astronauts due to exposure to ionizing radiation is a primary concern for exploration missions and may become the limiting factor for long duration missions. Methodologies for evaluating this risk in terms of radiation protection quantities such as dose, dose equivalent, gray equivalent, and effective dose are described. Environment models (galactic cosmic ray and solar particle event), vehicle/habitat geometry models, human geometry models, and transport codes are discussed and sample calculations for possible lunar and Mars missions are used as demonstrations. The dependence of astronaut health risk, in terms of dosimetric quantities, on astronaut orientation within a habitat is also examined. Previous work using a space station type module exposed to a proton spectrum modeling the October 1989 solar particle event showed that reorienting the astronaut within the module could change the calculated dose equivalent by a factor of two or more. Here the dose equivalent to various body tissues and the whole body effective dose due to both galactic cosmic rays and a solar particle event are calculated for a male astronaut in two different orientations, vertical and horizontal, in a representative lunar habitat. These calculations also show that the dose equivalent at some body locations resulting from a solar particle event can vary by a factor of two or more, but that the dose equivalent due to galactic cosmic rays has a much smaller (<15%) dependence on astronaut orientation.

Information by the German Federal Government. Environmental radioactivity and radiation exposure in 2010

International Nuclear Information System (INIS)

2010-01-01

The information by the German Federal Government on the environmental radioactivity and radiation exposure in 2010 includes five chapters. (I) Natural radiation exposure: radiation sources, contributions from cosmic radiation, contaminated construction materials, food and drinking water, and radon, evaluation of the different components of natural radiation exposure. (II) Civilization caused radiation exposure: nuclear power plants, research centers, nuclear fuel processing plants, other nuclear facilities (interim storage facilities, repositories); summarizing evaluation for nuclear facilities; environmental radioactivity due to mining; radioactive materials in research, technology and households; industrial and mining residues; fall-out as a consequence of the Chernobyl reactor accident and nuclear weapon testing. (III) Occupational radiation exposure: civil radiation sources, natural radiation sources, special events. (IV) Medical radiation exposure; X-ray diagnostics; nuclear medicine; radiotherapy using ionizing radiation; radiotherapy using open radioactive materials; evaluation of radiotherapy. (V) Non-ionizing radiation: electromagnetic fields; optical radiation; certification of solaria.

Investigation research on improvement of safe handling techniques of radiation in medical fields; Reduction of exposure to medical radiation

Energy Technology Data Exchange (ETDEWEB)

Tanaka, Minoru; Watabe, Makoto; Oono, Kuniko [Tokyo Metropolitan Isotope Research Center (Japan)

1990-01-01

Today, it is generally recognized that radiation exposure regardless of its use should be limited to the required minimum. The form of radiation utilization for medical treatment is extremely diverse, and to clarify the actual state of dose that doctors, radiation technicians, nurses and subjects as patients receive by the diagnosis and treatment accompanied by radiation exposure is not only indispensable for evaluating the risk they receive, but also to give the important data for pursuing the reduction of radiation exposure dose of those engaging in medical treatment and patients-subjects. In this investigation research, the actual state of radiation exposure in doctors, radiation technicians, nurses and patients or subjects was investigated, and the radiation exposure dose was measured, in this way the reduction of radiation exposure dose was attempted. The radiation exposure dose in one month was 10.8{+-}3.0 mrem in doctors, 10.4{+-}2.5 mrem in radiation technicians, and 6.3{+-}2.5 mrem in nurses. The risk coefficient in a specific medical university was 1155 men-rem. Also the case of nuclear medical diagnosis administering Ga-67 was measured. (K.I.).

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.

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

Radiation exposure and image quality in X-ray diagnostic radiology. Physical principles and clinical applications. 2. ed.

International Nuclear Information System (INIS)

Saebel, Manfred; Aichinger, Horst; Dierker, Joachim; Joite-Barfuss, Sigrid

2012-01-01

Diagnostic X-rays are the largest contributor to radiation exposure to the general population, and protecting the patient from radiation damage is a major aim of modern health policy. Once the decision has been taken to use ionising radiation for imaging in a particular patient, it is necessary to optimize the image acquisition process taking into account the diagnostic quality of the images and the radiation dose to the patient. Both image quality and radiation dose are affected by a number of parameters, knowledge of which permits scientifically based decision making. The authors of this second edition of Radiation Exposure and Image Quality in X-ray Diagnostic Radiology have spent many years studying the optimization of radiological imaging. In this book they present in detail the basic physical principles of diagnostic radiology and their application to clinical problems. Particular attention is devoted to evaluation of the dose to the patient, the influence of scattered radiation on image quality, the use of antiscatter grids, and optimization of image quality and dose. The final section is a supplement containing tables of data and graphical depictions of X-ray spectra, interaction coefficients, characteristics of X-ray beams, and other aspects relevant to patient dose calculations. In addition, a complementary CD-ROM contains a user-friendly Excel file database covering these aspects that can be used in the reader's own programs. Since the first edition, the text, figures, tables, and references have all been thoroughly updated, and more detailed attention is now paid to image quality and radiation exposure when using digital imaging and computed tomography. This book will be an invaluable aid to medical physicists when performing calculations relating to patient dose and image quality, and will also prove useful for diagnostic radiologists and engineers. (orig.)

Exposure of luminous marine bacteria to low-dose gamma-radiation.

Science.gov (United States)

Kudryasheva, N S; Petrova, A S; Dementyev, D V; Bondar, A A

2017-04-01

The study addresses biological effects of low-dose gamma-radiation. Radioactive 137 Cs-containing particles were used as model sources of gamma-radiation. Luminous marine bacterium Photobacterium phosphoreum was used as a bioassay with the bioluminescent intensity as the physiological parameter tested. To investigate the sensitivity of the bacteria to the low-dose gamma-radiation exposure (≤250 mGy), the irradiation conditions were varied as follows: bioluminescence intensity was measured at 5, 10, and 20°С for 175, 100, and 47 h, respectively, at different dose rates (up to 4100 μGy/h). There was no noticeable effect of gamma-radiation at 5 and 10°С, while the 20°С exposure revealed authentic bioluminescence inhibition. The 20°С results of gamma-radiation exposure were compared to those for low-dose alpha- and beta-radiation exposures studied previously under comparable experimental conditions. In contrast to ionizing radiation of alpha and beta types, gamma-emission did not initiate bacterial bioluminescence activation (adaptive response). As with alpha- and beta-radiation, gamma-emission did not demonstrate monotonic dose-effect dependencies; the bioluminescence inhibition efficiency was found to be related to the exposure time, while no dose rate dependence was found. The sequence analysis of 16S ribosomal RNA gene did not reveal a mutagenic effect of low-dose gamma radiation. The exposure time that caused 50% bioluminescence inhibition was suggested as a test parameter for radiotoxicity evaluation under conditions of chronic low-dose gamma irradiation. Copyright © 2017 Elsevier Ltd. All rights reserved.

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

Lead exposure in radiator repair workers: a survey of Washington State radiator repair shops and review of occupational lead exposure registry data.

Science.gov (United States)

Whittaker, Stephen G

2003-07-01